WorldWideScience

Sample records for forsmark-3 reactor

  1. The World's Reactors no. 70 - Forsmark 3, BWR-75

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    A large pull-out wall chart is presented showing a coloured cut-away diagram of the Forsmark 3 station. It is accompanied by 2 small sketches one showing the layout of station buildings and the other the inside of the reactor vessel. Parameters are listed. (U.K.)

  2. Reactor safety study applied to the Forsmark 3 Power Plant

    International Nuclear Information System (INIS)

    Ericsson, G.; Tiren, L.I.

    1978-01-01

    A reactor safety study of the Forsmark 3 BWR power plant has been carried out for the purpose of calculating core melt probabilities using WASH-1400 methods. A sensitivity analysis shows that the calculated core melt probability is changed by approximately a factor of 10 depending on assumptions made with respect to the probability of human error. The importance of the availability of off-site power and the influence of common cause failure is also discussed. (author)

  3. Safety improvement plant modifications at Forsmark 3, 1986-1995

    Energy Technology Data Exchange (ETDEWEB)

    Kjellander, M. [Kaernkraftsaekerhet och utbildning, Nykoeping (Sweden)

    1998-10-01

    All important plant modifications implemented in safety-related equipment or software at Forsmark 3 are compiled in this report. The report covers the period from the start of commercial operation in 1985 up to and including 1995. The plant modifications, which were carried out by different suppliers during the guarantee period, are not included in the report since they have not been administered by the Forsmark organisation. The report contains references to relevant modification notices and to files and file divider numbers. These data refer to the Safety Department central archives. The report is based on Forsmark 3 Technical Specifications (STF) which means that Chapter 3 is divided into the same sections as in the STF. Modifications, which cannot be directly attributed to any specific STF chapter, and major modifications are described separately

  4. Subsidence analysis Forsmark nuclear power plant - unit 1; Saettningsanalys Forsmarks kaernkraftverk - aggregat 1

    Energy Technology Data Exchange (ETDEWEB)

    Bono, Nancy; Fredriksson, Anders; Maersk Hansen, Lars (Golder Associates AB (Sweden))

    2010-12-15

    On behalf of SKB, Golder Associates Ltd carried out a risk analysis of subsidence during Forsmark nuclear power plant in the construction of the final repository for spent nuclear fuel near and below existing reactors. Specifically, the effect of horizontal cracks have been studied.

  5. Construction experiences from underground works at Forsmark. Compilation Report

    Energy Technology Data Exchange (ETDEWEB)

    Carlsson, Anders [Vattenfall Power Consultant AB, Stockholm (Sweden); Christiansson, Rolf [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

    2007-02-15

    The main objective with this report, the Construction Experience Compilation Report (CECR), is to compile experiences from the underground works carried out at Forsmark, primarily construction experiences from the tunnelling of the two cooling water tunnels of the Forsmark nuclear power units 1, 2 and 3, and from the underground excavations of the undersea repository for low and intermediate reactor waste, SFR. In addition, a brief account is given of the operational experience of the SFR on primarily rock support solutions. The authors of this report have separately participated throughout the entire construction periods of the Forsmark units and the SFR in the capacity of engineering geologists performing geotechnical mapping of the underground excavations and acted as advisors on tunnel support; Anders Carlsson participated in the construction works of the cooling water tunnels and the open cut excavations for Forsmark 1, 2 and 3 (geotechnical mapping) and the Forsmark 3 tunnel (advise on tunnel support). Rolf Christiansson participated in the underground works for the SFR (geotechnical mapping, principal investigator for various measurements and advise on tunnel support and grouting). The report is to a great extent based on earlier published material as presented in the list of references. But it stands to reason that, during the course of the work with this report, unpublished notes, diaries, drawings, photos and personal recollections of the two authors have been utilised in order to obtain such a complete compilation of the construction experiences as possible.

  6. Construction experiences from underground works at Forsmark. Compilation Report

    International Nuclear Information System (INIS)

    Carlsson, Anders; Christiansson, Rolf

    2007-02-01

    The main objective with this report, the Construction Experience Compilation Report (CECR), is to compile experiences from the underground works carried out at Forsmark, primarily construction experiences from the tunnelling of the two cooling water tunnels of the Forsmark nuclear power units 1, 2 and 3, and from the underground excavations of the undersea repository for low and intermediate reactor waste, SFR. In addition, a brief account is given of the operational experience of the SFR on primarily rock support solutions. The authors of this report have separately participated throughout the entire construction periods of the Forsmark units and the SFR in the capacity of engineering geologists performing geotechnical mapping of the underground excavations and acted as advisors on tunnel support; Anders Carlsson participated in the construction works of the cooling water tunnels and the open cut excavations for Forsmark 1, 2 and 3 (geotechnical mapping) and the Forsmark 3 tunnel (advise on tunnel support). Rolf Christiansson participated in the underground works for the SFR (geotechnical mapping, principal investigator for various measurements and advise on tunnel support and grouting). The report is to a great extent based on earlier published material as presented in the list of references. But it stands to reason that, during the course of the work with this report, unpublished notes, diaries, drawings, photos and personal recollections of the two authors have been utilised in order to obtain such a complete compilation of the construction experiences as possible

  7. Man-machine communication at Forsmark 3

    International Nuclear Information System (INIS)

    Hultquist, Goeran; Norberg, Soeren

    1984-01-01

    The design of Forsmark 3 began in 1976 and the control room layout and equipment were discussed right from the start. Susequent evolution and events in other nuclear power plants have, however, radically changed the direction of the development of the man-machine functions. (author)

  8. Lessons from the Forsmark 1 event in Sweden

    International Nuclear Information System (INIS)

    Jorle, A.

    2007-01-01

    A short circuit at a switchyard broke some of the safety chains in the reactor safety system and created a difficult situation in the control room at the Forsmark 1 power plant in Sweden. After a scram two of four diesel generators failed to deliver power but the reactor could safely be controlled through remaining two systems and power could be distributed from external grid after 22 minutes. Surveillance systems in the control room also failed and the situation at the reactor was unclear. Analysis shows that there was never a risk to the public and no damage on the core. The incident exposed unknown weakness in the power supply systems of the reactor. Also it was found that maintenance had failed and some components were not properly installed. The regulator identified the problem as a serious failure but did not at once realize the public impact. The licensee was late in its decision making and did only publish local press releases that did not fully expose the nature of the incident. After some days an independent expert claimed that a core melt was a close possibility. He was widely quoted and created a media impact many European countries. In the light of the incident problems with safety culture was identified at the plant and additional findings showed problems in the management system of Forsmark. Growing media interest culminated in January when a critical internal report from staff members in Forsmark was made public. Some lessons learnt: - Media activity followed well-known patterns. - The regulator was an important source for media. - Regulator not fired upon until January, after a long autumn filled with negative reporting on Forsmark. - The plant was not proactive in its communication which created a problem for the regulator. (author)

  9. District heating from Forsmark

    International Nuclear Information System (INIS)

    1980-11-01

    The district heating system of Greater Stockholm must be based on other energy sources than oil. Two alternatives are assessed, namely heat from Forsmark or a coal fueled plant in the region of Stockholm. Forsmark 3 can produce both electricity and heat from the year 1988 on. The capacity can be increased by coal fueled blocks. For low electricity use, 115 TWh in the year 1990, the Forsmark alternative will be profitable. The alternative will be profitable. The alternative with a fossile fuelled plant will be profitable when planning for high consumption of electricity, 125 TWh. The Forsmark alternative means high investments and the introduction of new techniques. (G.B.)

  10. Market led: Forsmark looks to 2000

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

    The Forsmark nuclear power plant in Sweden includes three BWR reactors totalling 3200 MWe. From a design level of 70% the average capability factor has been increased to 90%. This has been achieved by a market-orientated approach with efficient outages and a total production cost identified with each unit in order to show how each stands in relation to the market price level and to outside competition. Forsmark's performance, as indicated by capacity factors, refuelling outage length and electricity production costs is better than most. Strategic planning is important and a refurbishment programme up to 2000 is planned to renew the electricity generators, replace the process computers and upgrade the preheater systems. (UK)

  11. Subsidence analysis Forsmark nuclear power plant - unit 1

    International Nuclear Information System (INIS)

    Bono, Nancy; Fredriksson, Anders; Maersk Hansen, Lars

    2010-12-01

    On behalf of SKB, Golder Associates Ltd carried out a risk analysis of subsidence during Forsmark nuclear power plant in the construction of the final repository for spent nuclear fuel near and below existing reactors. Specifically, the effect of horizontal cracks have been studied

  12. Forsmark - site descriptive model version 0

    International Nuclear Information System (INIS)

    2002-10-01

    area identified in the feasibility study as favourable for further study. This rectangular area has now been designated the Forsmark regional model area. An important component of the present work is a data inventory, in which the location and scope of all potential sources of data is detailed and evaluated with respect to prospective usefulness for future site descriptive modelling for deep disposal. Data sources relevant to the Forsmark regional model area which still, to some degree, need to be evaluated/converted/inserted include the siting and construction of the three nuclear reactors (Forsmark 1-3), the feasibility study for an underground spent nuclear fuel interim storage facility at Forsmark, the pre-investigations and construction of the SFR, and the SAFE project. The present report describes the current level of knowledge of the surface ecosystems in the Forsmark regional model area, in a highly condensed form. It refers to, and draws its examples from, a series of SKB background reports which have been produced since the completion of the Oesthammar feasibility study, and a number of other sources of information which are gathered here for the first time. The data sources are outlined with reference to a series of functional ecosystem types: drainage areas, forest, wetland, agricultural land, lakes and rivers, and sea, each further subdivided into appropriate entities. A systematic approach has been used, even though, at the current level of knowledge, the information in many subdivisions is inadequate or lacking. The aims of biosphere studies within the site investigation programme are to define baseline (preconstruction) conditions, to provide the necessary data base for the environmental impact statement, and to contribute to the dose estimations in the safety analysis. The main emphasis of the report is on the preparation of a site descriptive model, version 0, for the geosphere, since data acquisition and processing in this area, in contrast to the

  13. Forsmark - site descriptive model version 0

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-10-01

    area identified in the feasibility study as favourable for further study. This rectangular area has now been designated the Forsmark regional model area. An important component of the present work is a data inventory, in which the location and scope of all potential sources of data is detailed and evaluated with respect to prospective usefulness for future site descriptive modelling for deep disposal. Data sources relevant to the Forsmark regional model area which still, to some degree, need to be evaluated/converted/inserted include the siting and construction of the three nuclear reactors (Forsmark 1-3), the feasibility study for an underground spent nuclear fuel interim storage facility at Forsmark, the pre-investigations and construction of the SFR, and the SAFE project. The present report describes the current level of knowledge of the surface ecosystems in the Forsmark regional model area, in a highly condensed form. It refers to, and draws its examples from, a series of SKB background reports which have been produced since the completion of the Oesthammar feasibility study, and a number of other sources of information which are gathered here for the first time. The data sources are outlined with reference to a series of functional ecosystem types: drainage areas, forest, wetland, agricultural land, lakes and rivers, and sea, each further subdivided into appropriate entities. A systematic approach has been used, even though, at the current level of knowledge, the information in many subdivisions is inadequate or lacking. The aims of biosphere studies within the site investigation programme are to define baseline (preconstruction) conditions, to provide the necessary data base for the environmental impact statement, and to contribute to the dose estimations in the safety analysis. The main emphasis of the report is on the preparation of a site descriptive model, version 0, for the geosphere, since data acquisition and processing in this area, in contrast to the

  14. Bedrock hydrogeology Forsmark. Site descriptive modelling, SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Follin, Sven (SF GeoLogic AB, Taeby (Sweden))

    2008-12-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has conducted site investigations at two different locations, the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a final repository for spent nuclear fuel according to the KBS-3 concept. Site characterisation should provide all data required for an integrated evaluation of the suitability of the investigated site and an important component in the characterisation work is the development of a hydrogeological model. The hydrogeological model is used by repository engineering to design the underground facility and to develop a repository layout adapted to the site. It also provides input to the safety assessment. Another important use of the hydrogeological model is in the environmental impact assessment. This report presents the understanding of the hydrogeological conditions of the bedrock at Forsmark reached following the completion of the surface-based investigations and provides a summary of the bedrock hydrogeological model and the underlying data supporting its development. It constitutes the main reference on bedrock hydrogeology for the site descriptive model concluding the surface-based investigations at Forsmark, SDM-site, and is intended to describe the hydraulic properties and hydrogeological conditions of the bedrock at the site and to give the information essential for demonstrating understanding

  15. A safety assessment approach using coupled NEAR3D and CHAN3D - Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Liu, Longcheng; Moreno, Luis; Neretnieks, Ivars (Dept. of Chemical Engineering and Technology, Royal Inst. of Technology, Stockholm (Sweden)); Gylling, Bjoern (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden))

    2010-12-15

    Safety assessment calculations for the Forsmark site were performed using a new code, which couples the far-field code CHAN3D and the near-field code NEAR3D. In addition, the package has a Graphical User Interface (GUI) and a code that governs the simulations (Coupling). The simulations were performed for 90 different canister locations, which were randomly chosen. Deterministic data were used for tunnels, deposition holes, and shafts. The background fractures were stochastically generated in two HRD realizations. The F-ratio and the water travel time distributions were used to study the performance of the simulations. Near-field calculations were not performed for the Forsmark site using the new coded presented in the prevailing report. However, the obtained results in this study are compared with the results from the Task 2 model of the ConnectFlow report /Joyce et al. 2010/. Although the results cannot be compared directly, a reasonably good agreement is obtained for the F-ratio

  16. Work at Forsmark since ASSET 1996

    Energy Technology Data Exchange (ETDEWEB)

    Loewenhielm, G; Andersson, O [Forsmark Kraftgrupp AB, Oesthammar (Sweden)

    1997-10-01

    The following directions of work at Forsmark since ASSET 1996 are briefly described: peer review follow-up; work related to peer review, Forsmark 2 mini-ASSET; MTO(man-technology-organization)-analysis method, concept development, combination of MTO and ASSET methods; Forsmark INES manual.

  17. Reflection seismic studies in the Forsmark area - stage 1

    Energy Technology Data Exchange (ETDEWEB)

    Juhlin, Christopher; Bergman Bjoern; Palm, Hans [Uppsala Univ. (Sweden). Dept. of Earth Sciences

    2002-10-01

    Reflection seismic data were acquired in the Spring of 2002 in the Forsmark area, located about 70 km northeast of Uppsala, Sweden. The Forsmark area has been targeted by SKB as a possible storage site for high level radioactive waste. About 16 km of high resolution seismic data were acquired along five separate profiles varying in length from 2 to 5 km. Non-final source and receiver spacing was 10 m with 100 active channels when recording data from a dynamite source (15-75 g). The profiles were located within a relatively undeformed lens of bedrock that trends in the NW-SE direction. The lens is surrounded by highly deformed rock on all sides. In conjunction with the reflection component of the study, all shots were also recorded on up to eleven 3-component fixed Orion seismographs. These recordings provided long offset data from which a velocity model of the uppermost 400 m of bedrock could be derived. Results from the study show that the bedrock has been well imaged down to depths of at least 3 km. The upper 1000 m of bedrock is much more reflective in the southeastern portion of the lens compared to the northwestern part close to the Forsmark reactors. This is interpreted as the bedrock being more homogeneous in the northwest. However, a major reflective zone (the A1 reflector) is interpreted to dip to the S-SE below this homogeneous bedrock. In the southeastern portion of the lens the orientation of the reflectors is well determined where the profiles cross one another. The general strike of the major reflectors is NE-SW with dips of 20-35 degrees to the southeast.

  18. Monitoring Forsmark. Moose age composition, reproduction and antler development in Forsmark; Monitoring Forsmark. Aelgstammens aalderssammansaettning reproduktion och hornutveckling i Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Cederlund, Goeran; Broman, Emil (Svensk Naturfoervaltning AB (Sweden))

    2011-05-15

    The moose (Alces alces) is an important game species in Forsmark, as well as in Sweden in general. Hunting on moose is subject to strict local regulations and restrictions within a management program. Such restrictions will have considerable effects on demography. This has led to a moose population in Forsmark with biased sex ratio with fewer adult males than females and a generally low average age. High hunting pressure on males has caused a low survival rate and the chance to survive more than five years is just a few percent. Restrictions in hunting pressure on females have caused a generally higher survival rate and a higher average age compared to males. Sex differences in body mass are normal compared to other populations in southern Sweden. Mean body mass of culled calves is an important measure of quality of the population, since it reflects the available food resources in the management area. Body mass among calves in Forsmark is generally low, indicating a deteriorated food resource due to either ambient population density and/or hampered food production in the forest. The average reproduction rate is normal compared to other populations in this part of Sweden. However, one year old females (yearlings) have a fairly low production of eggs per female (ovulation rate). As the yearlings constitute a considerable part of the population in Forsmark, their lowered ovulation rate will affect the rate of recruitment of calves to the local population. The moose population seems to have been subject to considerable variation in density during the last decade, which is probably a joint effect of changes in demography (hunting), changes in food resources due to forestry management and by food competition from other browsers in the area. Local managers believe that the population has reached such a low level (although not verified by surveys) that the number of moose has to be increased. It is vital to stress the importance of keeping up collection of data from the

  19. Encapsulation plant at Forsmark

    International Nuclear Information System (INIS)

    Nystroem, Anders

    2007-08-01

    SKB has already carried out a preliminary study of an encapsulation plant detached from Clab (Central interim storage for spent fuels). This stand-alone encapsulation plant was named FRINK and its assumed siting was the above-ground portion of the final repository, irrespective of the repository's location. The report previously presented was produced in cooperation with BNFL Engineering Ltd in Manchester and the fuel reception technical solution was examined by Gesellschaft fuer Nuklear-Service mbH (GNS) in Hannover and by Societe Generale pour les Techniques Nouvelles (SGN) in Paris. This report is an update of the earlier preliminary study report and is based on the assumption that the encapsulation plant and also the final repository will be sited in the Forsmark area. SKB's main alternative for siting the encapsulation plant is next to Clab. Planning of this facility is ongoing and technical solutions from the planning work have been incorporated in this report. An encapsulation plant placed in proximity to any final repository in Forsmark forms part of the alternative presentation in the application for permission to construct and operate an installation at Clab. The main technical difference between the planned encapsulation plant at Clab and an encapsulation plant at a final repository at Forsmark is how the fuel is managed and prepared before actual encapsulation. Fuel reception at the encapsulation plant in Forsmark would be dry, i.e. there would be no water-filled pools at the facility. Clab is used for verificatory fuel measurements, sorting and drying of the fuel before transport to Forsmark. This means that Clab will require a measure of rebuilding and supplementary equipment. In purely technical terms, the prospects for building an encapsulation plant sited at Forsmark are good. A description of the advantages and drawbacks of siting the encapsulation plant at Clab as opposed to any final repository at Forsmark is presented in a separate report

  20. Encapsulation plant at Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Nystroem, Anders

    2007-08-15

    SKB has already carried out a preliminary study of an encapsulation plant detached from Clab (Central interim storage for spent fuels). This stand-alone encapsulation plant was named FRINK and its assumed siting was the above-ground portion of the final repository, irrespective of the repository's location. The report previously presented was produced in cooperation with BNFL Engineering Ltd in Manchester and the fuel reception technical solution was examined by Gesellschaft fuer Nuklear-Service mbH (GNS) in Hannover and by Societe Generale pour les Techniques Nouvelles (SGN) in Paris. This report is an update of the earlier preliminary study report and is based on the assumption that the encapsulation plant and also the final repository will be sited in the Forsmark area. SKB's main alternative for siting the encapsulation plant is next to Clab. Planning of this facility is ongoing and technical solutions from the planning work have been incorporated in this report. An encapsulation plant placed in proximity to any final repository in Forsmark forms part of the alternative presentation in the application for permission to construct and operate an installation at Clab. The main technical difference between the planned encapsulation plant at Clab and an encapsulation plant at a final repository at Forsmark is how the fuel is managed and prepared before actual encapsulation. Fuel reception at the encapsulation plant in Forsmark would be dry, i.e. there would be no water-filled pools at the facility. Clab is used for verificatory fuel measurements, sorting and drying of the fuel before transport to Forsmark. This means that Clab will require a measure of rebuilding and supplementary equipment. In purely technical terms, the prospects for building an encapsulation plant sited at Forsmark are good. A description of the advantages and drawbacks of siting the encapsulation plant at Clab as opposed to any final repository at Forsmark is presented in a separate

  1. Investigation of BWR stability in Forsmark 2

    International Nuclear Information System (INIS)

    Oguma, R.; Reisch, F.; Bergdahl, B.G.; Lorenzen, J.; Aakerhielm, F.; Kellner, S.

    1988-01-01

    A series of noise measurements have been conducted at the Forsmark-2 reactor during its start-up operation after the revision in 1987. The main purpose was to investigate the BWR stability problem based on noise analysis, i.e. the problem of resonant power oscillation with frequency of about 0.5 Hz, which tends to arise at high power and low core flow condition. The noise analysis was performed to estimate the noise source which gives rise to the power oscillation, to evaluate the stability condition of the Forsmark-2 reactor in terms of the decay ratio (DR), as well as to investigate a safety related problem in connection with the BWR stability. The results indicate that the power oscillation is due to dynamic coupling between the neutron kinetics and thermal-hydraulics via void reactivity feedback. The DR reached as high as ≅ 0.7 at 63% of the rated power and 4100 kg/s of the total core flow. An investigation was made for the noise recording which represents a strong pressure oscillation with a peak frequency at 0.33 Hz. The result suggests that such pressure oscillation, if the peak frequency coincided with that of the resonant power oscillation, might become a cause of scram. The present noise analysis indicates the importance of a BWR on-line surveillance system with functions like stability condition monitoring and control system diagnosis. (orig.)

  2. Forsmark - System 522. Recursive linear regression for the determination of heating rate

    International Nuclear Information System (INIS)

    Carlsson, B.

    1980-01-01

    The heating rate for reactor tank and steam tubes is limited. The algorithm of the heating rate has been implemented on the computer and compared with real data from Forsmark-2. The evaluation of data shows a considerable improvement of the determination of derivata which contributes to information during heating events. (G.B.)

  3. Human population and activities in Forsmark. Site description

    Energy Technology Data Exchange (ETDEWEB)

    Miliander, Sofia; Punakivi, Mari; Kylaekorpi, Lasse; Rydgren, Bernt [SwedPower AB, Stockholm (Sweden)

    2004-12-01

    The Swedish Nuclear Fuel and Waste Management Co (SKB) is in the process of selecting a safe and environmentally acceptable location for a deep repository of radioactive waste. Two alternative locations are under investigation. These are Forsmark, Oesthammars kommun (kommun = municipality) and Simpevarp/Laxemar, Oskarshamns kommun. SKB has expressed the importance of describing the humans and their activities in these areas and therefore has this synthesis concerning the human population in Forsmark been produced.The description is a statistical synthesis, mainly based upon statistical data from SCB (Statistics Sweden) that has been collected, processed and analysed. The statistical data has not been verified through site inspections and interviews. When using statistical data, it is advisable to note that the data becomes more unreliable if the areas are small, with small populations.The data in this description is essential for future evaluations of the impact on the environment and its human population (Environmental Impact Assessments). The data is also important when modelling the potential flows of radio nuclides and calculating the risk of exposure in future safety assessments.The actual area for the study is in this report called 'the Forsmark area', an area of 19.5 km{sup 2} near Forsmark nuclear power plant. The land use in the Forsmark area differs notably from the land use in Uppsala laen (laen = county). Only 0.04% of the total area is developed (built-up) compared to 4.9% in Uppsala laen and only 4% is agricultural land compared to 25% in the county. Furthermore, there are far more forest, wetlands and water areas in the Forsmark area. The forest area represents as much as 72.5% of the total area.The Forsmark area is uninhabited, and its surroundings are very sparsely populated. In 2002, the population density in Forsmark was 1.8 inhabitants per square kilometre, which was 24 times lower than in Uppsala laen. The population density in the

  4. Human population and activities in Forsmark. Site description

    International Nuclear Information System (INIS)

    Miliander, Sofia; Punakivi, Mari; Kylaekorpi, Lasse; Rydgren, Bernt

    2004-12-01

    The Swedish Nuclear Fuel and Waste Management Co (SKB) is in the process of selecting a safe and environmentally acceptable location for a deep repository of radioactive waste. Two alternative locations are under investigation. These are Forsmark, Oesthammars kommun (kommun = municipality) and Simpevarp/Laxemar, Oskarshamns kommun. SKB has expressed the importance of describing the humans and their activities in these areas and therefore has this synthesis concerning the human population in Forsmark been produced.The description is a statistical synthesis, mainly based upon statistical data from SCB (Statistics Sweden) that has been collected, processed and analysed. The statistical data has not been verified through site inspections and interviews. When using statistical data, it is advisable to note that the data becomes more unreliable if the areas are small, with small populations.The data in this description is essential for future evaluations of the impact on the environment and its human population (Environmental Impact Assessments). The data is also important when modelling the potential flows of radio nuclides and calculating the risk of exposure in future safety assessments.The actual area for the study is in this report called 'the Forsmark area', an area of 19.5 km 2 near Forsmark nuclear power plant. The land use in the Forsmark area differs notably from the land use in Uppsala laen (laen = county). Only 0.04% of the total area is developed (built-up) compared to 4.9% in Uppsala laen and only 4% is agricultural land compared to 25% in the county. Furthermore, there are far more forest, wetlands and water areas in the Forsmark area. The forest area represents as much as 72.5% of the total area.The Forsmark area is uninhabited, and its surroundings are very sparsely populated. In 2002, the population density in Forsmark was 1.8 inhabitants per square kilometre, which was 24 times lower than in Uppsala laen. The population density in the parish has been

  5. Forsmark site investigation. Interpretation of topographic lineaments 2002

    International Nuclear Information System (INIS)

    Isaksson, Hans

    2003-04-01

    SKB performs site investigations for localization of a deep repository for high level radioactive waste. The site investigations are performed in two municipalities; Oesthammar and Oskarshamn. The Forsmark investigation area is situated in Oesthammar, close to the Forsmark nuclear power plant. The purpose of interpretation of lineaments from topographic data is to identify linear features (lineaments), which may correspond to deformation zones in the bedrock. The data will be combined with interpretations of lineaments from airborne geophysical data in order to produce an integrated lineament interpretation for the Forsmark area. This integrated interpretation will be combined with geological data in order to establish a bedrock geological map of the Forsmark area. The area for the lineament interpretation is the same as that selected for the bedrock mapping activities during 2002, i.e. the land area around Forsmark

  6. Monitoring Forsmark. Moose age composition, reproduction and antler development in Forsmark

    International Nuclear Information System (INIS)

    Cederlund, Goeran; Broman, Emil

    2011-05-01

    The moose (Alces alces) is an important game species in Forsmark, as well as in Sweden in general. Hunting on moose is subject to strict local regulations and restrictions within a management program. Such restrictions will have considerable effects on demography. This has led to a moose population in Forsmark with biased sex ratio with fewer adult males than females and a generally low average age. High hunting pressure on males has caused a low survival rate and the chance to survive more than five years is just a few percent. Restrictions in hunting pressure on females have caused a generally higher survival rate and a higher average age compared to males. Sex differences in body mass are normal compared to other populations in southern Sweden. Mean body mass of culled calves is an important measure of quality of the population, since it reflects the available food resources in the management area. Body mass among calves in Forsmark is generally low, indicating a deteriorated food resource due to either ambient population density and/or hampered food production in the forest. The average reproduction rate is normal compared to other populations in this part of Sweden. However, one year old females (yearlings) have a fairly low production of eggs per female (ovulation rate). As the yearlings constitute a considerable part of the population in Forsmark, their lowered ovulation rate will affect the rate of recruitment of calves to the local population. The moose population seems to have been subject to considerable variation in density during the last decade, which is probably a joint effect of changes in demography (hunting), changes in food resources due to forestry management and by food competition from other browsers in the area. Local managers believe that the population has reached such a low level (although not verified by surveys) that the number of moose has to be increased. It is vital to stress the importance of keeping up collection of data from the

  7. Safety-related site characteristics - a relative comparison of the Forsmark reference areas; Saekerhetsrelaterade platsegenskaper - en relativ jaemfoerelse av Forsmark med referensomraaden

    Energy Technology Data Exchange (ETDEWEB)

    Winberg, Anders (Conterra AB, Uppsala (Sweden))

    2010-12-15

    SKB has over the years from 2002 to 2008 conducted site investigations in Forsmark and Laxemar, with associated site modeling, design and safety analysis. In mid-2009 Forsmark was selected on the basis of analysis made as site for a future repository for spent nuclear fuel. Based on defined safety-related geoscientific location factors data from Forsmark are compared in relative terms with data from a number of locations in Sweden, previously studied by SKB. The factors compared include: the rock's composition and structures, future climate evolution, rock mechanical conditions, earthquakes, groundwater flow, groundwater composition, delay of solutes, and the ability to characterize and describe the location. Past comparisons of these properties for the selected sites show that none of these sites collectively show any significant benefit over Forsmark site for a repository. This does not preclude that there may be places on the basis of an overall assessment of geoscientific location factors could be equivalent to Forsmark

  8. Impact of modeling Choices on Inventory and In-Cask Criticality Calculations for Forsmark 3 BWR Spent Fuel

    International Nuclear Information System (INIS)

    Martinez-Gonzalez, Jesus S.; Ade, Brian J.; Bowman, Stephen M.; Gauld, Ian C.; Ilas, Germina; Marshall, William BJ J.

    2015-01-01

    Simulation of boiling water reactor (BWR) fuel depletion poses a challenge for nuclide inventory validation and nuclear criticality safety analyses. This challenge is due to the complex operating conditions and assembly design heterogeneities that characterize these nuclear systems. Fuel depletion simulations and in-cask criticality calculations are affected by (1) completeness of design information, (2) variability of operating conditions needed for modeling purposes, and (3) possible modeling choices. These effects must be identified, quantified, and ranked according to their significance. This paper presents an investigation of BWR fuel depletion using a complete set of actual design specifications and detailed operational data available for five operating cycles of the Swedish BWR Forsmark 3 reactor. The data includes detailed axial profiles of power, burnup, and void fraction in a very fine temporal mesh for a GE14 (10x10) fuel assembly. The specifications of this case can be used to assess the impacts of different modeling choices on inventory prediction and in-cask criticality, specifically regarding the key parameters that drive inventory and reactivity throughout fuel burnup. This study focused on the effects of the fidelity with which power history and void fraction distributions are modeled. The corresponding sensitivity of the reactivity in storage configurations is assessed, and the impacts of modeling choices on decay heat and inventory are addressed.

  9. Forsmark NPP I and C modernization strategy

    International Nuclear Information System (INIS)

    Hallen, J.; Rydahl, I.; Kloow, L.

    2003-01-01

    By the year 2000, the Forsmark NPP was halfway through the planned plant life. As early as 1995, Forsmark realized that the old analog I and C equipment would need to be replaced before 2005. At the Forsmark NPP they had strength of a vision of an integrated modernization and a strategy to reach the vision. Without vision and strategy, the plant could end up with a fragmented plant I and C-architecture that is not cost-effective or operable. This paper will address several questions that led to the current modernization program in Forsmark, the more important questions are: What would happen if the modernization would be postponed? Which main requirements were to be achieved by means of the modernization strategy? The goal of a completed plant modernization program is a totally integrated system solution and what factors were considered during the modernization? How to gain acceptance from the operational staff in designing Control Room and Soft Control Displays? What are the important roles for the staff and organization to reach the end goal? What has been the experience to date and what are the lessons learned? Thanks to the long term co-operation between Forsmark and Westinghouse the modernization has been very successful for both parties. (orig.)

  10. Bioturbation in different ecosystems at Forsmark and Oskarshamn

    Energy Technology Data Exchange (ETDEWEB)

    Persson, Tryggve; Lenoir, Lisette; Taylor, Astrid [Dept. of Ecology and Environmental Research, Swedish University or Agricultural Sciences, Uppsala (Sweden)

    2007-01-15

    The Swedish Nuclear Fuel and Waste Management Co (SKB) carries out extensive investigations on factors that can affect long-term storage of nuclear waste. Earthworms consume organic soil materials and when doing so they transport and mix mineral soil particles as well as litter and humus materials. Ants do not consume soil materials, but they collect and mix mineral soil particles and litter materials to construct their nests. This process of material displacement by earthworms and ants is called bioturbation and can be a mechanism for the redistribution (vertical and horizontal) of radionuclides within the soil profile. The aim of the present study was to determine the quantitative impact of earthworms and ants on bioturbation of soil in different ecosystems at Forsmark and Oskarshamn. Earthworms were sampled at four 20x20 cm{sup 2} sub-plots at each site and were determined, dried and weighed in the laboratory. Gut passage time and faeces production were determined in a laboratory experiment at constant temperature. Temperature dependence of earthworm growth was studied at 3, 6, 10 and 20 deg C, and it was assumed that defecation mirrored growth as regards temperature dependence. Ant species composition, ant nest density and nest volume were investigated in the field by using pitfall traps and a transect method to enumerate ant nests. Dry weights of ant nests were determined after weighing in the laboratory. Earthworm abundances and biomasses were high in moist/wet alder forests and deciduous woodlands and low in pine and pine/spruce forests at both Forsmark and Oskarshamn. In mesic spruce forests, high estimates of abundance/biomass of earthworms were found at Forsmark but low at Oskarshamn, whereas grazed pastures had high estimates at Oskarshamn and ungrazed abandoned fields had relatively low estimates at Forsmark. High pH at Forsmark and low pH at Oskarshamn as well as high groundwater tables at some of the Forsmark sites can explain the difference between

  11. Bioturbation in different ecosystems at Forsmark and Oskarshamn

    International Nuclear Information System (INIS)

    Persson, Tryggve; Lenoir, Lisette; Taylor, Astrid

    2007-01-01

    The Swedish Nuclear Fuel and Waste Management Co (SKB) carries out extensive investigations on factors that can affect long-term storage of nuclear waste. Earthworms consume organic soil materials and when doing so they transport and mix mineral soil particles as well as litter and humus materials. Ants do not consume soil materials, but they collect and mix mineral soil particles and litter materials to construct their nests. This process of material displacement by earthworms and ants is called bioturbation and can be a mechanism for the redistribution (vertical and horizontal) of radionuclides within the soil profile. The aim of the present study was to determine the quantitative impact of earthworms and ants on bioturbation of soil in different ecosystems at Forsmark and Oskarshamn. Earthworms were sampled at four 20x20 cm 2 sub-plots at each site and were determined, dried and weighed in the laboratory. Gut passage time and faeces production were determined in a laboratory experiment at constant temperature. Temperature dependence of earthworm growth was studied at 3, 6, 10 and 20 deg C, and it was assumed that defecation mirrored growth as regards temperature dependence. Ant species composition, ant nest density and nest volume were investigated in the field by using pitfall traps and a transect method to enumerate ant nests. Dry weights of ant nests were determined after weighing in the laboratory. Earthworm abundances and biomasses were high in moist/wet alder forests and deciduous woodlands and low in pine and pine/spruce forests at both Forsmark and Oskarshamn. In mesic spruce forests, high estimates of abundance/biomass of earthworms were found at Forsmark but low at Oskarshamn, whereas grazed pastures had high estimates at Oskarshamn and ungrazed abandoned fields had relatively low estimates at Forsmark. High pH at Forsmark and low pH at Oskarshamn as well as high groundwater tables at some of the Forsmark sites can explain the difference between

  12. Surface system Forsmark. Site descriptive modelling SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Lindborg, Tobias [ed.

    2008-12-15

    SKB has undertaken site characterization of two different areas, Forsmark and Laxemar-Simpevarp, in order to find a suitable location for a geological repository for spent nuclear fuel. This report focuses on the site descriptive modelling of the surface system at Forsmark. The characterization of the surface system at the site was primarily made by identifying and describing important properties in different parts of the surface system, properties concerning e.g. hydrology and climate, Quaternary deposits and soils, hydrochemistry, vegetation, ecosystem functions, but also current and historical land use. The report presents available input data, methodology for data evaluation and modelling, and resulting models for each of the different disciplines. Results from the modelling of the surface system are also integrated with results from modelling of the deep bedrock system. The Forsmark site is located within the municipality of Oesthammar, about 120 km north of Stockholm. The investigated area is located along the shoreline of Oeregrundsgrepen, a funnel-shaped bay of the Baltic Sea. The area is characterized by small-scale topographic variations and is almost entirely located at altitudes lower than 20 metres above sea level. The Quaternary deposits in the area are dominated by till, characterized by a rich content of calcite which was transported by the glacier ice to the area from the sedimentary bedrock of Gaevlebukten about 100 km north of Forsmark. As a result, the surface waters and shallow groundwater at Forsmark are characterized by high pH values and high concentrations of certain major constituents, especially calcium and bicarbonate. The annual precipitation and runoff are 560 and 150 mm, respectively. The lakes are small and shallow, with mean and maximum depths ranging from approximately 0.1 to 1 m and 0.4 to 2 m. Sea water flows into the most low-lying lakes during events giving rise to very high sea levels. Wetlands are frequent and cover 25 to 35

  13. Surface system Forsmark. Site descriptive modelling SDM-Site Forsmark

    International Nuclear Information System (INIS)

    Lindborg, Tobias

    2008-12-01

    SKB has undertaken site characterization of two different areas, Forsmark and Laxemar-Simpevarp, in order to find a suitable location for a geological repository for spent nuclear fuel. This report focuses on the site descriptive modelling of the surface system at Forsmark. The characterization of the surface system at the site was primarily made by identifying and describing important properties in different parts of the surface system, properties concerning e.g. hydrology and climate, Quaternary deposits and soils, hydrochemistry, vegetation, ecosystem functions, but also current and historical land use. The report presents available input data, methodology for data evaluation and modelling, and resulting models for each of the different disciplines. Results from the modelling of the surface system are also integrated with results from modelling of the deep bedrock system. The Forsmark site is located within the municipality of Oesthammar, about 120 km north of Stockholm. The investigated area is located along the shoreline of Oeregrundsgrepen, a funnel-shaped bay of the Baltic Sea. The area is characterized by small-scale topographic variations and is almost entirely located at altitudes lower than 20 metres above sea level. The Quaternary deposits in the area are dominated by till, characterized by a rich content of calcite which was transported by the glacier ice to the area from the sedimentary bedrock of Gaevlebukten about 100 km north of Forsmark. As a result, the surface waters and shallow groundwater at Forsmark are characterized by high pH values and high concentrations of certain major constituents, especially calcium and bicarbonate. The annual precipitation and runoff are 560 and 150 mm, respectively. The lakes are small and shallow, with mean and maximum depths ranging from approximately 0.1 to 1 m and 0.4 to 2 m. Sea water flows into the most low-lying lakes during events giving rise to very high sea levels. Wetlands are frequent and cover 25 to 35

  14. Site description of Forsmark at completion of the site investigation phase. SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    2008-12-15

    The Swedish Nuclear Fuel and Waste Management Co., SKB, has undertaken site characterisation in two different areas, Forsmark and Laxemar-Simpevarp, in order to identify a suitable location for a geological repository of spent nuclear fuel according to the KBS-3 method. The site investigations have been conducted in campaigns, punctuated by data freezes. After each data freeze, the site data have been analysed and modelling has been carried out with the overall purpose to develop a site descriptive model (SDM). The site descriptive model is used by repository engineering to design the underground facility and to develop a repository layout adapted to the site. It is also essential for safety assessment, since the model is the only source for site-specific input. Another important use of the site descriptive model is in the environmental impact assessment. An SDM is an integrated model for geology, thermal properties, rock mechanics, hydrogeology, hydrogeochemistry, bedrock transport properties and a description of the surface system. The site descriptive model compiled in the current report, SDM-Site, presents an integrated understanding of the Forsmark area at the completion of the surface-based investigations, which were conducted at Forsmark during the period 2002 to 2007. It also provides a summary of the abundant underlying data and the discipline-specific models that support the site understanding. The description relies heavily on background reports that address, in particular, details in data analyses and modelling in the different disciplines. The Forsmark area is located in northern Uppland within the municipality of Oesthammar, about 120 km north of Stockholm. The candidate area for site investigation is located along the shoreline of Oeregrundsgrepen, within the north-western part of a major tectonic lens that formed between 1.87 and 1.85 billion years ago during the Svecokarelian orogeny. The candidate area is approximately 6 km long and 2 km wide. The

  15. Site description of Forsmark at completion of the site investigation phase. SDM-Site Forsmark

    International Nuclear Information System (INIS)

    2008-12-01

    The Swedish Nuclear Fuel and Waste Management Co., SKB, has undertaken site characterisation in two different areas, Forsmark and Laxemar-Simpevarp, in order to identify a suitable location for a geological repository of spent nuclear fuel according to the KBS-3 method. The site investigations have been conducted in campaigns, punctuated by data freezes. After each data freeze, the site data have been analysed and modelling has been carried out with the overall purpose to develop a site descriptive model (SDM). The site descriptive model is used by repository engineering to design the underground facility and to develop a repository layout adapted to the site. It is also essential for safety assessment, since the model is the only source for site-specific input. Another important use of the site descriptive model is in the environmental impact assessment. An SDM is an integrated model for geology, thermal properties, rock mechanics, hydrogeology, hydrogeochemistry, bedrock transport properties and a description of the surface system. The site descriptive model compiled in the current report, SDM-Site, presents an integrated understanding of the Forsmark area at the completion of the surface-based investigations, which were conducted at Forsmark during the period 2002 to 2007. It also provides a summary of the abundant underlying data and the discipline-specific models that support the site understanding. The description relies heavily on background reports that address, in particular, details in data analyses and modelling in the different disciplines. The Forsmark area is located in northern Uppland within the municipality of Oesthammar, about 120 km north of Stockholm. The candidate area for site investigation is located along the shoreline of Oeregrundsgrepen, within the north-western part of a major tectonic lens that formed between 1.87 and 1.85 billion years ago during the Svecokarelian orogeny. The candidate area is approximately 6 km long and 2 km wide. The

  16. Electric failure on the reactor n.3 of the nuclear power plant of Dampierre

    International Nuclear Information System (INIS)

    2007-05-01

    This note of information resumes the progress of the electric failure on the reactor n.3 of the nuclear power plant of Dampierre, the organization during the incident, it establishes then a comparison with the incident arisen to Forsmark in 2006 and reminds that it lead in an inspection on behalf of the Asn which noticed that all the procedures had been respected by the operators and did not noticed any abnormality in the maintenance. This event was classified at the level 1 of the international nuclear event scale (INES). (N.C.)

  17. Validation of the marine vegetation model in Forsmark. SFR-Site Forsmark

    International Nuclear Information System (INIS)

    Aquilonius, Karin; Qvarfordt, Susanne; Borgiel, Micke

    2011-04-01

    A regression model implemented in GIS of the marine vegetation in Forsmark were developed by SKB /Aquilonius 2010/ based on field investigations and video surveys /Fredriksson 2005/ and from correlations of field data and physical properties /Carlen et al. 2007/. The marine vegetation model describes distribution and biomasses of the marine vegetation and is used as input data in the dose modeling within the safety assessments performed by the SKB. In this study the predictive performance of the vegetation model in the less examined parts of the marine area in Forsmark is evaluated. In general, the vegetation model works very well in predicting absence of biomass, except for Red algae. In total and for Fucus sp., the model also predicts the observed biomass fairly well. However, for phanerogams, Chara sp., filamentous algae and red algae the vegetation model works less well in predicting biomass

  18. Validation of the marine vegetation model in Forsmark. SFR-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Aquilonius, Karin (Studsvik Nuclear AB (Sweden)); Qvarfordt, Susanne; Borgiel, Micke (Sveriges Vattenekologer AB (Sweden))

    2011-04-15

    A regression model implemented in GIS of the marine vegetation in Forsmark were developed by SKB /Aquilonius 2010/ based on field investigations and video surveys /Fredriksson 2005/ and from correlations of field data and physical properties /Carlen et al. 2007/. The marine vegetation model describes distribution and biomasses of the marine vegetation and is used as input data in the dose modeling within the safety assessments performed by the SKB. In this study the predictive performance of the vegetation model in the less examined parts of the marine area in Forsmark is evaluated. In general, the vegetation model works very well in predicting absence of biomass, except for Red algae. In total and for Fucus sp., the model also predicts the observed biomass fairly well. However, for phanerogams, Chara sp., filamentous algae and red algae the vegetation model works less well in predicting biomass

  19. Geology - Background complementary studies. Forsmark modelling stage 2.2

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, Michael B. [Geological Survey of Sweden, Uppsala (Sweden); Skagius, Kristina [Kemakta Konsult AB, Stockholm (Sweden)] (eds.)

    2007-09-15

    borehole (VSP) reflection seismic data along profiles 2 and 5, Forsmark, Sweden. Christopher Juhlin. 3. Correlation of 2D surface seismic, vertical seismic profile (VSP), and geological and sonic data in boreholes KFM01A and KFM02A, Forsmark: Background analysis. Nicoleta Enescu and Calin Cosma. 4. Refraction seismic data and bedrock velocity distribution at Forsmark. Johan Nissen. 5. Correlation between refraction seismic data, low magnetic lineaments and deformation zones (model stage 2.2). Hans Isaksson. 6. Interpretation of tomography inversion models for seismic refraction data along profile LFM001017 in Forsmark. Haakan Mattsson. 7. Correlation of oriented radar reflectors with geological features in boreholes at Forsmark. Seje Carlsten.

  20. Geology - Background complementary studies. Forsmark modelling stage 2.2

    International Nuclear Information System (INIS)

    Stephens, Michael B.; Skagius, Kristina

    2007-09-01

    borehole (VSP) reflection seismic data along profiles 2 and 5, Forsmark, Sweden. Christopher Juhlin. 3. Correlation of 2D surface seismic, vertical seismic profile (VSP), and geological and sonic data in boreholes KFM01A and KFM02A, Forsmark: Background analysis. Nicoleta Enescu and Calin Cosma. 4. Refraction seismic data and bedrock velocity distribution at Forsmark. Johan Nissen. 5. Correlation between refraction seismic data, low magnetic lineaments and deformation zones (model stage 2.2). Hans Isaksson. 6. Interpretation of tomography inversion models for seismic refraction data along profile LFM001017 in Forsmark. Haakan Mattsson. 7. Correlation of oriented radar reflectors with geological features in boreholes at Forsmark. Seje Carlsten

  1. Monitoring Forsmark - Bird monitoring in Forsmark 2012

    Energy Technology Data Exchange (ETDEWEB)

    Green, Martin [Dept of Biology, Lund Univ., Lund (Sweden)

    2013-03-15

    This report summarizes the monitoring of selected listed (Swedish Red List and/or the EU Birds directive) breeding birds in Forsmark 2002 - 2012. Monitoring of eleven listed species was conducted in the regional model area, including the candidate area in 2012 in the same way as in earlier years. The results from 2012 generally follow patterns recorded in earlier years. 2012 was in general a better bird year compared to 2010 and 2011 and most species (82%) showed increasing or stable numbers from 2011 to 2012. Only two species (18%) decreased in numbers between the last two years. All in all, six species (55 %, black-throated diver, honey buzzard, black grouse, ural owl, wryneck and red-backed shrike) show no significant trends since the start of the bird monitoring (2002/2003/2004 depending on species). During this period three species (27 %, white-tailed eagle, osprey and lesser spotted woodpecker) have increased in numbers while just two (18 %, capercaillie and hazelhen) have decreased. A new pair of black-throated divers was discovered in 2012 and seven resident pairs were registered. Breeding success was very good, the second best during the study period. Population development follows the national pattern, but breeding success seems to be better in Forsmark than in the country as a whole. Honey buzzards and ospreys occurred in good numbers, and breeding success for ospreys was good. No signs of successful breedings of honey buzzards were recorded, but this may mean little as no detailed monitoring of breeding success is made for this species. The white-tailed eagles had their best breeding year since the start of the SKB bird monitoring, meaning that during the last two years local breeding success has been back at the level recorded before the site investigations started. The three grouse species (black grouse, capercaillie and hazelhen) again showed somewhat varying patterns between the last two years as well as in the long run. The black grouse increased

  2. Monitoring Forsmark-Bird monitoring in Forsmark 2012

    International Nuclear Information System (INIS)

    Green, Martin

    2013-03-01

    This report summarizes the monitoring of selected listed (Swedish Red List and/or the EU Birds directive) breeding birds in Forsmark 2002 - 2012. Monitoring of eleven listed species was conducted in the regional model area, including the candidate area in 2012 in the same way as in earlier years. The results from 2012 generally follow patterns recorded in earlier years. 2012 was in general a better bird year compared to 2010 and 2011 and most species (82%) showed increasing or stable numbers from 2011 to 2012. Only two species (18%) decreased in numbers between the last two years. All in all, six species (55 %, black-throated diver, honey buzzard, black grouse, ural owl, wryneck and red-backed shrike) show no significant trends since the start of the bird monitoring (2002/2003/2004 depending on species). During this period three species (27 %, white-tailed eagle, osprey and lesser spotted woodpecker) have increased in numbers while just two (18 %, capercaillie and hazelhen) have decreased. A new pair of black-throated divers was discovered in 2012 and seven resident pairs were registered. Breeding success was very good, the second best during the study period. Population development follows the national pattern, but breeding success seems to be better in Forsmark than in the country as a whole. Honey buzzards and ospreys occurred in good numbers, and breeding success for ospreys was good. No signs of successful breedings of honey buzzards were recorded, but this may mean little as no detailed monitoring of breeding success is made for this species. The white-tailed eagles had their best breeding year since the start of the SKB bird monitoring, meaning that during the last two years local breeding success has been back at the level recorded before the site investigations started. The three grouse species (black grouse, capercaillie and hazelhen) again showed somewhat varying patterns between the last two years as well as in the long run. The black grouse increased

  3. Uncertainty aspects of the digital elevation model for the Forsmark area

    Energy Technology Data Exchange (ETDEWEB)

    Stroemgren, Maarten; Brydsten, Lars (Umeaa Univ., Umeaa (Sweden))

    2009-10-15

    for the 50-metre DEM. However, the statistical analysis has revealed errors larger than 10 m within the areas of these data sources. In the sea area, the highest quality is found within the extensions of the measurements from shallow bays, the base map, and the detailed area of the measurements from the Geological Survey of Sweden (SGU). In the regional area of the measurements from the Geological Survey of Sweden, the uncertainty is much larger and errors of almost 10 m have been calculated. In the extension of the digital nautical chart/nautical chart, the uncertainty is very high with a mean error of almost 5 m, a standard deviation of a little more than 3 m, and a maximum error of more than 35 m. No error calculation was done in the lakes in the Forsmark area. However, comparing the maximum distance between points in the lakes with measurements from the sea area would suggest a quality at least as good as in the shallow bays. No error calculation was done for the inlet channel to the nuclear power plant and nor for the small areas where false depth values are placed

  4. Uncertainty aspects of the digital elevation model for the Forsmark area

    International Nuclear Information System (INIS)

    Stroemgren, Maarten; Brydsten, Lars

    2009-10-01

    for the 50-metre DEM. However, the statistical analysis has revealed errors larger than 10 m within the areas of these data sources. In the sea area, the highest quality is found within the extensions of the measurements from shallow bays, the base map, and the detailed area of the measurements from the Geological Survey of Sweden (SGU). In the regional area of the measurements from the Geological Survey of Sweden, the uncertainty is much larger and errors of almost 10 m have been calculated. In the extension of the digital nautical chart/nautical chart, the uncertainty is very high with a mean error of almost 5 m, a standard deviation of a little more than 3 m, and a maximum error of more than 35 m. No error calculation was done in the lakes in the Forsmark area. However, comparing the maximum distance between points in the lakes with measurements from the sea area would suggest a quality at least as good as in the shallow bays. No error calculation was done for the inlet channel to the nuclear power plant and nor for the small areas where false depth values are placed

  5. Advanced on-site conceptual simulator for Forsmark 3

    International Nuclear Information System (INIS)

    Johansson, G.; Sjoestrand, K.

    1984-01-01

    On-site conceptual simulators have been extensively used at Swedish nuclear power plants. Despite having access to identical replica simulators, both the Swedish State Power Board and the Swedish private power industry have ordered conceptual simulators during 1982. The motivation has been that a complete training programme requires access to both a replica and a conceptual simulator. The replica simulator is perfect for training in control room behaviour but less appropriate for ensuring deeper process understanding. On the other hand, the conceptual simulator is not well suited for getting the personnel acquainted with the control room but is perfect for extending their knowledge of the plant processes. In order to give a realistic description of these processes, the conceptual simulator model must be fairly advanced. The Forsmark 3 conceptual simulator simulates the entire primary system, including the details of the steam and feedwater systems. Considerable attention has also been devoted to the presentation of calculated variables. For example, all the variables in the data base (approx. 6600) can be presented on colour-graphic CRTs as functions of time. (author)

  6. Revising the security organisation at Forsmark NPP - A case study from the point of view of the operator and the regulatory and supervisory authority

    International Nuclear Information System (INIS)

    Roeden, B.; Strandberg, L.; Isaksson, S.

    2001-01-01

    Forsmark Nuclear Power Plant consists of three reactor-units. Each unit has separate shift crews and separate control rooms for operation of the plant. During 1996, Forsmarks Kraftgrupp AB (FKA) decided to change the organisation of Security at the site in Forsmark, Sweden. Reasons for changing the Organisation Experiences pointed out that it was necessary to have a Security supervisor present at site 24 hours per day. Experiences were basically gained from occasions when malfunctions in the technical security systems occurred. Another experience was that the procedures describing counter measures to different malfunctions in the technical security systems, did not meet the same high requirements, that would be expected in comparison with the Standard Operational and Emergency Operational Procedures, which are used for operation of the Nuclear Power Plant. It was decided to integrate the Security guards in the shift crew, one guard for each reactor unit and shift. Some of the regular Field Operators in the shift-crews for operating the plant were educated to competent Security Guards. The Shift Supervisor on each reactor unit became in charge for one Security Guard. One of the units also became in charge of the Security Central and the Security Guard operating the technical security systems. During incidents the supervisor from the fire brigade takes the responsibility for the security. He also has additionally two Security Guards at disposal from the fire brigade. In case of a major incident, this arrangement let the Shift Supervisors proceed taking the necessary counter measures concerning the process in the power plant. The attitude to new duties among the regular Field Operators educated to Security Guards were not positive, this problem affected also the attitude among the Shift supervisors. It was difficult to bring the different reactor units to work in the same direction and at the same time, generally speaking. The procedures and standards at each unit

  7. Description of surface hydrology and near-surface hydrogeology at Forsmark. Site descriptive modelling SDM. Site Forsmark

    International Nuclear Information System (INIS)

    Johansson, Per-Olof

    2008-12-01

    are highly dependent on the very transmissive horizontal and sub-horizontal fractures of the uppermost bedrock and that evapotranspiration induced flow may change these directions under dry conditions in some areas. Data as well as the simulations with MIKE SHE raise the question if the prevailing groundwater levels in the northern part of the tectonic lens are influenced by the pumping for the drainage of the SFR facility (c. 6 L/s). Another possibly influencing sink is the pumping for drainage of the Forsmark nuclear plant reactor buildings 1 and 2 (c. 1-2 L/s). These sinks may influence the vertical flow gradients in some parts of the investigation area, and it is strongly recommended that additional investigations are performed to resolve this uncertainty

  8. Description of surface hydrology and near-surface hydrogeology at Forsmark. Site descriptive modelling SDM. Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Johansson, Per-Olof (Artesia Grundvattenkonsult AB, Taeby (Sweden))

    2008-12-15

    the bedrock are highly dependent on the very transmissive horizontal and sub-horizontal fractures of the uppermost bedrock and that evapotranspiration induced flow may change these directions under dry conditions in some areas. Data as well as the simulations with MIKE SHE raise the question if the prevailing groundwater levels in the northern part of the tectonic lens are influenced by the pumping for the drainage of the SFR facility (c. 6 L/s). Another possibly influencing sink is the pumping for drainage of the Forsmark nuclear plant reactor buildings 1 and 2 (c. 1-2 L/s). These sinks may influence the vertical flow gradients in some parts of the investigation area, and it is strongly recommended that additional investigations are performed to resolve this uncertainty.

  9. The marine ecosystems at Forsmark and Laxemar-Simpevarp. SR-Site Biosphere

    Energy Technology Data Exchange (ETDEWEB)

    Aquilonius, Karin [ed.; Studsvik Nuclear AB (Sweden)

    2010-12-15

    mean for the Baltic Sea and slightly lower in Laxemar-Simpevarp. The sea level at Forsmark has since 2003 fluctuated between 0.6 m below and 1.3 m above the mean level, and the corresponding values for Laxemar-Simpevarp are 0.5 and 0.7 m. Due to the gentler slope of the coastline, the sea level fluctuations have a more marked effect in Forsmark, than in the Laxemar-Simpevarp landscape, exhibiting a steeper slope. In Forsmark the macrophyte vegetation in the photic zone is dominated by red algae and brown filamentous algae. In Laxemar-Simpevarp, the red algae community covers the largest area. The benthic biomass at the bottom sampling sites in Forsmark has been dominated by the Baltic mussel. In Laxemar-Simpevarp the sessile macro fauna attached to hard substrates is completely dominated by the blue mussel in terms of both biomass and abundance. Test fishing in Forsmark and Laxemar-Simpevarp show similar development as in other nearby coastal areas and herring and sprat are the dominant species in offshore areas at both sites. In the inner bays at the sites, perch and pike are the most frequent species. The biomass in Forsmark is dominated by the primary producers and is focused along the shoreline of the area. On average, the marine area in Forsmark shows a positive Net Ecosystem Production (NEP), although most of the area is heterotrophic. The coastal shallow basins tend to be autotrophic, whereas the more offshore basins are heterothropic. The largest carbon pool in all basins in Forsmark is the abiotic pools (i.e. sediment, DIC and DOC) followed by the macrophytes. The major carbon flux in the ecosystem is the advective flux caused by the movement of sea water. All biotic fluxes are small in comparison with the advective flux. The largest biotic flux is fixation of carbon by primary producers. On average 4% of the initially consumed carbon in the marine ecosystem food web is transferred to the top predators. For nitrogen, phosphorus and thorium, the major pool in

  10. The marine ecosystems at Forsmark and Laxemar-Simpevarp. SR-Site Biosphere

    International Nuclear Information System (INIS)

    Aquilonius, Karin

    2010-12-01

    mean for the Baltic Sea and slightly lower in Laxemar-Simpevarp. The sea level at Forsmark has since 2003 fluctuated between 0.6 m below and 1.3 m above the mean level, and the corresponding values for Laxemar-Simpevarp are 0.5 and 0.7 m. Due to the gentler slope of the coastline, the sea level fluctuations have a more marked effect in Forsmark, than in the Laxemar-Simpevarp landscape, exhibiting a steeper slope. In Forsmark the macrophyte vegetation in the photic zone is dominated by red algae and brown filamentous algae. In Laxemar-Simpevarp, the red algae community covers the largest area. The benthic biomass at the bottom sampling sites in Forsmark has been dominated by the Baltic mussel. In Laxemar-Simpevarp the sessile macro fauna attached to hard substrates is completely dominated by the blue mussel in terms of both biomass and abundance. Test fishing in Forsmark and Laxemar-Simpevarp show similar development as in other nearby coastal areas and herring and sprat are the dominant species in offshore areas at both sites. In the inner bays at the sites, perch and pike are the most frequent species. The biomass in Forsmark is dominated by the primary producers and is focused along the shoreline of the area. On average, the marine area in Forsmark shows a positive Net Ecosystem Production (NEP), although most of the area is heterotrophic. The coastal shallow basins tend to be autotrophic, whereas the more offshore basins are heterothropic. The largest carbon pool in all basins in Forsmark is the abiotic pools (i.e. sediment, DIC and DOC) followed by the macrophytes. The major carbon flux in the ecosystem is the advective flux caused by the movement of sea water. All biotic fluxes are small in comparison with the advective flux. The largest biotic flux is fixation of carbon by primary producers. On average 4% of the initially consumed carbon in the marine ecosystem food web is transferred to the top predators. For nitrogen, phosphorus and thorium, the major pool in

  11. Numerical modelling of surface hydrology and near-surface hydrogeology at Forsmark. Site descriptive modelling SDM. Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Bosson, Emma (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)); Gustafsson, Lars-Goeran; Sassner, Mona (DHI Sverige AB, Stockholm (Sweden))

    2008-09-15

    SKB is currently performing site investigations at two potential sites for a final repository for spent nuclear fuel. This report presents results of water flow and solute transport modelling of the Forsmark site. The modelling reported in this document focused on the near-surface groundwater, i.e. groundwater in Quaternary deposits and shallow rock, and surface water systems, and was performed using the MIKE SHE tool. The most recent site data used in the modelling were delivered in the Forsmark 2.3 dataset, which had its 'data freeze' on March 31, 2007. The present modelling is performed in support of the final version of the Forsmark site description that is produced during the site investigation phase. In this work, the hydrological modelling system MIKE SHE has been used to describe near-surface groundwater flow and the contact between groundwater and surface water at the Forsmark site. The surface water system at Forsmark is described with the one-dimensional 'channel flow' modelling tool MIKE 11, which is fully and dynamically integrated with MIKE SHE. The MIKE SHE model was updated with data from the F2.3 data freeze. The main updates concerned the geological description of the saturated zone and the time series data on water levels and surface water discharges. The time series data used as input data and for calibration and validation was extended until the Forsmark 2.3 data freeze (March 31, 2007). The present work can be subdivided into the following four parts: 1. Update of the numerical flow model. 2. Sensitivity analysis and calibration of the model parameters. 3. Validation of the calibrated model, followed by evaluation and identification of discrepancies between measurements and model results. 4. Additional sensitivity analysis and calibration in order to resolve the problems identified in point three above. The main actions taken during the calibration can be summarised as follows: 1. The potential evapotranspiration was

  12. Safety-related site characteristics - a relative comparison of the Forsmark reference areas

    International Nuclear Information System (INIS)

    Winberg, Anders

    2010-12-01

    SKB has over the years from 2002 to 2008 conducted site investigations in Forsmark and Laxemar, with associated site modeling, design and safety analysis. In mid-2009 Forsmark was selected on the basis of analysis made as site for a future repository for spent nuclear fuel. Based on defined safety-related geoscientific location factors data from Forsmark are compared in relative terms with data from a number of locations in Sweden, previously studied by SKB. The factors compared include: the rock's composition and structures, future climate evolution, rock mechanical conditions, earthquakes, groundwater flow, groundwater composition, delay of solutes, and the ability to characterize and describe the location. Past comparisons of these properties for the selected sites show that none of these sites collectively show any significant benefit over Forsmark site for a repository. This does not preclude that there may be places on the basis of an overall assessment of geoscientific location factors could be equivalent to Forsmark

  13. Hydrogeological conceptual model development and numerical modelling using CONNECTFLOW, Forsmark modelling stage 2.3

    Energy Technology Data Exchange (ETDEWEB)

    Follin, Sven (SF GeoLogic AB, Taeby (Sweden)); Hartley, Lee; Jackson, Peter; Roberts, David (Serco TAP (United Kingdom)); Marsic, Niko (Kemakta Konsult AB, Stockholm (Sweden))

    2008-05-15

    Three versions of a site descriptive model (SDM) have been completed for the Forsmark area. Version 0 established the state of knowledge prior to the start of the site investigation programme. Version 1.1 was essentially a training exercise and was completed during 2004. Version 1.2 was a preliminary site description and concluded the initial site investigation work (ISI) in June 2005. Three modelling stages are planned for the complete site investigation work (CSI). These are labelled stage 2.1, 2.2 and 2.3, respectively. An important component of each of these stages is to address and continuously try to resolve discipline-specific uncertainties of importance for repository engineering and safety assessment. Stage 2.1 included an updated geological model for Forsmark and aimed to provide a feedback from the modelling working group to the site investigation team to enable completion of the site investigation work. Stage 2.2 described the conceptual understanding and the numerical modelling of the bedrock hydrogeology in the Forsmark area based on data freeze 2.2. The present report describes the modelling based on data freeze 2.3, which is the final data freeze in Forsmark. In comparison, data freeze 2.3 is considerably smaller than data freeze 2.2. Therefore, stage 2.3 deals primarily with model confirmation and uncertainty analysis, e.g. verification of important hypotheses made in stage 2.2 and the role of parameter uncertainty in the numerical modelling. On the whole, the work reported here constitutes an addendum to the work reported in stage 2.2. Two changes were made to the CONNECTFLOW code in stage 2.3. These serve to: 1) improve the representation of the hydraulic properties of the regolith, and 2) improve the conditioning of transmissivity of the deformation zones against single-hole hydraulic tests. The changes to the modelling of the regolith were made to improve the consistency with models made with the MIKE SHE code, which involved the introduction

  14. The Laxemar and Forsmark repositories. An analysis of the water inflow distribution

    International Nuclear Information System (INIS)

    Svensson, Urban

    2006-12-01

    A numerical simulation model is used to estimate the water inflow distribution to the Laxemar and Forsmark repositories. In particular statistics for the inflow to individual deposition holes, i.e. inflow distribution expressed as litre/min, deposition hole, is requested. Different grouting efficiencies are evaluated, including no grouting. The simulations are based on the code DarcyTools version 3.0, which was also used in simulations of the impact of the Repositories in Forsmark and Laxemar. Both the code and the simulations include many novel features and all simulations should hence be regarded as tentative. For the Laxemar repository it is found that less than 2% of all deposition holes will have an inflow larger than 1.0 l/min. This number will increase to about 20% if the inflow limit is put to 0.1 l/min. For the Forsmark repository it is found that 99.9% of all deposition holes will have an inflow smaller than 0.01 l/min

  15. Forsmark site investigation. Bedrock geology - overview and excursion guide

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, Michael B. (Geological Survey of Sweden, Uppsala (Sweden))

    2010-09-15

    Bearing in mind the significance of the bedrock data from the ground surface for the geological 3D modelling work, SKB decided to present excursion guides that serve in the demonstration of the bedrock geology at the ground surface in both the Forsmark (this guide) and Laxemar-Simpevarp areas. An excursion guide is also available for the Olkiluoto area in south-western Finland, which has been selected for the construction of a repository for the disposal of highly radioactive, spent nuclear fuel in Finland. The current excursion guide presents the bedrock geology and describes in detail the character of the bedrock at ten representative outcrops or outcrop areas at the ground surface in the site investigation area at Forsmark. All localities are located within or immediately adjacent to the proposed repository volume selected by SKB

  16. Forsmark site investigation. Bedrock geology - overview and excursion guide

    International Nuclear Information System (INIS)

    Stephens, Michael B.

    2010-09-01

    Bearing in mind the significance of the bedrock data from the ground surface for the geological 3D modelling work, SKB decided to present excursion guides that serve in the demonstration of the bedrock geology at the ground surface in both the Forsmark (this guide) and Laxemar-Simpevarp areas. An excursion guide is also available for the Olkiluoto area in south-western Finland, which has been selected for the construction of a repository for the disposal of highly radioactive, spent nuclear fuel in Finland. The current excursion guide presents the bedrock geology and describes in detail the character of the bedrock at ten representative outcrops or outcrop areas at the ground surface in the site investigation area at Forsmark. All localities are located within or immediately adjacent to the proposed repository volume selected by SKB

  17. Coolability of degraded core under reflooding conditions in Nordic boiling water reactors

    Energy Technology Data Exchange (ETDEWEB)

    Lindholm, I; Pekkarinen, E [VTT Energy, Espoo (Finland); Nilsson, L [Studsvik EcoSafe AB, Nykoeping (Sweden); Sjoevall, H [Teollisuuden Voima Oy, Olkiluoto (Finland)

    1995-09-01

    Present work is part of the first phase of subproject RAK-2.1 of the new Nordic Co-operative Reactor Safety Program, NKS. The first phase comprises reflooding calculations for the boiling water reactors (BWRs) TVO I/II in Finland and Forsmark 3 in Sweden, as a continuation of earlier severe accident analyses which were made in the SIK-2 project. The objective of the core reflooding studies is to evaluate when and how the core is still coolable with water and what are the probable consequences of water cooling. In the following phase of the RAK-2.1 project, recriticality studies will be performed. Conditions for recriticality might occur if control rods have melted away with the fuel rods intact in a shape that critical conditions can be created in reflooding with insufficiently borated water. Core coolability was investigated for two reference plants, TVO I/II and Forsmark 3. The selected accident cases were anticipated station blackout with or without successful depressurization of reactor coolant system (RCS). The effects of the recovery of emergency core cooling (ECC) were studied by varying the starting time of core reflooding. The start of ECC systems were assigned to reaching a maximum cladding temperature: 1400 K, 1600 K, 1800 K and 2000 K in the core. Cases with coolant injection through the downcomer were studied for TVO I/II and both downcomer injection and core top spray were investigated for Forsmark 3. Calculations with three different computer codes: MAAP 4, MELCOR 1.8.3 and SCDA/RELAP5/MOD 3.1 for the basis for the presented reflooding studies. Presently, and experimental programme on core reflooding phenomena has been started in Kernforschungszentrum Karlsruhe in QUENCH test facility. (EG) 17 refs.

  18. Rock Mechanics Forsmark. Site descriptive modelling Forsmark stage 2.2

    Energy Technology Data Exchange (ETDEWEB)

    Glamheden, Rune; Fredriksson, Anders (Golder Associates AB (SE)); Roeshoff, Kennert; Karlsson, Johan (Berg Bygg Konsult AB (SE)); Hakami, Hossein (Itasca Geomekanik AB (SE)); Christiansson, Rolf (Swedish Nuclear Fuel and Waste Management Co., Stockholm (SE))

    2007-12-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterisation at two different locations, Forsmark and Laxemar/Simpevarp, with the objective of siting a geological repository for spent nuclear fuel. The characterisation of a site is an integrated work carried out by several disciplines including geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry and surface systems. This report presents the rock mechanics model of the Forsmark site up to stage 2.2. The scope of work has included compilation and analysis of primary data of intact rock and fractures, estimation of the rock mass mechanical properties and estimation of the in situ state of stress at the Forsmark site. The laboratory results on intact rock and fractures in the target volume demonstrate a good quality rock mass that is strong, stiff and relatively homogeneous. The homogeneity is also supported by the lithological and the hydrogeological models. The properties of the rock mass have been initially estimated by two separate modelling approaches, one empirical and one theoretical. An overall final estimate of the rock mass properties were achieved by integrating the results from the two models via a process termed 'Harmonization'. Both the tensile tests, carried out perpendicular and parallel to the foliation, and the theoretical analyses of the rock mass properties in directions parallel and perpendicular to the major principal stress, result in parameter values almost independent of direction. This indicates that the rock mass in the target volume is isotropic. The rock mass quality in the target volume appears to be of high and uniform quality. Those portions with reduced rock mass quality that do exist are mainly related to sections with increased fracture frequency. Such sections are associated with deformation zones according to the geological description. The results of adjacent rock domains and fracture domains of the target

  19. Bedrock geology Forsmark. Modelling stage 2.3. Description of the bedrock geological map at the ground surface

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, Michael B.; Bergman, Torbjoern (Geological Survey of Sweden, Uppsala (Sweden)); Isaksson, Hans (GeoVista AB, Luleaa (Sweden)); Petersson, Jesper (SwedPower AB, Stockholm (Sweden))

    2008-12-15

    A description of the bedrock geological map of the ground surface at the Forsmark site is presented here. This map is essentially a 2D model for the distribution of different types of rock unit on this surface. Besides showing the distribution of these rock units, the bedrock geological map also displays the distribution of some deformation zones that intersect the ground surface. It also presents information bearing on the position and form of outcrops, the location and projection of boreholes drilled during the site investigation programme, subordinate rock types, the occurrence of abandoned mines or exploration prospects, measurements of ductile structures in outcrops, inferred form lines, key minerals, and the occurrence of mylonite and cataclastic rock. Bedrock data from outcrops and excavations, airborne and ground magnetic data and information from the uppermost part of boreholes have all been used in the construction of the geological map. The description has also made use of complementary analytical data bearing on the composition and age of the rocks as well gamma-ray spectrometry and gravity data. Uncertainty in the position of the boundaries between rock units over the mapped area are addressed in a qualitative manner. Four model versions of the bedrock geological map have been delivered to SKB's GIS database (bedrock geological map, Forsmark, versions 1.1, 1.2, 2.2 and 2.3) at different times during the site investigation programme. The Forsmark area is situated along the coast of the Baltic Sea in northern Uppland, Sweden, in a region where the overall level of ductile strain in the bedrock is high. This high-strain region extends several tens of kilometres across the WNW-ENE to NW-SE strike of the rocks in this part of the Fennoscandian Shield. At Forsmark, the coastal region is composed partly of high-strain belts, which formed under amphibolite-facies metamorphic conditions, and partly of tectonic lenses, where the bedrock is also affected by

  20. Bedrock geology Forsmark. Modelling stage 2.3. Description of the bedrock geological map at the ground surface

    International Nuclear Information System (INIS)

    Stephens, Michael B.; Bergman, Torbjoern; Isaksson, Hans; Petersson, Jesper

    2008-12-01

    A description of the bedrock geological map of the ground surface at the Forsmark site is presented here. This map is essentially a 2D model for the distribution of different types of rock unit on this surface. Besides showing the distribution of these rock units, the bedrock geological map also displays the distribution of some deformation zones that intersect the ground surface. It also presents information bearing on the position and form of outcrops, the location and projection of boreholes drilled during the site investigation programme, subordinate rock types, the occurrence of abandoned mines or exploration prospects, measurements of ductile structures in outcrops, inferred form lines, key minerals, and the occurrence of mylonite and cataclastic rock. Bedrock data from outcrops and excavations, airborne and ground magnetic data and information from the uppermost part of boreholes have all been used in the construction of the geological map. The description has also made use of complementary analytical data bearing on the composition and age of the rocks as well gamma-ray spectrometry and gravity data. Uncertainty in the position of the boundaries between rock units over the mapped area are addressed in a qualitative manner. Four model versions of the bedrock geological map have been delivered to SKB's GIS database (bedrock geological map, Forsmark, versions 1.1, 1.2, 2.2 and 2.3) at different times during the site investigation programme. The Forsmark area is situated along the coast of the Baltic Sea in northern Uppland, Sweden, in a region where the overall level of ductile strain in the bedrock is high. This high-strain region extends several tens of kilometres across the WNW-ENE to NW-SE strike of the rocks in this part of the Fennoscandian Shield. At Forsmark, the coastal region is composed partly of high-strain belts, which formed under amphibolite-facies metamorphic conditions, and partly of tectonic lenses, where the bedrock is also affected by

  1. Quantifying in situ stress magnitudes and orientations for Forsmark. Forsmark stage 2.2

    International Nuclear Information System (INIS)

    Martin, C. Derek

    2007-11-01

    Stephansson et al. concluded that in the Fennoscandia shield: (1) there is a large horizontal stress component in the uppermost 1,000 m of bedrock, and (2) the maximum and minimum horizontal stresses exceed the vertical stress assuming the vertical stress is estimated from the weight of the overburden. Several stress campaigns involving both overcoring and hydraulic fracturing, including the hydraulic testing of pre-existing fractures (HTPF), have been carried out at Forsmark to establish the in situ stress state. The results from the initial campaigns were summarised by Sjoeberg et al. which formed the bases for the stresses provided in the Site Descriptive Model version 1.2. Since then additional stress measurement campaigns have been completed. The results from these stress measurement campaigns support the conclusions from Stephansson et al. In addition to these in situ stress measurements the following additional studies were undertaken to aid in assessing the stress state at Forsmark. 1. A detailed televiewer survey of approximately 6,900 m of borehole walls to depths of 1,000 m was carried out to assess borehole wall damage, i.e. borehole breakouts. 2. Evaluation of nonlinear strains in laboratory samples to depths of approximately 800 m to assess if stress magnitudes were sufficient to create stress-induced microcracking. 3. Assessment of the magnitudes required to cause core disking and survey of core disking observed at Forsmark. The magnitudes and orientations from the stress measurement campaigns were analysed to establish the most likely stress magnitudes and orientations for Design Step D2 within the Target Area of the Complete Site Investigations. The maximum and minimum horizontal stress components are essentially the same as the maximum and intermediate principal stresses, σ1 and σ2, respectively. The minimum principal stress (σ3) is synonymous with the vertical stress. The most likely range in values to be used in the design is also shown. The

  2. Quantifying in situ stress magnitudes and orientations for Forsmark. Forsmark stage 2.2

    Energy Technology Data Exchange (ETDEWEB)

    Martin, C. Derek (Univ. of Alberta (Canada))

    2007-11-15

    Stephansson et al. concluded that in the Fennoscandia shield: (1) there is a large horizontal stress component in the uppermost 1,000 m of bedrock, and (2) the maximum and minimum horizontal stresses exceed the vertical stress assuming the vertical stress is estimated from the weight of the overburden. Several stress campaigns involving both overcoring and hydraulic fracturing, including the hydraulic testing of pre-existing fractures (HTPF), have been carried out at Forsmark to establish the in situ stress state. The results from the initial campaigns were summarised by Sjoeberg et al. which formed the bases for the stresses provided in the Site Descriptive Model version 1.2. Since then additional stress measurement campaigns have been completed. The results from these stress measurement campaigns support the conclusions from Stephansson et al. In addition to these in situ stress measurements the following additional studies were undertaken to aid in assessing the stress state at Forsmark. 1. A detailed televiewer survey of approximately 6,900 m of borehole walls to depths of 1,000 m was carried out to assess borehole wall damage, i.e. borehole breakouts. 2. Evaluation of nonlinear strains in laboratory samples to depths of approximately 800 m to assess if stress magnitudes were sufficient to create stress-induced microcracking. 3. Assessment of the magnitudes required to cause core disking and survey of core disking observed at Forsmark. The magnitudes and orientations from the stress measurement campaigns were analysed to establish the most likely stress magnitudes and orientations for Design Step D2 within the Target Area of the Complete Site Investigations. The maximum and minimum horizontal stress components are essentially the same as the maximum and intermediate principal stresses, sigma1 and sigma2, respectively. The minimum principal stress (sigma3) is synonymous with the vertical stress. The most likely range in values to be used in the design is also

  3. Forsmark 1

    International Nuclear Information System (INIS)

    Fredell, J.; Henriksson, T.

    1981-12-01

    ASEA-ATOM carried out an experiment in Forsmark 1 in 1978, in conjunction with discharge test, by means of the safety/relief valves. The tests have been carried out for the case of single valve actuation (SVA), multiple valve actuations (MVA) and consecutive valve actuations (CVA). During MVA tests, up to 12 valves have been used. One of the aims of the experiment was to confirm the operation of the new design of mitigator of the discharge pipes and another was to survey the pressure oscillations in the pool and the vibratory behaviour of the structures and components. The results of these measurements are presented in a number of reports. This report contains an abstract of the results of the measurements presented in these reports. This report also describes the theoretical background and comparisons between test and theoretical results. It is clear that very good agreement has been established between earlier steam discharge experiments, using a mitigator of the type fitted in Forsmark 1, and this experiment. This is based on the fact the amplitude, frequency and distribution of the pressure oscillations in the condensation pool are basically equal to the values predicted by calculations based on the earlier experiments. The low maximum acceleration amplitudes predicted by the beam type structural model have been confirmed, but the frequency content of the response is not very well represented by this type of model. The shell-beam finite element model of the structure gives better agreement with the measured frequency. (author)

  4. Environmental monitoring at the Forsmark nuclear power plant

    International Nuclear Information System (INIS)

    Sandstroem, O.

    1991-01-01

    The use of cooling water at such large power plants as Forsmark creates a considerable hazard for fish in the intake area, as they may be transported into the plant and killed. Several millions of Baltic herring and three-spined stickleback are lost each year at the intake screens. A release of cooling water to an open sea area is generally considered as a minor environmental problem, a presumption so far not contradicated by the results from the monitoring studies at Forsmark. In the Biotest basin, however, where the exposure to heat is maximal, a long series of effects ultimately changing populations of plants, benthic animals and fish have been documented. One important conclusion after ten years of studies in a heated Biotest basin, is that ecosystem stability seems to need very long time to be established, if it ever will. The monitoring of radioactivity controls the quality of the fish as food but is also directed to select special species accumulating these elements, bladder wrack etc. At Forsmark only small amounts of radionuclides from the plant so far have been detected in the marine environment. (KAE)

  5. Execution programme for the initial site investigations at Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-05-01

    In the feasibility studies that were completed in 2001, eight sites were identified as potentially suitable for hosting a repository. All the identified sites meet the safety requirements with respect to bedrock conditions that could be checked at that time. The feasibility studies have revealed good potential when it comes to the technical and environmental aspects as well. Based on an integrated evaluation SKB proposed to start site investigations with test drillings at three sites; Forsmark, Simpevarp and Tierp. Site investigations have started at Forsmark and Simpevarp. The municipal council of Tierp voted no to a site investigation in April 2002. The site investigations are divided into two main phases; initial and complete investigations. Initial site investigations are performed to identify the site within a specified area that is deemed to be most suitable for a deep repository and to determine whether the feasibility study's judgement of the suitability of the area holds up in the light of borehole data from repository depth. The initial site investigations are expected to take 1.5-2 years. If the assessment shows that the site has good potential to host a repository, complete site investigations will follow for an expected duration of 3.5-4 years. The purpose of the complete site investigations is to gather all information required to select one of the sites as the main alternative and to apply for a permit for construction of the deep repository at that site. A general programme in which the results from feasibility studies are summarized, the candidate sites presented and the framework of programme for the site investigation phase presented has been published. The general programme, and main references to the programme, specifies which data are required in order to design the repository and carry out a safety assessment, how the investigations should be carried out in order to provide these data, criteria with which the site must comply, as well as

  6. Execution programme for the initial site investigations at Forsmark

    International Nuclear Information System (INIS)

    2002-05-01

    In the feasibility studies that were completed in 2001, eight sites were identified as potentially suitable for hosting a repository. All the identified sites meet the safety requirements with respect to bedrock conditions that could be checked at that time. The feasibility studies have revealed good potential when it comes to the technical and environmental aspects as well. Based on an integrated evaluation SKB proposed to start site investigations with test drillings at three sites; Forsmark, Simpevarp and Tierp. Site investigations have started at Forsmark and Simpevarp. The municipal council of Tierp voted no to a site investigation in April 2002. The site investigations are divided into two main phases; initial and complete investigations. Initial site investigations are performed to identify the site within a specified area that is deemed to be most suitable for a deep repository and to determine whether the feasibility study's judgement of the suitability of the area holds up in the light of borehole data from repository depth. The initial site investigations are expected to take 1.5-2 years. If the assessment shows that the site has good potential to host a repository, complete site investigations will follow for an expected duration of 3.5-4 years. The purpose of the complete site investigations is to gather all information required to select one of the sites as the main alternative and to apply for a permit for construction of the deep repository at that site. A general programme in which the results from feasibility studies are summarized, the candidate sites presented and the framework of programme for the site investigation phase presented has been published. The general programme, and main references to the programme, specifies which data are required in order to design the repository and carry out a safety assessment, how the investigations should be carried out in order to provide these data, criteria with which the site must comply, as well as

  7. Monitoring Forsmark. Meteorological monitoring at Forsmark, January-December 2010

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Cari; Jones, Joergen (Swedish Meteorological and Hydrological Institute (SMHI), Norrkoeping (Sweden))

    2011-01-15

    In the Forsmark area, SKB's meteorological monitoring started in 2003 at the sites Storskaeret and Hoegmasten. However, since July 1, 2007 measurements are only performed at Hoegmasten. Measured and calculated parameters at Hoegmasten are precipitation and corrected precipitation, air temperature, barometric pressure, wind speed and direction, air humidity, global radiation and potential evapotranspiration. The Swedish Meteorological and Hydrological Institute, SMHI, has been responsible for planning and design, as well as for the operation of the stations used for meteorological monitoring. In general, the quality of the meteorological measurements during the period concerned, starting January 1, 2010, and ending December 31, 2010, has shown to be good

  8. Water-rock interaction modelling and uncertainties of mixing modelling. SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Gimeno, Maria J.; Auque, Luis F.; Gomez, Javier B.; Acero, Patricia (Univ. of Zaragoza, Zaragoza (Spain))

    2008-08-15

    in geochemistry, hydrochemistry, hydrogeochemistry, microbiology, geomicrobiology, analytical chemistry etc. The resulting site descriptive model version, mainly based on 2.2 data and complementary 2.3 data, was carried out during September 2006 to December 2007. Several groups within ChemNet were involved and the evaluation was conducted independently using different approaches ranging from expert knowledge to geochemical and mathematical modelling including transport modelling. During regular ChemNet meetings the results have been presented and discussed. This report presents the modelling work performed by the University of Zaragoza group as part of the work planned for Forsmark during stages 2.2 and 2.3. The chemical characteristics of the groundwaters in the Forsmark and Laxemar areas are the result of a complex mixing process driven by the input of different recharge waters since the last glaciation. The successive penetration at different depths of dilute glacial melt-waters, Littorina Sea waters and dilute meteoric waters has triggered complex density and hydraulically driven flows that have mixed them with long residence time, highly saline waters present in the fractures and in the rock matrix. A general description of the main characteristics and processes controlling the hydrogeochemical evolution with depth in the Forsmark groundwater system is presented in this report: The hydrochemical characteristics and evolution of the Near surface waters (up to 20 m depth) is mainly determined by weathering reactions and especially affected by the presence of limestones. The biogenic CO{sub 2} input (derived from decay of organic matter and root respiration) and the associated weathering of carbonates control the pH and the concentrations of Ca and HCO{sub 3}- in the near-surface environment. Current seasonal variability of CO{sub 2} input produces variable but high calcium and bicarbonate contents in the Forsmark near-surface waters: up to 240 mg/L Ca and 150 to

  9. Water-rock interaction modelling and uncertainties of mixing modelling. SDM-Site Forsmark

    International Nuclear Information System (INIS)

    Gimeno, Maria J.; Auque, Luis F.; Gomez, Javier B.; Acero, Patricia

    2008-08-01

    geochemistry, hydrochemistry, hydrogeochemistry, microbiology, geomicrobiology, analytical chemistry etc. The resulting site descriptive model version, mainly based on 2.2 data and complementary 2.3 data, was carried out during September 2006 to December 2007. Several groups within ChemNet were involved and the evaluation was conducted independently using different approaches ranging from expert knowledge to geochemical and mathematical modelling including transport modelling. During regular ChemNet meetings the results have been presented and discussed. This report presents the modelling work performed by the University of Zaragoza group as part of the work planned for Forsmark during stages 2.2 and 2.3. The chemical characteristics of the groundwaters in the Forsmark and Laxemar areas are the result of a complex mixing process driven by the input of different recharge waters since the last glaciation. The successive penetration at different depths of dilute glacial melt-waters, Littorina Sea waters and dilute meteoric waters has triggered complex density and hydraulically driven flows that have mixed them with long residence time, highly saline waters present in the fractures and in the rock matrix. A general description of the main characteristics and processes controlling the hydrogeochemical evolution with depth in the Forsmark groundwater system is presented in this report: The hydrochemical characteristics and evolution of the Near surface waters (up to 20 m depth) is mainly determined by weathering reactions and especially affected by the presence of limestones. The biogenic CO 2 input (derived from decay of organic matter and root respiration) and the associated weathering of carbonates control the pH and the concentrations of Ca and HCO 3 - in the near-surface environment. Current seasonal variability of CO 2 input produces variable but high calcium and bicarbonate contents in the Forsmark near-surface waters: up to 240 mg/L Ca and 150 to 900 mg/L HCO 3 - . These

  10. Evaluation of the state of stress at the Forsmark site. Preliminary site investigation Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Sjoeberg, Jonny; Lindfors, Ulf; Perman, Fredrik; Ask, Daniel [SwedPower AB, Stockholm (Sweden)

    2005-09-15

    This report presents an evaluation of the state of stress at the Forsmark site, based on all conducted stress measurements to date at the site, indirect stress estimates, geological and tectonic description of the site, and regional stress data from nearby locations. The work included (i) compilation of measurement results from Forsmark, as well as from nearby (regional) sites/locations, (ii) analysis of confidence intervals for each group of measurement, (iii) assessment of the stress state for the Forsmark site accounting for geological/tectonic evolution at the site, (iv) assessment of stress state for selected nearby (regional) sites/locations, and (v) comparison and combined interpretation of similarities and/or differences in stress state from a regional perspective. The combined assessment of the local (site-scale) and regional stress data for Forsmark showed that the major stress is orientated sub-horizontally and trending NW-SE; however, with significant local variation. A thrust faulting ({sigma}H > {sigma}h > {sigma}v) or possibly strike-slip faulting ({sigma}H > {sigma}v > {sigma}h) stress regime is evident at the Forsmark site. The maximum horizontal stress tends to be higher at the site compared to nearby sites and regional conditions. The site and regional data indicate that the vertical stress seems to be solely due to the overburden pressure. The lack of solid core discing for large portions of the boreholes at Forsmark was used to estimate an upper limit of the maximum horizontal stress magnitude. However, such an estimation is highly uncertain due to e.g. partly unknown mechanism for core discing failure, and unknown effects of the simplifying assumptions made in the analysis. The possible effects of shallow-dipping deformation zones on the stress state, could not be verified from the currently available data. However, the possibility of different stress regimes above and below deformation zones must be considered in future work. Slightly lower

  11. Evaluation of the state of stress at the Forsmark site. Preliminary site investigation Forsmark area - version 1.2

    International Nuclear Information System (INIS)

    Sjoeberg, Jonny; Lindfors, Ulf; Perman, Fredrik; Ask, Daniel

    2005-09-01

    This report presents an evaluation of the state of stress at the Forsmark site, based on all conducted stress measurements to date at the site, indirect stress estimates, geological and tectonic description of the site, and regional stress data from nearby locations. The work included (i) compilation of measurement results from Forsmark, as well as from nearby (regional) sites/locations, (ii) analysis of confidence intervals for each group of measurement, (iii) assessment of the stress state for the Forsmark site accounting for geological/tectonic evolution at the site, (iv) assessment of stress state for selected nearby (regional) sites/locations, and (v) comparison and combined interpretation of similarities and/or differences in stress state from a regional perspective. The combined assessment of the local (site-scale) and regional stress data for Forsmark showed that the major stress is orientated sub-horizontally and trending NW-SE; however, with significant local variation. A thrust faulting (σH > σh > σv) or possibly strike-slip faulting (σH > σv > σh) stress regime is evident at the Forsmark site. The maximum horizontal stress tends to be higher at the site compared to nearby sites and regional conditions. The site and regional data indicate that the vertical stress seems to be solely due to the overburden pressure. The lack of solid core discing for large portions of the boreholes at Forsmark was used to estimate an upper limit of the maximum horizontal stress magnitude. However, such an estimation is highly uncertain due to e.g. partly unknown mechanism for core discing failure, and unknown effects of the simplifying assumptions made in the analysis. The possible effects of shallow-dipping deformation zones on the stress state, could not be verified from the currently available data. However, the possibility of different stress regimes above and below deformation zones must be considered in future work. Slightly lower horizontal stress was found in

  12. Water activities in Forsmark. Ecological field inventory and classification of biodiversity values and description of forest production land; Vattenverksamhet i Forsmark. Ekologisk faeltinventering och naturvaerdesklassificering samt beskrivning av skogsproduktionsmark

    Energy Technology Data Exchange (ETDEWEB)

    Hamren, Ulrika; Collinder, Per [Ekologigruppen AB (Sweden)

    2010-12-15

    In 2009, the Swedish Nuclear Fuel and Waste Management Co (SKB) chose Forsmark in the Municipality of Oesthammar as site for the final repository for spent nuclear fuel. This report describes nature values and forestry areas in Forsmark, and provides part of the background material for description of consequences due to groundwater diversion during construction and operation of the repository. The report describes results of map studies and comprehensive field investigations, in terms of geographical delineations, descriptions of characteristics and classifications of nature values for groundwater dependent or groundwater favoured nature objects in Forsmark. The nature objects are located in an investigation area, which contains the area that according to numerical flow modelling could be affected by groundwater-table drawdown due to groundwater diversion

  13. Groundwater flow modelling of the excavation and operational phases - Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Svensson, Urban (Computer-aided Fluid Engineering AB, Lyckeby (Sweden)); Follin, Sven (SF GeoLogic AB, Taeby (Sweden))

    2010-07-15

    As a part of the license application for a final repository for spent nuclear fuel at Forsmark, the Swedish Nuclear Fuel and Waste Management Company (SKB) has undertaken a series of groundwater flow modelling studies. These represent time periods with different climate conditions and the simulations carried out contribute to the overall evaluation of the repository design and long-term radiological safety. The modelling study reported here presents calculated inflow rates, drawdown of the groundwater table and upconing of deep saline water for different levels of grouting efficiency during the excavation and operational phases of a final repository at Forsmark. The inflow calculations are accompanied by a sensitivity study, which among other matters handles the impact of parameter heterogeneity, different deposition hole rejection criteria, and the SFR facility (the repository for short-lived radioactive waste located approximately 1 km to the north of the investigated candidate area for a final repository at Forsmark). The report also presents tentative modelling results for the duration of the saturation phase, which starts once the used parts of the repository are being backfilled.

  14. Groundwater flow modelling of the excavation and operational phases - Forsmark

    International Nuclear Information System (INIS)

    Svensson, Urban; Follin, Sven

    2010-07-01

    As a part of the license application for a final repository for spent nuclear fuel at Forsmark, the Swedish Nuclear Fuel and Waste Management Company (SKB) has undertaken a series of groundwater flow modelling studies. These represent time periods with different climate conditions and the simulations carried out contribute to the overall evaluation of the repository design and long-term radiological safety. The modelling study reported here presents calculated inflow rates, drawdown of the groundwater table and upconing of deep saline water for different levels of grouting efficiency during the excavation and operational phases of a final repository at Forsmark. The inflow calculations are accompanied by a sensitivity study, which among other matters handles the impact of parameter heterogeneity, different deposition hole rejection criteria, and the SFR facility (the repository for short-lived radioactive waste located approximately 1 km to the north of the investigated candidate area for a final repository at Forsmark). The report also presents tentative modelling results for the duration of the saturation phase, which starts once the used parts of the repository are being backfilled

  15. Bedrock hydrogeochemistry Forsmark. Site descriptive modelling SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Laaksoharju, Marcus [Geopoint AB, Sollentuna (Sweden); Smellie, John [Conterra AB, Partille (Sweden); Tullborg, Eva-Lena [Terralogica, Graabo (Sweden); Gimeno, Maria [Univ. of Zaragoza, Zaragoza (Spain); Hallbeck, Lotta [Microbial Analytics, Goeteborg (Sweden); Molinero, Jorge [Amphos XXI Consulting S.L., Barcelona (Spain); Waber, Nick [Univ. of Bern, Bern (Switzerland)

    2008-12-15

    The overall objectives of the hydrogeochemical site description for Forsmark are to establish a detailed understanding of the hydrogeochemical conditions at the site, and to use this understanding to develop models that address the needs identified by the safety assessment groups during the site investigation phase. Issues of concern to safety assessment are radionuclide transport and technical barrier behaviour, both of which are dependent on the chemistry of groundwater and porewater and their evolution with time. The specific aims of the hydrogeochemical work were: To document the hydrogeochemistry at the Forsmark site with focus on the development of conceptual models to describe and visualise the site. To provide relevant parameter values to be used for safety assessment calculations. To provide the hydrogeochemical basis for the modelling work by other teams, in particular hydrogeology. To take account of the feedback from the SR-Can safety assessment work that bears relevance to the hydrogeochemical modelling work. The work has involved the development of descriptive and mathematical models for groundwaters in relation to rock domains, fracture domains and deformation zones. In this report, the groundwaters have been interpreted in relation to their origin, evolution and composition, which require close integration with geological, climatological and hydrogeological information. Past climate changes are one of the major driving forces for long-term hydrogeochemical changes (hundreds to thousands of years) and are, therefore, of fundamental importance for understanding the palaeohydrogeological, palaeohydrogeochemical and present evolution of groundwater in the Fennoscandian crystalline bedrock. In contrast, redox buffer capacity of the bedrock will minimise the effects on changes in alkalinity and redox at repository depths, therefore limiting the variations in pH and Eh significantly, regardless of major changes in groundwater composition. There is

  16. Bedrock hydrogeochemistry Forsmark. Site descriptive modelling SDM-Site Forsmark

    International Nuclear Information System (INIS)

    Laaksoharju, Marcus; Smellie, John; Tullborg, Eva-Lena; Gimeno, Maria; Hallbeck, Lotta; Molinero, Jorge; Waber, Nick

    2008-12-01

    The overall objectives of the hydrogeochemical site description for Forsmark are to establish a detailed understanding of the hydrogeochemical conditions at the site, and to use this understanding to develop models that address the needs identified by the safety assessment groups during the site investigation phase. Issues of concern to safety assessment are radionuclide transport and technical barrier behaviour, both of which are dependent on the chemistry of groundwater and porewater and their evolution with time. The specific aims of the hydrogeochemical work were: To document the hydrogeochemistry at the Forsmark site with focus on the development of conceptual models to describe and visualise the site. To provide relevant parameter values to be used for safety assessment calculations. To provide the hydrogeochemical basis for the modelling work by other teams, in particular hydrogeology. To take account of the feedback from the SR-Can safety assessment work that bears relevance to the hydrogeochemical modelling work. The work has involved the development of descriptive and mathematical models for groundwaters in relation to rock domains, fracture domains and deformation zones. In this report, the groundwaters have been interpreted in relation to their origin, evolution and composition, which require close integration with geological, climatological and hydrogeological information. Past climate changes are one of the major driving forces for long-term hydrogeochemical changes (hundreds to thousands of years) and are, therefore, of fundamental importance for understanding the palaeohydrogeological, palaeohydrogeochemical and present evolution of groundwater in the Fennoscandian crystalline bedrock. In contrast, redox buffer capacity of the bedrock will minimise the effects on changes in alkalinity and redox at repository depths, therefore limiting the variations in pH and Eh significantly, regardless of major changes in groundwater composition. There is

  17. Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3

    International Nuclear Information System (INIS)

    O'Regan, Patrick; Moody, Jim; Loetman, Jan; Sandstedt, Johan

    2010-12-01

    The objective of this project was a pilot plant demonstration of the EPRI RI-ISI Methodology to selected systems at Forsmark, Unit 3 (F3). This scope of this study encompasses five systems and is based upon F3 implementation of SKIFs guidance as well as other consideration as documented in the PMT program. As described in section 2, five systems were selected for evaluation. These systems were selected because they allow this project to focus on a number of issues of interest in developing a RI-ISI methodology and RI-ISI program. This includes the following: - Several different types of degradation may be identified, - Several different types of 'consequence of failure' may be identified, - Different types of safety systems are evaluated - Non-safety systems are evaluated Using the results of this application, insights and comparisons between SKIFS and the EPRI methodologies' are provided including the following: - Consequence of pressure boundary failure (PBF) as described in Section 3.14. - Degradation mechanism evaluation as described in Section 4.8. - Risk ranking as described in Section 5. - Element selection for inspection as described in Section 6. - Risk impact as described in Section 7

  18. Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3

    Energy Technology Data Exchange (ETDEWEB)

    O' Regan, Patrick (Electric Power Research Inst., Knoxville, TN (United States)); Moody, Jim (JHM Consulting, Strafford (United States)); Loetman, Jan (Forsmarks Kraftgrupp AB (Sweden)); Sandstedt, Johan (Risk Pilot AB, Stockholm (Sweden))

    2010-12-15

    The objective of this project was a pilot plant demonstration of the EPRI RI-ISI Methodology to selected systems at Forsmark, Unit 3 (F3). This scope of this study encompasses five systems and is based upon F3 implementation of SKIFs guidance as well as other consideration as documented in the PMT program. As described in section 2, five systems were selected for evaluation. These systems were selected because they allow this project to focus on a number of issues of interest in developing a RI-ISI methodology and RI-ISI program. This includes the following: - Several different types of degradation may be identified, - Several different types of 'consequence of failure' may be identified, - Different types of safety systems are evaluated - Non-safety systems are evaluated Using the results of this application, insights and comparisons between SKIFS and the EPRI methodologies' are provided including the following: - Consequence of pressure boundary failure (PBF) as described in Section 3.14. - Degradation mechanism evaluation as described in Section 4.8. - Risk ranking as described in Section 5. - Element selection for inspection as described in Section 6. - Risk impact as described in Section 7

  19. Simulated carbon and water processes of forest ecosystems in Forsmark and Oskarshamn during a 100-year period

    International Nuclear Information System (INIS)

    Gustafsson, David; Jansson, Per-Erik; Gaerdenaes, Annemieke; Eckersten, Henrik

    2006-12-01

    The Swedish Nuclear Fuel and Waste Management Co (SKB) is currently investigating the Forsmark and Oskarshamn areas for possible localisation of a repository for spent nuclear fuel. Important components of the investigations are characterizations of the land surface ecosystems in the areas with respect to hydrological and biological processes, and their implications for the fate of radionuclide contaminants entering the biosphere from a shallow groundwater contamination. In this study, we simulate water balance and carbon turnover processes in forest ecosystems representative for the Forsmark and Oskarshamn areas for a 100-year period using the ecosystem process model CoupModel. The CoupModel describes the fluxes of water and matter in a one-dimensional soil-vegetation-atmosphere system, forced by time series of meteorological variables. The model has previously been parameterized for many of the vegetation systems that can be found in the Forsmark and Oskarshamn areas: spruce/pine forests, willow, grassland and different agricultural crops. This report presents a platform for further use of models like CoupModel for investigations of radionuclide turnover in the Forsmark and Oskarshamn area based on SKB data, including a data set of meteorological forcing variables for Forsmark 1970-2004, suitable for simulations of a 100-year period representing the present day climate, a hydrological parameterization of the CoupModel for simulations of the forest ecosystems in the Forsmark and Oskarshamn areas, and simulated carbon budgets and process descriptions for Forsmark that correspond to a possible steady state of the soil storage of the forest ecosystem

  20. Simulated carbon and water processes of forest ecosystems in Forsmark and Oskarshamn during a 100-year period

    Energy Technology Data Exchange (ETDEWEB)

    Gustafsson, David; Jansson, Per-Erik [Royal Inst. of Technology, Stockholm (Sweden). Dept. of Land and Water Resources Engineering; Gaerdenaes, Annemieke [Swedish Univ. of Agricultural Sciences, Uppsala (Sweden). Dept. of Soil Sciences; Eckersten, Henrik [Swedish Univ. of Agricultural Sciences, Uppsala (Sweden). Dept. of Crop Production Ecology

    2006-12-15

    The Swedish Nuclear Fuel and Waste Management Co (SKB) is currently investigating the Forsmark and Oskarshamn areas for possible localisation of a repository for spent nuclear fuel. Important components of the investigations are characterizations of the land surface ecosystems in the areas with respect to hydrological and biological processes, and their implications for the fate of radionuclide contaminants entering the biosphere from a shallow groundwater contamination. In this study, we simulate water balance and carbon turnover processes in forest ecosystems representative for the Forsmark and Oskarshamn areas for a 100-year period using the ecosystem process model CoupModel. The CoupModel describes the fluxes of water and matter in a one-dimensional soil-vegetation-atmosphere system, forced by time series of meteorological variables. The model has previously been parameterized for many of the vegetation systems that can be found in the Forsmark and Oskarshamn areas: spruce/pine forests, willow, grassland and different agricultural crops. This report presents a platform for further use of models like CoupModel for investigations of radionuclide turnover in the Forsmark and Oskarshamn area based on SKB data, including a data set of meteorological forcing variables for Forsmark 1970-2004, suitable for simulations of a 100-year period representing the present day climate, a hydrological parameterization of the CoupModel for simulations of the forest ecosystems in the Forsmark and Oskarshamn areas, and simulated carbon budgets and process descriptions for Forsmark that correspond to a possible steady state of the soil storage of the forest ecosystem.

  1. Soils and site types in the Forsmark area

    International Nuclear Information System (INIS)

    Lundin, Lars; Lode, Elve; Stendahl, Johan; Melkerud, Per-Arne; Bjoerkvald, Louise; Thorstensson, Anna

    2004-01-01

    and soils influenced by water, such as Gleysols and Histosols, occur frequently. The fairly rich nutrient conditions together with climate and hydrology provided properties for mull and moder humus forms to develop, being more frequent as compared to most other parts of Sweden. Also the O horizon pH was in general high with values around six while Sweden on average show values between four and five. The humus layer are influenced by the underlying mineral soil and pH values there reached 6.5 on average to be compared with values around 5 for most of Sweden. Carbon concentrations in the humus layer agree with Swedish ordinary conditions but in the mineral soil the influence of CaCO 3 makes the concentration higher as compared to the general values for Sweden. There exist also increasing concentrations with depth, which mainly would be attributed to the CaCO 3 content, and deviating from ordinary forest soil conditions. Nitrogen concentrations in the soil agree fairly well with most parts of Sweden. However, the values are lower than the region IV and Uppsala county to which regions the Forsmark area belongs

  2. The limnic ecosystems at Forsmark and Laxemar-Simpevarp

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Eva

    2010-12-15

    The overall objective of this report is to describe the limnic ecosystems at Forsmark and Laxemar- Simpevarp, identify important processes in a radionuclide perspective and provide a description of the radionuclide model for the biosphere used in SR-Site. The report includes a thorough description of the lakes and streams in Forsmark and Laxemar- Simpevarp and covers the following areas: catchment area characteristics, hydrology, climate, sediment characteristics, physical characteristics of streams, habitat distribution in lakes, biotic components (biomass as well as production), water chemistry, and comparison with other lakes and streams in the region, and a historical description. Ecosystem models for carbon and mass balances for a number of elements have been calculated to further improve the understanding of the lake ecosystems. Important processes for the safety assessment are described and evaluated in the report. A separate chapter is included to specifically describe how and where these processes are included in the radionuclide model. The radionuclide model is described and parameterisation and guidance to parameter calculation is provided. The last chapter of the report provides a summary of the knowledge of the limnic systems at the two areas. The Forsmark regional model area contains more than 25 permanent lakes and pools. All lakes are small and shallow, and are characterized as oligotrophic hardwater lakes. Calcareous soils in the area give rise to high calcium concentrations in the surface water, which in turn leads to high pH and low nutrient concentrations in water as phosphorus often co-precipitates with calcium. The shallow depths and moderate water colour permit photosynthesis in the entire benthic habitat of the lakes, and the bottoms are covered by dense stands of the macroalgae Chara sp. Moreover, many of the lakes also have a thick microbial mat (>10 cm), consisting of cyanobacteria and diatoms, in the benthic habitat. Fish in the lakes

  3. The limnic ecosystems at Forsmark and Laxemar-Simpevarp

    International Nuclear Information System (INIS)

    Andersson, Eva

    2010-12-01

    The overall objective of this report is to describe the limnic ecosystems at Forsmark and Laxemar- Simpevarp, identify important processes in a radionuclide perspective and provide a description of the radionuclide model for the biosphere used in SR-Site. The report includes a thorough description of the lakes and streams in Forsmark and Laxemar- Simpevarp and covers the following areas: catchment area characteristics, hydrology, climate, sediment characteristics, physical characteristics of streams, habitat distribution in lakes, biotic components (biomass as well as production), water chemistry, and comparison with other lakes and streams in the region, and a historical description. Ecosystem models for carbon and mass balances for a number of elements have been calculated to further improve the understanding of the lake ecosystems. Important processes for the safety assessment are described and evaluated in the report. A separate chapter is included to specifically describe how and where these processes are included in the radionuclide model. The radionuclide model is described and parameterisation and guidance to parameter calculation is provided. The last chapter of the report provides a summary of the knowledge of the limnic systems at the two areas. The Forsmark regional model area contains more than 25 permanent lakes and pools. All lakes are small and shallow, and are characterized as oligotrophic hardwater lakes. Calcareous soils in the area give rise to high calcium concentrations in the surface water, which in turn leads to high pH and low nutrient concentrations in water as phosphorus often co-precipitates with calcium. The shallow depths and moderate water colour permit photosynthesis in the entire benthic habitat of the lakes, and the bottoms are covered by dense stands of the macroalgae Chara sp. Moreover, many of the lakes also have a thick microbial mat (>10 cm), consisting of cyanobacteria and diatoms, in the benthic habitat. Fish in the lakes

  4. Operative meteorological data base in Forsmark

    International Nuclear Information System (INIS)

    Appelgren, A.; Hallberg, B.; Nordlinder, S.

    1990-01-01

    This report describes how data collected during a field measurement campaign were analysed and compiled to create a data base for operative use. The data base gives information about the wind and the atmospheric stability at five locations around the Forsmark nuclear power plant. In the measurement campaign, sodar systems and a 100 m high tower at Forsmark were used. Temperature, wind speed and wind direction were measured by sensors on the tower, while wind speed and direction, and the standard deviation of the vertical wind, were monitored by the sodar systems. This gave meteorological data from several heights. At Forsmark, the temperature difference and the wind speed from the tower were used to determine the atmospheric stability. At the sodar locations, the stability was deduced by employing a scheme which considered the season, the time of day, the wind direction and the wind speed. To create the operative data base, the wind speeds and wind directions, respectively, from two locations at the time were correlated. A code for graphical and numerical presentation of the data from the data base was developed. A special system of warnings was included, featuring notification about phenomena such as sea breeze, warnings about large variation in the wind conditions within the area, and warnings for situations in which the meteorological conditions make the results from the atmospheric dispersion calculations uncertain. This feature was implemented to alert the user to the fact that ordinary dispersion and dose calculations, using meteorological data from a single point, might give erroneous results. The operative data base and the presentation code were integrated with the dispersion and dose calculation code AIRPAC/EMMA, which is to be used in case of increased releases from nuclear power plants. The possibility to use the data from the operative data base in the dispersion calculations was investigated. It was found that a modification of AIRPAC/EMMA, in such a

  5. Validation of coastal oceanographic models at Forsmark. Site descriptive modelling SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Engqvist, Anders (A och I Engqvist Konsult HB, Vaxholm (SE)); Andrejev, Oleg (Finnish Inst. of Marine Research, Helsinki (FI))

    2008-01-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterisation at two different locations, the Forsmark and the Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. The characterisation work is divided into an initial site investigation phase and a complete site investigation phase. In this context, the water exchange of the coastal zone is one link of the chain of possible nuclide transport mechanisms that must be assessed in the site description of potential repository areas. For the purpose of validating the pair of nested 3D-models employed to simulate the water exchange in the near-shore coastal zone in the Forsmark area, an encompassing measurement program entailing six stations has been performed. The design of this program was to first assess to what degree the forcing of the fine resolution (FR) model of the Forsmark study area at its interfacial boundary to the coarse resolution (CR) model of the entire Baltic was reproduced. In addition to this scrutiny it is of particular interest how the time-varying density-determining properties, salinity and temperature, at the borders are propagated into the FR-domain, since this corresponds to the most efficient mode of water exchange. An important part of the validation process has been to carefully evaluate which measurement data that can be considered reliable. The result was that several periods of foremost near-surface salinity data had to be discarded due to growth of algae on the conductivity sensors. Lack of thorough absolute calibration of the salinity meters also necessitates dismissal of measurement data. Relative the assessed data that can be accepted as adequate, the outcome of the validation can be summarized in five points: (i) The surface-most salinity of the CR-model drifts downward a little less than one practical salinity unit (psu) per year, requiring that the ensuing correlation analysis be subdivided into periods of a

  6. Forsmark site investigation. Reflection seismic studies in the Forsmark area, 2004: Stage 2

    Energy Technology Data Exchange (ETDEWEB)

    Juhlin, Christopher; Palm, Hans [Uppsala Univ. (Sweden). Dept. of Earth Sciences

    2005-06-15

    this structure is limited in this direction. The subhorizontal C1 and C2 reflectors, at about 3 km depth, appear present on nearly all profiles. No pronounced set of reflections corresponding to the group A and B sets found in the south eastern part of the lens on the Stage 1 survey are observed. However, the upper 0.5 s of crust is very reflective north of the Singoe zone. The reflectivity appears to be mainly south dipping. Three new prominent reflectors have been identified in southern part of the survey area (J1, J2 and K1). These have different orientations from the A and B groups of the Stage 1 survey. None of them can be traced to the surface within the survey area. Reflections from the presumed steeply dipping Forsmark, Eckarfjaerden and Singoe deformation zones are not directly observed, consistent with these zones being near vertical. The zones appear to disrupt reflectivity patterns on either side of them and some reflectors appear to terminate against them. However, the fact that profiles are not long enough, lack of 3D control and, on occasion, poorer data quality near the zones imply that this interpretation is very tentative.

  7. Validation of coastal oceanographic models at Forsmark. Site descriptive modelling SDM-Site Forsmark

    International Nuclear Information System (INIS)

    Engqvist, Anders; Andrejev, Oleg

    2008-01-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterisation at two different locations, the Forsmark and the Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. The characterisation work is divided into an initial site investigation phase and a complete site investigation phase. In this context, the water exchange of the coastal zone is one link of the chain of possible nuclide transport mechanisms that must be assessed in the site description of potential repository areas. For the purpose of validating the pair of nested 3D-models employed to simulate the water exchange in the near-shore coastal zone in the Forsmark area, an encompassing measurement program entailing six stations has been performed. The design of this program was to first assess to what degree the forcing of the fine resolution (FR) model of the Forsmark study area at its interfacial boundary to the coarse resolution (CR) model of the entire Baltic was reproduced. In addition to this scrutiny it is of particular interest how the time-varying density-determining properties, salinity and temperature, at the borders are propagated into the FR-domain, since this corresponds to the most efficient mode of water exchange. An important part of the validation process has been to carefully evaluate which measurement data that can be considered reliable. The result was that several periods of foremost near-surface salinity data had to be discarded due to growth of algae on the conductivity sensors. Lack of thorough absolute calibration of the salinity meters also necessitates dismissal of measurement data. Relative the assessed data that can be accepted as adequate, the outcome of the validation can be summarized in five points: (i) The surface-most salinity of the CR-model drifts downward a little less than one practical salinity unit (psu) per year, requiring that the ensuing correlation analysis be subdivided into periods of a

  8. Description of surface systems. Preliminary site description. Forsmark area Version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Lindborg, Tobias [ed.

    2005-06-01

    Swedish Nuclear Fuel and Waste Management Co (SKB) started site investigations for a deep repository for spent nuclear fuel in 2002 at two different sites in Sweden, Forsmark and Oskarshamn. The investigations should provide necessary information for a license application aimed at starting underground exploration. For this reason, ecosystem data need to be interpreted and assessed into site descriptive models, which in turn are used for safety assessment studies and for environmental impact assessment. Descriptions of the surface system are also needed for further planning of the site investigations. This report describes the surface ecosystems of the Forsmark site (e.g. hydrology, Quaternary deposits, chemistry, vegetation, animals and the human land use). The ecosystem description is an integration of the site and its regional setting, covering the current state of the biosphere as well as the ongoing natural processes affecting the longterm development. Improving the descriptions is important during both the initial and the complete site investigation phase. Before starting of the initial phase in Forsmark, version 0 of the site descriptive model was developed. The results of the initial site investigation phase is compiled into a preliminary site description of Forsmark (version 1.2) in June 2005. This report provides the major input and background to the biosphere description, in the 1.2 version of the Forsmark site description. The basis for this interim version is quality-assured field data from the Forsmark sub area and regional area, available in the SKB SICADA, and GIS data bases as of July 31th 2004 as well as version 1.1 of the Site Descriptive Model. To achieve an ecosystem site description there is a need to develop discipline-specific models by interpreting and analysing primary data. The different discipline-specific models are then integrated into a system describing interactions and flows and stocks of matter between and within functional units in

  9. Description of surface systems. Preliminary site description. Forsmark area Version 1.2

    International Nuclear Information System (INIS)

    Lindborg, Tobias

    2005-06-01

    Swedish Nuclear Fuel and Waste Management Co (SKB) started site investigations for a deep repository for spent nuclear fuel in 2002 at two different sites in Sweden, Forsmark and Oskarshamn. The investigations should provide necessary information for a license application aimed at starting underground exploration. For this reason, ecosystem data need to be interpreted and assessed into site descriptive models, which in turn are used for safety assessment studies and for environmental impact assessment. Descriptions of the surface system are also needed for further planning of the site investigations. This report describes the surface ecosystems of the Forsmark site (e.g. hydrology, Quaternary deposits, chemistry, vegetation, animals and the human land use). The ecosystem description is an integration of the site and its regional setting, covering the current state of the biosphere as well as the ongoing natural processes affecting the longterm development. Improving the descriptions is important during both the initial and the complete site investigation phase. Before starting of the initial phase in Forsmark, version 0 of the site descriptive model was developed. The results of the initial site investigation phase is compiled into a preliminary site description of Forsmark (version 1.2) in June 2005. This report provides the major input and background to the biosphere description, in the 1.2 version of the Forsmark site description. The basis for this interim version is quality-assured field data from the Forsmark sub area and regional area, available in the SKB SICADA, and GIS data bases as of July 31th 2004 as well as version 1.1 of the Site Descriptive Model. To achieve an ecosystem site description there is a need to develop discipline-specific models by interpreting and analysing primary data. The different discipline-specific models are then integrated into a system describing interactions and flows and stocks of matter between and within functional units in

  10. Investigation of power oscillation mechanisms based on noise analysis at Forsmark-1 BWR

    International Nuclear Information System (INIS)

    Oguma, Ritsuo

    1996-01-01

    Noise analysis has been performed for stability test data collected during reactor start-up in January 1989 at the boiling water reactor (BWR) Forsmark unit 1. A unique instrumentation to measure local coolant flow in this reactor allowed investigation of dynamic interactions between neutron flux and coolant flow noise signals at different radial positions in the core. The causal relationship for these signals was evaluated based on a method called signal transmission path (STP) analysis with the aim of identifying the principal mechanism of power oscillations in this reactor. The results of the present study indicated that large amplitude power oscillations were induced by two instability mechanisms concurrent in the core. The first is the global void reactivity feedback effect which played the most significant role to power oscillations at a resonant frequency of about 0.53 Hz. The second is the thermal-hydraulics coupling with neutron kinetics, inducing resonant oscillations at about 0.45 Hz. The latter was found to be active only in a certain core region. A peculiar phenomenon of amplitude modulations observed in some local power range monitor (LPRM) signals was also examined. It was interpreted to occur as the consequence of these two resonant power oscillations, the frequencies of which lie close to each other. The noise analysis technique applied in the present study is expected to be useful to get a deeper understanding of the power oscillation mechanism which is active in the reactor under evaluation. The technique may be applicable to BWRs with instruments to measure local channel flow together with in-core neutron detectors. (Author)

  11. The potential for ore and industrial minerals in the Forsmark area

    Energy Technology Data Exchange (ETDEWEB)

    Lindroos, Hardy [MIRAB Mineral Resurser AB, Uppsala (Sweden); Isaksson, Hans; Thunehed, Hans [GeoVista AB, Luleaa (Sweden)

    2004-03-01

    A survey has been made of existing information concerning the potential for ore and industrial minerals in and near the candidate area for a deep repository in Forsmark. A deep repository for spent nuclear fuel should not be located in a rock type or an area where mineral extraction might be considered in the future, since this would make it impossible to exploit this natural resource. Avoiding such areas reduces the risk that people in the future will come into contact with the deep repository through mineral prospecting or mining activities. The survey has made use of all the geoscientific information that was compiled in the more regional investigations in Oesthammar Municipality in 1996-97. In cooperation with the Geological Survey of Sweden (SGU), a new, more detailed mineral resources map has been prepared. The map shows areas with an ore potential that may be unsuitable or unfavourable for siting of a deep repository. The results of the recently completed geophysical helicopter surveys of the Forsmark area are presented in a special chapter. The judgement of the area's ore potential is in part based on the geophysical evaluation of these measurements. Furthermore, the survey obtained information from ongoing deep drillings from the site investigation in Forsmark. In order to better be able to judge the ore potential, the survey has initiated a geochemical investigation of activated soil samples, plus an ore geology sampling of a section in the deep borehole KFM02A, where a hydrothermally altered zone was detected in 2003.The first results from these samplings are presented in the report, which also discusses prospecting efforts in the area as well as relevant Swedish mining legislation. Some suggestions are made for further ore geology investigations. The mineral resources map shows that there is an elongate northwest-southeast zone south and southwest of the candidate area which has a potential for skarn iron ore, and possibly for copper and zinc

  12. The potential for ore and industrial minerals in the Forsmark area

    International Nuclear Information System (INIS)

    Lindroos, Hardy; Isaksson, Hans; Thunehed, Hans

    2004-03-01

    A survey has been made of existing information concerning the potential for ore and industrial minerals in and near the candidate area for a deep repository in Forsmark. A deep repository for spent nuclear fuel should not be located in a rock type or an area where mineral extraction might be considered in the future, since this would make it impossible to exploit this natural resource. Avoiding such areas reduces the risk that people in the future will come into contact with the deep repository through mineral prospecting or mining activities. The survey has made use of all the geoscientific information that was compiled in the more regional investigations in Oesthammar Municipality in 1996-97. In cooperation with the Geological Survey of Sweden (SGU), a new, more detailed mineral resources map has been prepared. The map shows areas with an ore potential that may be unsuitable or unfavourable for siting of a deep repository. The results of the recently completed geophysical helicopter surveys of the Forsmark area are presented in a special chapter. The judgement of the area's ore potential is in part based on the geophysical evaluation of these measurements. Furthermore, the survey obtained information from ongoing deep drillings from the site investigation in Forsmark. In order to better be able to judge the ore potential, the survey has initiated a geochemical investigation of activated soil samples, plus an ore geology sampling of a section in the deep borehole KFM02A, where a hydrothermally altered zone was detected in 2003.The first results from these samplings are presented in the report, which also discusses prospecting efforts in the area as well as relevant Swedish mining legislation. Some suggestions are made for further ore geology investigations. The mineral resources map shows that there is an elongate northwest-southeast zone south and southwest of the candidate area which has a potential for skarn iron ore, and possibly for copper and zinc, although

  13. Noise analysis of Forsmark 1 data to investigate BWR core local instability

    International Nuclear Information System (INIS)

    Oguma, R.

    1998-04-01

    BWR core local instability was experienced at Forsmark 1 (F1) during reactor operation in cycle 16. The event has been studied by applying noise analysis and stability calculations to get insight into the event as well as to identify the cause of local instability. The present report is concerned with noise analysis of data collected during start-up in cycle 17. The results of the current study indicates: The F1 core is quite stable in cycle 17. The max. decay ratio (DR) value of 0.37 was obtained from the stability evaluation of an APRM (average power range monitor) and LPRM (local power range monitor) signals measured at 66% (APRM) of reactor power and 4252 Kg/s (SA-HC) of core flow. Compared with the power profile in cycle 17 (as well as in reactor F2), the core in cycle 16 had an extreme power profile with high power and bottom-shifted axial peak in the core periphery esp. at the four quadrant corners. Such a profile decreases the stability margin in the region. It is a common observation that the DR obtained from APRM tends to be higher than that from LPRM if the global instability mechanism is dominant in the core, and vice versa. The comparison of global and local DR values should be an effective method for detecting local instability during the reactor operation. In order to detect the local instability it is important to evaluate the core stability with sufficient number of LPRMs so as to cover the whole core cross section together with APRMs

  14. Forsmark site investigation. A deformation analysis of the Forsmark GPS monitoring network from 2005 to 2009

    Energy Technology Data Exchange (ETDEWEB)

    Gustafson, Lars; Ljungberg, Annika (Caliterra AB (Sweden))

    2010-10-15

    The objective of the study is to identify possible movements in the bedrock within and outside the candidate area at Forsmark. Seven physically stable stations were built in the Forsmark area in the autumn of 2005. Stations were established within a ten-kilometer radius. The stations were placed in three different areas separated by regional deformation zones: NE of the Singoe zone, within the candidate area, and SW of the Forsmark zone. Data have been collected in eighteen campaigns, each with a duration of about five days, from November 2005 to December 2009. Stations consist of a stainless steel rod fixed in the bedrock on which the GPS antenna mounts. Each station has dedicated GPS equipment only used at the specific site. Sets consist of a GPS receiver collecting raw GPS data and a choke ring antenna linked to the receiver using a coaxial cable. The receivers and antennas are dual frequency high precision geodetic grade. During each campaign the GPS receiver saves a reading every second for the duration of the five days campaign. The antennas remain mounted on the stations during the entire project, whereas all other equipment is in place at the station only during the campaigns. The measurements were related to the SWEPOS network stations Lovoe, Uppsala and Maartsbo that are defined as stations with stable fundaments by the National Land Survey of Sweden (Lantmaeteriet). This report deals with altogether 18 campaigns. The first 13 campaigns were performed during the period November 2005 to August 2008. However, the number of campaigns has been extended by adding a fourth year to the project. Optimization of the data processing depends on the properties of the entire data set comprising a period of four years. We divided the data into periods of 24 hours with each period processed as a separate session in the Bernese post processing software, after which we analyzed the residuals to conclude that data are of the expected quality. The entire data set from four

  15. Forsmark site investigation. Searching for evidence of late- or postglacial faulting in the Forsmark region. Results from 2002-2004

    Energy Technology Data Exchange (ETDEWEB)

    Lagerbaeck, Robert; Sundh, Martin; Svedlund, Jan-Olov; Johansson, Helena [Geological Survey of Sweden, Uppsala (Sweden)

    2005-10-15

    The study was designed to determine whether any major late- or postglacial faulting occurred in the proposed repository area at Forsmark or in its vicinity. 'Major faulting' in this context is defined as dislocations in the order of several metres along faults several kilometres long. Faults of such dimensions may, if conditions are favourable, be detected by means of interpreting aerial photographs. Furthermore, they would have generated high magnitude earthquakes that could produce characteristic distortions in waterlogged sandy or silty sediments. Interpretation of aerial photographs was carried out in a relatively large area in northeast Uppland, with the purpose of looking for morphologically conspicuous lineaments, i.e. late- or postglacial fault candidates. A number of fairly prominent but short escarpments and crevasses were noted, but when later field-checked these candidates for young fault movement proved to be more or less strongly glacially eroded, i.e. formed prior to the last deglaciation. In order to search for seismically induced distortions, all gravel and sand pits being worked in the investigation area were visited and some fifty machine-dug trenches were excavated, mainly in sandy-silty glaciofluvial deposits along eskers. Contorted and folded sequences of glacial clay were encountered at many of the localities, but the disturbances were generally interpreted as caused by sliding. A seismic origin for the sliding cannot be excluded, but no conclusive evidence of this was found. As no distortions attributable to seismically induced liquefaction were noted in any of the trenches excavated along the Boerstil esker, to the southeast of Forsmark, it is concluded that no major (>M7) earthquakes occurred in the Forsmark area after the disappearance of the last inland ice sheet. An erosional unconformity accompanied by a laterally persistent layer of coarse-grained sediments was found in most of the investigated trenches and it is concluded

  16. Forsmark site investigation. Searching for evidence of late- or postglacial faulting in the Forsmark region. Results from 2002-2004

    International Nuclear Information System (INIS)

    Lagerbaeck, Robert; Sundh, Martin; Svedlund, Jan-Olov; Johansson, Helena

    2005-10-01

    The study was designed to determine whether any major late- or postglacial faulting occurred in the proposed repository area at Forsmark or in its vicinity. 'Major faulting' in this context is defined as dislocations in the order of several metres along faults several kilometres long. Faults of such dimensions may, if conditions are favourable, be detected by means of interpreting aerial photographs. Furthermore, they would have generated high magnitude earthquakes that could produce characteristic distortions in waterlogged sandy or silty sediments. Interpretation of aerial photographs was carried out in a relatively large area in northeast Uppland, with the purpose of looking for morphologically conspicuous lineaments, i.e. late- or postglacial fault candidates. A number of fairly prominent but short escarpments and crevasses were noted, but when later field-checked these candidates for young fault movement proved to be more or less strongly glacially eroded, i.e. formed prior to the last deglaciation. In order to search for seismically induced distortions, all gravel and sand pits being worked in the investigation area were visited and some fifty machine-dug trenches were excavated, mainly in sandy-silty glaciofluvial deposits along eskers. Contorted and folded sequences of glacial clay were encountered at many of the localities, but the disturbances were generally interpreted as caused by sliding. A seismic origin for the sliding cannot be excluded, but no conclusive evidence of this was found. As no distortions attributable to seismically induced liquefaction were noted in any of the trenches excavated along the Boerstil esker, to the southeast of Forsmark, it is concluded that no major (>M7) earthquakes occurred in the Forsmark area after the disappearance of the last inland ice sheet. An erosional unconformity accompanied by a laterally persistent layer of coarse-grained sediments was found in most of the investigated trenches and it is concluded that strong

  17. Spatial modelling of marine organisms in Forsmark and Oskarshamn. Including calculation of physical predictor variables

    Energy Technology Data Exchange (ETDEWEB)

    Carlen, Ida; Nikolopoulos, Anna; Isaeus, Martin (AquaBiota Water Research, Stockholm (SE))

    2007-06-15

    GIS grids (maps) of marine parameters were created using point data from previous site investigations in the Forsmark and Oskarshamn areas. The proportion of global radiation reaching the sea bottom in Forsmark and Oskarshamn was calculated in ArcView, using Secchi depth measurements and the digital elevation models for the respective area. The number of days per year when the incoming light exceeds 5 MJ/m2 at the bottom was then calculated using the result of the previous calculations together with measured global radiation. Existing modelled grid-point data on bottom and pelagic temperature for Forsmark were interpolated to create surface covering grids. Bottom and pelagic temperature grids for Oskarshamn were calculated using point measurements to achieve yearly averages for a few points and then using regressions with existing grids to create new maps. Phytoplankton primary production in Forsmark was calculated using point measurements of chlorophyll and irradiance, and a regression with a modelled grid of Secchi depth. Distribution of biomass of macrophyte communities in Forsmark and Oskarshamn was calculated using spatial modelling in GRASP, based on field data from previous surveys. Physical parameters such as those described above were used as predictor variables. Distribution of biomass of different functional groups of fish in Forsmark was calculated using spatial modelling based on previous surveys and with predictor variables such as physical parameters and results from macrophyte modelling. All results are presented as maps in the report. The quality of the modelled predictions varies as a consequence of the quality and amount of the input data, the ecology and knowledge of the predicted phenomena, and by the modelling technique used. A substantial part of the variation is not described by the models, which should be expected for biological modelling. Therefore, the resulting grids should be used with caution and with this uncertainty kept in mind. All

  18. Spatial modelling of marine organisms in Forsmark and Oskarshamn. Including calculation of physical predictor variables

    International Nuclear Information System (INIS)

    Carlen, Ida; Nikolopoulos, Anna; Isaeus, Martin

    2007-06-01

    GIS grids (maps) of marine parameters were created using point data from previous site investigations in the Forsmark and Oskarshamn areas. The proportion of global radiation reaching the sea bottom in Forsmark and Oskarshamn was calculated in ArcView, using Secchi depth measurements and the digital elevation models for the respective area. The number of days per year when the incoming light exceeds 5 MJ/m2 at the bottom was then calculated using the result of the previous calculations together with measured global radiation. Existing modelled grid-point data on bottom and pelagic temperature for Forsmark were interpolated to create surface covering grids. Bottom and pelagic temperature grids for Oskarshamn were calculated using point measurements to achieve yearly averages for a few points and then using regressions with existing grids to create new maps. Phytoplankton primary production in Forsmark was calculated using point measurements of chlorophyll and irradiance, and a regression with a modelled grid of Secchi depth. Distribution of biomass of macrophyte communities in Forsmark and Oskarshamn was calculated using spatial modelling in GRASP, based on field data from previous surveys. Physical parameters such as those described above were used as predictor variables. Distribution of biomass of different functional groups of fish in Forsmark was calculated using spatial modelling based on previous surveys and with predictor variables such as physical parameters and results from macrophyte modelling. All results are presented as maps in the report. The quality of the modelled predictions varies as a consequence of the quality and amount of the input data, the ecology and knowledge of the predicted phenomena, and by the modelling technique used. A substantial part of the variation is not described by the models, which should be expected for biological modelling. Therefore, the resulting grids should be used with caution and with this uncertainty kept in mind. All

  19. Macrofauna on rocky substrates in the Forsmark biotest basin. March 1984 - March 1985

    International Nuclear Information System (INIS)

    Snoeijs, P.; Mo, K.

    1987-09-01

    The Forsmark biotest basin, situated on the Swedish east coast, is an artificial offshore brackish lake, through which the cooling water is channelled from the Forsmark nuclear power plant to the Bothnian Sea. The biotest basin is up to 10 0 C warmer than the sea surrounding it, and has no ice cover in winter. There is an artificial, fast current in a large part of the basin. Macrofauna on stones in the hydrolittoral belt was sampled at 11 sites in- and outside the basin every third week during one year. The numbers of individuals per m 2 for each taxon were counted. Diversity indices and dominance-diversity curves were computed for each site on the basis of pooled data for the cold season, and for the rest of the year. In total 66 taxa were distinguished in the species lists, of which 3 are sessile, the rest free-living. (orig./DG)

  20. Statement about KBS-3

    International Nuclear Information System (INIS)

    Styrelsen.

    1984-02-01

    The National Institute of Radiation Protection has examined the basis for the application of the Swedish Nuclear Fuel Supply Company for permission to load the nuclear reactors Forsmark-3 and Oskarshamn-3, regarding the special nuclear law. The institute find that the proposed method for handling and final disposal of spent nuclear fuel will comply with the abovementioned law regarding radiation protection. The law does also require a programme for research and development. No such programme has been distributed.(P.Aa)

  1. Mapping of reed in shallow bays. SFR-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Stroemgren, Maarten; Lindgren, Fredrik (Umeaa Univ. (Sweden))

    2011-03-15

    The regolith-lake development model (RLDM) describes the development of shallow bays to lakes and the infilling of lakes in the Forsmark area during an interglacial. The sensitivity analysis has shown the need for an update of the infill procedure in the RLDM. Data from the mapping of reed in shallow bays in the Forsmark area will be used to improve the infill procedure of an updated RLDM. The field work was performed in August 26-31, 2010. The mapping of reed was done in 124 points. In these points, coordinates and water depth were mapped using an echo sounder and a DGPS. Quaternary deposits and the thickness of soft sediments were mapped using an earth probe. Measurement points were delivered in ESRI shape format with coordinates in RT90 2.5 gon W and altitudes in the RHB70 system for storage in SKB's GIS data base

  2. Present status and an appreciation of the consequences for recreation and outdoor leisure activities from siting a nuclear waste repository at Forsmark; Nulaegesanalys samt bedoemning av konsekvenser foer rekreation och friluftsliv av ett slutfoervar i Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Ottosson, Pia [Atrax Energi AB, Stockholm (Sweden)

    2007-07-15

    This report describes how the area around Forsmark is used with respect to recreation and outdoor life. It also describes the impact of the final repository on recreation and outdoor life if it is located in Forsmark. The studied area is situated in the parish of Forsmark in the municipality of Oesthammar. Forsmark nuclear power plant and the final repository for radioactive operational waste, SFR, are situated within the area and there are both houses and holiday houses. The area is used for leisure pursuit by inhabitants and employees at FKA and SKB, but also by a number of different associations and by tourists. Statistical data shows that the parish of Forsmark is sparsely populated. The area was previously dominated by one big landowner and the land surrounding the nuclear power plant was inaccessible to the general public during that period. The outdoor life is therefore less widespread here than along other parts of the east coast. The value of the area does not lie in paths and trails, bike tracks and bathing places, but in the unspoiled countryside, the wildlife and the bird life. Recreation such as hunting and fishing is very popular in the area. The construction of a final repository will increase traffic and hence increase noise and motion in the area. This will mainly impact the enjoyment value for the people spending time in the area. No other significant consequences are expected as the final repository will be mainly situated within the existing industrial complex and hence the character of the area should remain unchanged.

  3. The examination of KBS-3 by SSI

    International Nuclear Information System (INIS)

    1983-02-01

    The National Institute of Radiation Protection has examined the basis for the application of the permission to load the nuclear reactors Forsmark-3 and Oskarshamn-3, regarding the special nuclear law. The Institute finds that the proposed method for handling and final disposal of spent nuclear fuel will comply with the above mentioned law regarding radiation protection. The law also requires a programme for research and development. No such programme has been distributed.(author)

  4. Soils and site types in the Forsmark area

    Energy Technology Data Exchange (ETDEWEB)

    Lundin, Lars; Lode, Elve; Stendahl, Johan; Melkerud, Per-Arne; Bjoerkvald, Louise; Thorstensson, Anna [Swedish Univ. of Agricultural Sciences, Uppsala (Sweden). Dept. of Forest Soils

    2004-01-01

    Investigations to give prerequisites for long-term storage of nuclear waste are made by the Swedish Nuclear Fuel and Waste Management Company (SKB AB). Ecosystem functions are crucial in this management. The range of the scope is wide including bedrock, regolith, hydrosphere and biosphere. The interface between deep geological formations and surface systems is then considered very important. This would be the top of the regolith, where soils are developed. Special attention has been paid to these layers with fairly comprehensive investigations. Field investigations were made for one of the candidate areas, the Forsmark area, in 2002 by the Department of Forest Soils, Swedish University of Agricultural Sciences. In these ecosystem functions, the upper part of the regolith is one crucial component and the focus in the investigations was on the upper metre of the soil. Variables determined include vegetation, hydrology, soil parent material, textural composition, soil type and physical and chemical properties of relevant soil layers. Methods used in the investigation coincide with those of the Swedish Forest Soil Inventory, which provide possibilities to compare properties in the Forsmark area with those of total Sweden and regions of the country. Soil properties were determined thoroughly on eight site types in two replicates to provide statistical significance. However, this meant that the investigation did not have a total spatial coverage. Instead, the spatial distribution of soils in the area was determined from a GIS based on the inventory made and information on vegetation types, distribution of Quaternary deposits and a hydrological index. From this GIS, distributions were compared with other parts of the country. The geographical location of the Forsmark area (N 60 deg 22 min; E 18 deg 13 min) is on the northeast coast of central Sweden bordering to the Bothnian Sea. The area is low-lying, reaching only up to 15 m above the sea, which means that the soils are

  5. Complementary modelling of radionuclide retention in the near-surface system at Forsmark. Development of a reactive transport model using Forsmark 1.2 data

    Energy Technology Data Exchange (ETDEWEB)

    Sena, Clara; Grandia, Fidel; Arcos, David; Molinero, Jorge; Duro, Lara (Amphos XXI Consulting S.L., Barcelona (Spain))

    2008-10-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is conducting a comprehensive geoscientific characterization of two alternative sites to allocate a deep geological repository of high level nuclear waste. The Site Characterization Program also includes the near-surface systems, which are expected to constitute the last geological barrier between the repository system and the earth's surface. The evaluation of the retention capacity of the near surface systems is, therefore, very relevant for the site characterization program. From the geological point of view, near-surface systems in the Forsmark area consist of Quaternary deposits that overlay a granitic bedrock. Glacial till is the most abundant outcropping Quaternary deposit (approx75% of surface extension) and the remainder is made up of clayey materials (glacial and post-glacial clays). These types of near-surface sediments show distinctive hydraulic and geochemical features. The main reactive mineral in the till deposits, for the time scale considered in this work, is calcium carbonate (calcite). This mineral is found along with clay minerals (e.g. illite) and Fe(III) hydroxides. In contrast, glacial and post-glacial clays are basically composed of illite with minor amounts of calcium carbonate, and containing organic matter-rich levels (gyttja) which can promote reducing conditions in the system. The assessment of the migration behaviour of selected long-lived radionuclides through the near-surface system of Forsmark was developed in an earlier work, that focused on the evaluation of the capacity of the Quaternary deposits for radionuclide retention. The work reported here is an improvement of the geochemical conceptual and numerical model already presented, based on data available in the Site Descriptive Model v 1.2 (Forsmark). Regarding the geochemical variability of the Quaternary deposits present at Forsmark and its implications on radionuclide mobility through the near-surface systems, a

  6. Review of the conclusions of the 1996 workshop on safety culture, in Forsmark, Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Eckered, T [PROMENT LTD (Sweden)

    1997-09-01

    The IAEA/SiP Senior Managers Workshop on International Promotion of Safety Culture for the NPPs with RBMK reactors was organized by IAEA and the Swedish International Project Nuclear Safety (SiP). It took place at the Forsmark NPP, Sweden, from 1 to 4 October 1996. The objective of the workshop were to provide a forum managers to exchange national and international experience on factors influencing safety culture, to better understand these factors and to further enhance promotion of safety culture. The Workshop participants started work by agreeing to seek the answers to the following three questions: 1. What constitutes a good Safety Culture? 2. What is good and bad in our own countries and plants from a Safety Culture point of view? 3. Where can we find advice and help from our colleagues to improve our own Safety Culture? This was the first workshop specifically addressing Safety Culture in RBMK countries. The aim was therefore not to produce good practices, but to lay a foundation for further work and development. A follow-up workshop should deepen the understanding of the SC concept and address specific SC matters identified at this Workshop.

  7. Review of the conclusions of the 1996 workshop on safety culture, in Forsmark, Sweden

    International Nuclear Information System (INIS)

    Eckered, T.

    1997-01-01

    The IAEA/SiP Senior Managers Workshop on International Promotion of Safety Culture for the NPPs with RBMK reactors was organized by IAEA and the Swedish International Project Nuclear Safety (SiP). It took place at the Forsmark NPP, Sweden, from 1 to 4 October 1996. The objective of the workshop were to provide a forum managers to exchange national and international experience on factors influencing safety culture, to better understand these factors and to further enhance promotion of safety culture. The Workshop participants started work by agreeing to seek the answers to the following three questions: 1. What constitutes a good Safety Culture? 2. What is good and bad in our own countries and plants from a Safety Culture point of view? 3. Where can we find advice and help from our colleagues to improve our own Safety Culture? This was the first workshop specifically addressing Safety Culture in RBMK countries. The aim was therefore not to produce good practices, but to lay a foundation for further work and development. A follow-up workshop should deepen the understanding of the SC concept and address specific SC matters identified at this Workshop

  8. Thermal modelling. Preliminary site description. Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Sundberg, Jan; Back, Paer-Erik; Bengtsson, Anna; Laendell, Maerta [Geo Innova AB, Linkoeping (Sweden)

    2005-08-01

    This report presents the thermal site descriptive model for the Forsmark area, version 1.2. The main objective of this report is to present the thermal modelling work where data has been identified, quality controlled, evaluated and summarised in order to make an upscaling to lithological domain level possible. The thermal conductivity at canister scale has been modelled for two different lithological domains (RFM029 and RFM012, both dominated by granite to granodiorite (101057)). A main modelling approach has been used to determine the mean value of the thermal conductivity. Two alternative/complementary approaches have been used to evaluate the spatial variability of the thermal conductivity at domain level. The thermal modelling approaches are based on the lithological model for the Forsmark area, version 1.2 together with rock type models constituted from measured and calculated (from mineral composition) thermal conductivities. Results indicate that the mean of thermal conductivity is expected to exhibit a small variation between the different domains, 3.46 W/(mxK) for RFM012 to 3.55 W/(mxK) for RFM029. The spatial distribution of the thermal conductivity does not follow a simple model. Lower and upper 95% confidence limits are based on the modelling results, but have been rounded of to only two significant figures. Consequently, the lower limit is 2.9 W/(mxK), while the upper is 3.8 W/(mxK). This is applicable to both the investigated domains. The temperature dependence is rather small with a decrease in thermal conductivity of 10.0% per 100 deg C increase in temperature for the dominating rock type. There are a number of important uncertainties associated with these results. One of the uncertainties considers the representative scale for the canister. Another important uncertainty is the methodological uncertainties associated with the upscaling of thermal conductivity from cm-scale to canister scale. In addition, the representativeness of rock samples is

  9. Impact assessment of the impact on nature values of the construction and operation of the repository for spent nuclear fuel at Forsmark; Konsekvensbedoemning av paaverkan paa naturvaerden av anlaeggande och drift av slutfoervar foer anvaent kaernbraensle i Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Allmer, Johan (Ekologigruppen AB, Stockholm (Sweden))

    2011-03-15

    Construction and operation of a repository at Soederviken in Forsmark, Oesthammar municipality means impact, effects and consequences for the environment. This report describes the natural conditions and natural values in Forsmark with particular focus on Soederviken. Furthermore, an assessment of consequences for the natural environment in the development and operation of a repository at Soederviken. Assessment of impacts from water activities are treated in a special report.

  10. Background complementary hydrogeochemical studies. SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Kalinowski, Birgitta E. (ed.)

    2008-08-15

    in geochemistry, hydrochemistry, hydrogeochemistry, microbiology, geomicrobiology, analytical chemistry etc. The resulting site descriptive model version, mainly based on 2.2 data and complementary 2.3 data, was carried out during September 2006 to December 2007. Several groups within ChemNet were involved and the evaluation was conducted independently using different approaches ranging from expert knowledge to geochemical and mathematical modelling including transport modelling. During regular ChemNet meetings the results have been presented and discussed. This report is a compilation of different projects that have been finished independently of each other. Section 1: M3 modelling and 2D visualisation of the hydrochemical parameters by Ioana Gurban. The focus of this part is on updating the hydrochemical model, to make uncertainty tests and to present the final models that can be integrated better with the hydrodynamic models. M3 modelling helps to summarise and understand the measured data, by using the major elements and the isotopes delta18O and delta2H as variables. The visualisation of the mixing proportions along the boreholes helps to understand the distribution of the data in the domain and to check and compare the results of different models; and therefore to choose the model which best describes the measured data. Section 2: Coupled hydrogeological and solute transport, visualisation and supportive detailed reaction modelling by Jorge Molinero, David Arcos, Lara Duro. Reactive mixing and reactive solute transport models are used as quantitative tools in order to evaluate how much disturbance can be allowed for a given groundwater sample at repository depth and still meet the SKB suitability criteria. Spatial analysis and 3D visualisation of available representative samples in Forsmark was performed. The computed M3 mixing fractions show a spatial distribution qualitatively correlated with key hydrochemical signatures, such as strontium (for Deep Saline

  11. The occurrence of waterfowl in the biotest basin at the Forsmark nuclear power plant, Sweden, 1981-1984

    International Nuclear Information System (INIS)

    Sandstroem, U.

    1985-01-01

    During the period Sep 1981 to Aug 1984 a monthly census was taken of waterfowl in the Biotest basin and its surroundings at Forsmark, as well as in a reference area in the region. During the same period the staff of the Biotest basin made weekly censuses of the basin. The aim of the censuses was to establish if there was any increase in the number of waterfowl in the Biotest basin and its surroundings caused by the discharge of cooling water from the two nuclear power reactors that are in operation in Forsmark. Seventeen waterfowl species were observed in the area during the period studied. Of these species five were regularly observed viz.: the Mute Swan (Cygnus olor), the Mallard (Anas plathyryncos), the Tufted Duck (Aythya fuligula), the Goldeneye (Bucephala clangula) and the Goosander (Mergus merganser). The first four species were generally found in low numbers in the Biotest basin and its surroundings, as well as in the reference area. This implies that the Biotest basin and its surroundings has not become an area of importance during the winter for waterfowl, with one exception: the Goosander. The Goosander showed an increasing population growth in the Biotest basin and its surroundings during the studied period with a maximum average in in the basin during the last winter. As a result, the size of the Goosander population may affect the number of small fish in the Biotest basin. (author)

  12. Modelling of temperature in deep boreholes and evaluation of geothermal heat flow at Forsmark and Laxemar

    Energy Technology Data Exchange (ETDEWEB)

    Sundberg, Jan; Back, Paer-Erik; Laendell, Maerta; Sundberg, Anders (GEO INNOVA AB, Linkoeping (Sweden))

    2009-06-15

    This report presents modelling of temperature and temperature gradients in boreholes in Laxemar and Forsmark and fitting to measured temperature data. The modelling is performed with an analytical expression including thermal conductivity, thermal diffusivity, heat flow, internal heat generation and climate events in the past. As a result of the fitting procedure it is also possible to evaluate local heat flow values for the two sites. However, since there is no independent evaluation of the heat flow, uncertainties in for example thermal conductivity, diffusivity and the palaeoclimate temperature curve are transferred into uncertainties in the heat flow. Both for Forsmark and Laxemar, reasonably good fits were achieved between models and data on borehole temperatures. However, none of the general models achieved a fit within the 95% confidence intervals of the measurements. This was achieved in some cases for the additional optimised models. Several of the model parameters are uncertain. A good model fit does not automatically imply that 'correct' values have been used for these parameters. Similar model fits can be expected with different sets of parameter values. The palaeoclimatically corrected surface mean heat flow at Forsmark and Laxemar is suggested to be 61 and 56 mW/m2 respectively. If all uncertainties are combined, including data uncertainties, the total uncertainty in the heat flow determination is judged to be within +12% to -14% for both sites. The corrections for palaeoclimate are quite large and verify the need of site-specific climate descriptions. Estimations of the current ground surface temperature have been made by extrapolations from measured temperature logging. The mean extrapolated ground surface temperature in Forsmark and Laxemar is estimated to 6.5 deg and 7.3 deg C respectively. This is approximately 1.7 deg C higher for Forsmark, and 1.6 deg C higher for Laxemar compared to data in the report SKB-TR-06-23. Comparison with

  13. Modelling of temperature in deep boreholes and evaluation of geothermal heat flow at Forsmark and Laxemar

    International Nuclear Information System (INIS)

    Sundberg, Jan; Back, Paer-Erik; Laendell, Maerta; Sundberg, Anders

    2009-05-01

    This report presents modelling of temperature and temperature gradients in boreholes in Laxemar and Forsmark and fitting to measured temperature data. The modelling is performed with an analytical expression including thermal conductivity, thermal diffusivity, heat flow, internal heat generation and climate events in the past. As a result of the fitting procedure it is also possible to evaluate local heat flow values for the two sites. However, since there is no independent evaluation of the heat flow, uncertainties in for example thermal conductivity, diffusivity and the palaeoclimate temperature curve are transferred into uncertainties in the heat flow. Both for Forsmark and Laxemar, reasonably good fits were achieved between models and data on borehole temperatures. However, none of the general models achieved a fit within the 95% confidence intervals of the measurements. This was achieved in some cases for the additional optimised models. Several of the model parameters are uncertain. A good model fit does not automatically imply that 'correct' values have been used for these parameters. Similar model fits can be expected with different sets of parameter values. The palaeoclimatically corrected surface mean heat flow at Forsmark and Laxemar is suggested to be 61 and 56 mW/m 2 respectively. If all uncertainties are combined, including data uncertainties, the total uncertainty in the heat flow determination is judged to be within +12% to -14% for both sites. The corrections for palaeoclimate are quite large and verify the need of site-specific climate descriptions. Estimations of the current ground surface temperature have been made by extrapolations from measured temperature logging. The mean extrapolated ground surface temperature in Forsmark and Laxemar is estimated to 6.5 deg and 7.3 deg C respectively. This is approximately 1.7 deg C higher for Forsmark, and 1.6 deg C higher for Laxemar compared to data in the report SKB-TR-06-23. Comparison with air

  14. The limnic ecosystems at Forsmark and Laxemar-Simpevarp. Site descriptive modelling SDM-Site

    Energy Technology Data Exchange (ETDEWEB)

    Norden, Sara; Soederbaeck, Bjoern [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Andersson, Eva [SWECO, Stockholm (Sweden)

    2008-11-15

    The overall objective of this report is to provide a thorough description of the limnic ecosystems at both Forsmark and Laxemar-Simpevarp. This information may be used in the Safety Assessment and as a basis for the Environmental Impact Assessment. Three aims were set up for the report: 1) to characterize and describe the limnic ecosystems today and in the past in the Forsmark and Laxemar-Simpevarp areas and compare these ecosystems with limnic ecosystems in other areas; 2) to evaluate and visualize major pools, fluxes and sinks of elements within the limnic ecosystems; and finally 3) to describe human impact on the limnic ecosystems. The report includes a thorough description of the lakes and streams in Forsmark and Laxemar-Simpevarp and covers the following areas: catchment area characteristics, hydrology, climate, sediment characteristics, physical characteristics of streams, habitat distribution in lakes, biotic components, water chemistry, comparisons with other lakes and streams in the region, and a historical description. Ecosystem models for carbon and mass balances for a number of elements have been calculated to further improve the understanding of the lake ecosystems. Important processes for the safety assessment are described and evaluated in the report. The Forsmark regional model area contains more than 20 permanent lakes and pools. All lakes are small and shallow, and are characterized as oligotrophic hardwater lakes. Calcareous soils in the area give rise to high calcium concentrations in the surface water, which in turn leads to high pH and low nutrient concentrations in water as phosphorus often co-precipitates with calcium. The shallow depths and moderate water colour permit photosynthesis in the entire benthic habitat of the lakes, and the bottoms are covered by dense stands of the macroalgae Chara sp. Moreover, many of the lakes also have a thick microbial mat (>10 cm), consisting of cyanobacteria and diatoms, in the benthic habitat. Fish in

  15. Reactor safety research in Sweden

    International Nuclear Information System (INIS)

    Pershagen, B.

    1980-02-01

    Objectives, means and results of Swedish light water reactor safety research during the 1970s are reviewed. The expenditure is about 40 Million Swkr per year excluding industry. Large efforts have been devoted to experimental studies of loss of coolant accidents. Large scale containment response tests for simulated pipe breaks were carried out at the Marviken facility. At Studsvik a method for testing fuel during fast power changes has been developed. Stress corrosion, crack growth and the effect of irradiation on the strength ductility of Zircaloy tube was studied. A method for determining the fracture toughness of pressure vessel steel was developed and it was shown that the fracture toughness was lower than earlier assumed. The release of fission products to reactor water was studied and so was the release, transport and removal of airborne radioactive matter for Swedish BWRs and PWRs. Test methods for iodine filter systems were developed. A system for continuous monitoring of radioactive noble gas stack release was developed for the Ringhals plant. Attention was drawn to the importance of the human factor for reactor safety. Probabilistic methods for risk analysis were applied to the Barsebaeck 2 and Forsmark 3 boiling water reactors. Procedures and working conditions for operator personnel were investigated. (GBn)

  16. Monitoring Forsmark. Bird monitoring in Forsmark 2010

    Energy Technology Data Exchange (ETDEWEB)

    Green, Martin (Dept. of Animal Ecology, Lund Univ. (Sweden))

    2010-12-15

    This report summarizes the monitoring of selected listed (Swedish Red List and/or the EU Birds Directive) breeding birds in Forsmark 2002-2010. Monitoring of eleven listed species was conducted in the regional model area, including the candidate area in 2010 in the same way as in earlier years. The results from the monitoring in 2010 differed somewhat from results gathered in earlier years. Most monitored species have increased in local numbers during the study years, and from most years continued increases have been reported. Between 2009 and 2010 most species (seven, 64% of the monitored ones) instead decreased in numbers. Only one species (honey buzzard) increased in numbers between the years and in this case this was probably more a result of small moves by certain pairs so that they this year had parts reaching into the regional model area, while in 2009 their territories were outside of this. No dramatic changes in bird numbers were however recorded and all the studied species show stable or increasing local populations over the study period. Number of Black-throated diver pairs was normal and breeding success was good this year. The breeding success of divers has improved considerably over the studied period and the patterns recorded in Forsmark closely follow recorded patterns at the national level. Honey buzzards and ospreys occurred in good numbers, above the average for the whole period, and breeding success was better than in 2009. Even if breeding success of honey buzzards is not monitored in any detail, there were still signs of at least a few successful breedings in the area this year. Breeding success of ospreys was below average, but still within the normal variation for most years. The local white-tailed eagles had a poor breeding season and no young at all were produced within the study area. All three grouse species (black grouse, capercaillie and hazelhen) decreased in numbers between 2009 and 2010. Note however that the large amounts of snow

  17. Monitoring Forsmark. Bird monitoring in Forsmark 2010

    International Nuclear Information System (INIS)

    Green, Martin

    2010-12-01

    This report summarizes the monitoring of selected listed (Swedish Red List and/or the EU Birds Directive) breeding birds in Forsmark 2002-2010. Monitoring of eleven listed species was conducted in the regional model area, including the candidate area in 2010 in the same way as in earlier years. The results from the monitoring in 2010 differed somewhat from results gathered in earlier years. Most monitored species have increased in local numbers during the study years, and from most years continued increases have been reported. Between 2009 and 2010 most species (seven, 64% of the monitored ones) instead decreased in numbers. Only one species (honey buzzard) increased in numbers between the years and in this case this was probably more a result of small moves by certain pairs so that they this year had parts reaching into the regional model area, while in 2009 their territories were outside of this. No dramatic changes in bird numbers were however recorded and all the studied species show stable or increasing local populations over the study period. Number of Black-throated diver pairs was normal and breeding success was good this year. The breeding success of divers has improved considerably over the studied period and the patterns recorded in Forsmark closely follow recorded patterns at the national level. Honey buzzards and ospreys occurred in good numbers, above the average for the whole period, and breeding success was better than in 2009. Even if breeding success of honey buzzards is not monitored in any detail, there were still signs of at least a few successful breedings in the area this year. Breeding success of ospreys was below average, but still within the normal variation for most years. The local white-tailed eagles had a poor breeding season and no young at all were produced within the study area. All three grouse species (black grouse, capercaillie and hazelhen) decreased in numbers between 2009 and 2010. Note however that the large amounts of snow

  18. Inventory of mammals at Forsmark and Haallnaes; Inventering av daeggdjur i Forsmark och Haallnaes

    Energy Technology Data Exchange (ETDEWEB)

    Truve, Johan [Svensk Naturfoervaltning AB, Goeteborg (Sweden)

    2012-08-15

    A selection of terrestrial mammals was surveyed in the SKB site investigation areas near Forsmark and Haallnaes between January and April 2012. The methods that were used include snow tracking along line transects, snow tracking along water, aerial survey and fecal pellet counts. The same species were found in 2012 as in previous surveys performed in 2002, 2003 and 2007. Some species show a large variation in density between years and it is difficult to draw any conclusions about their long term development. Several carnivores, i.e. lynx, fox and otter show a positive growth rate in both areas. The wild boar population is also growing whilst moose density remains fairly stable and roe deer are becoming less numerous.

  19. Water activities in Forsmark. Ecological field inventory and classification of biodiversity values and description of forest production land

    International Nuclear Information System (INIS)

    Hamren, Ulrika; Collinder, Per

    2010-12-01

    In 2009, the Swedish Nuclear Fuel and Waste Management Co (SKB) chose Forsmark in the Municipality of Oesthammar as site for the final repository for spent nuclear fuel. This report describes nature values and forestry areas in Forsmark, and provides part of the background material for description of consequences due to groundwater diversion during construction and operation of the repository. The report describes results of map studies and comprehensive field investigations, in terms of geographical delineations, descriptions of characteristics and classifications of nature values for groundwater dependent or groundwater favoured nature objects in Forsmark. The nature objects are located in an investigation area, which contains the area that according to numerical flow modelling could be affected by groundwater-table drawdown due to groundwater diversion

  20. Discrete-Feature Model Implementation of SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Geier, Joel (Clearwater Hardrock Consulting, Corvallis, OR (United States))

    2010-03-15

    A discrete-feature model (DFM) was implemented for the Forsmark repository site based on the final site descriptive model from surface based investigations. The discrete-feature conceptual model represents deformation zones, individual fractures, and other water-conducting features around a repository as discrete conductors surrounded by a rock matrix which, in the present study, is treated as impermeable. This approximation is reasonable for sites in crystalline rock which has very low permeability, apart from that which results from macroscopic fracturing. Models are constructed based on the geological and hydrogeological description of the sites and engineering designs. Hydraulic heads and flows through the network of water-conducting features are calculated by the finite-element method, and are used in turn to simulate migration of non-reacting solute by a particle-tracking method, in order to estimate the properties of pathways by which radionuclides could be released to the biosphere. Stochastic simulation is used to evaluate portions of the model that can only be characterized in statistical terms, since many water-conducting features within the model volume cannot be characterized deterministically. Chapter 2 describes the methodology by which discrete features are derived to represent water-conducting features around the hypothetical repository at Forsmark (including both natural features and features that result from the disturbance of excavation), and then assembled to produce a discrete-feature network model for numerical simulation of flow and transport. Chapter 3 describes how site-specific data and repository design are adapted to produce the discrete-feature model. Chapter 4 presents results of the calculations. These include utilization factors for deposition tunnels based on the emplacement criteria that have been set forth by the implementers, flow distributions to the deposition holes, and calculated properties of discharge paths as well as

  1. Discrete-Feature Model Implementation of SDM-Site Forsmark

    International Nuclear Information System (INIS)

    Geier, Joel

    2010-03-01

    A discrete-feature model (DFM) was implemented for the Forsmark repository site based on the final site descriptive model from surface based investigations. The discrete-feature conceptual model represents deformation zones, individual fractures, and other water-conducting features around a repository as discrete conductors surrounded by a rock matrix which, in the present study, is treated as impermeable. This approximation is reasonable for sites in crystalline rock which has very low permeability, apart from that which results from macroscopic fracturing. Models are constructed based on the geological and hydrogeological description of the sites and engineering designs. Hydraulic heads and flows through the network of water-conducting features are calculated by the finite-element method, and are used in turn to simulate migration of non-reacting solute by a particle-tracking method, in order to estimate the properties of pathways by which radionuclides could be released to the biosphere. Stochastic simulation is used to evaluate portions of the model that can only be characterized in statistical terms, since many water-conducting features within the model volume cannot be characterized deterministically. Chapter 2 describes the methodology by which discrete features are derived to represent water-conducting features around the hypothetical repository at Forsmark (including both natural features and features that result from the disturbance of excavation), and then assembled to produce a discrete-feature network model for numerical simulation of flow and transport. Chapter 3 describes how site-specific data and repository design are adapted to produce the discrete-feature model. Chapter 4 presents results of the calculations. These include utilization factors for deposition tunnels based on the emplacement criteria that have been set forth by the implementers, flow distributions to the deposition holes, and calculated properties of discharge paths as well as

  2. Soil carbon effluxes in ecosystems of Forsmark and Laxemar

    Energy Technology Data Exchange (ETDEWEB)

    Tagesson, Torbern (Dept. of Physical Geography and Ecosystem Analysis, Lund Univ. (Sweden))

    2007-12-15

    Soil carbon effluxes were estimated in a number of ecosystems in Laxemar and Forsmark investigations areas. It was done in a young Scots pine (Pinus sylvestris) stand, a wet deciduous stand, a poor fen and an agricultural field in the Laxemar investigation area in south-eastern Sweden (57 deg 5 min N, 16 deg 7 min E) and in a pasture, two Norway spruce (Picea abies) stands, a deciduous forest, a mire, a wet deciduous forest and a clear-cut in the Forsmark investigation area (60 deg 4 min N, 18 deg 2 min E). It was measured with the closed chamber technique in 2005 and 2006. Soil temperature at 10 cm depth, air temperature and photosynthetically active radiation (PAR) were also measured. Exponential regressions with soil respiration against air and soil temperature were used to estimate annual soil respiration. A hyperbolic curve with Gross Primary Production (GPP) against PAR was used for modelling GPP for the growing season in the poor fen and the agricultural area of Laxemar. The exponential regressions with soil respiration against air and soil temperature explained on average 33.6% and 44.0% of the variation, respectively. GPP of the ground vegetation were reducing soil carbon effluxes, in all stands but one of the spruce stands, the deciduous forest, the mire and the wet deciduous forest of Forsmark. The significant (all but spruce 2 in Forsmark) curves with GPP against PAR explained on average 22.7% of the variation in GPP. The cubic regressions with GPP against air temperature were only significant for the poor fen and the agricultural field in Laxemar and it explained on average 34.8% of the variation in GPP for these ecosystems. The exponential regressions with air and soil temperature against soil respiration could be used to temporally extrapolate the occasional field measurements. The hyperbolic curve with GPP against PAR could also be used for temporal extrapolation of GPP for the ecosystems without a tree layer, i.e. the poor fen and the agricultural

  3. Soil carbon effluxes in ecosystems of Forsmark and Laxemar

    International Nuclear Information System (INIS)

    Tagesson, Torbern

    2007-12-01

    Soil carbon effluxes were estimated in a number of ecosystems in Laxemar and Forsmark investigations areas. It was done in a young Scots pine (Pinus sylvestris) stand, a wet deciduous stand, a poor fen and an agricultural field in the Laxemar investigation area in south-eastern Sweden (57 deg 5 min N, 16 deg 7 min E) and in a pasture, two Norway spruce (Picea abies) stands, a deciduous forest, a mire, a wet deciduous forest and a clear-cut in the Forsmark investigation area (60 deg 4 min N, 18 deg 2 min E). It was measured with the closed chamber technique in 2005 and 2006. Soil temperature at 10 cm depth, air temperature and photosynthetically active radiation (PAR) were also measured. Exponential regressions with soil respiration against air and soil temperature were used to estimate annual soil respiration. A hyperbolic curve with Gross Primary Production (GPP) against PAR was used for modelling GPP for the growing season in the poor fen and the agricultural area of Laxemar. The exponential regressions with soil respiration against air and soil temperature explained on average 33.6% and 44.0% of the variation, respectively. GPP of the ground vegetation were reducing soil carbon effluxes, in all stands but one of the spruce stands, the deciduous forest, the mire and the wet deciduous forest of Forsmark. The significant (all but spruce 2 in Forsmark) curves with GPP against PAR explained on average 22.7% of the variation in GPP. The cubic regressions with GPP against air temperature were only significant for the poor fen and the agricultural field in Laxemar and it explained on average 34.8% of the variation in GPP for these ecosystems. The exponential regressions with air and soil temperature against soil respiration could be used to temporally extrapolate the occasional field measurements. The hyperbolic curve with GPP against PAR could also be used for temporal extrapolation of GPP for the ecosystems without a tree layer, i.e. the poor fen and the agricultural

  4. Hydraulic effects of unsealed boreholes. Numerical groundwater flow modelling of the Forsmark and Laxemar sites

    International Nuclear Information System (INIS)

    Bockgaard, Niclas

    2011-06-01

    The objective of the work was to investigate hydraulic effects of open and poorly sealed boreholes on groundwater flow conditions through simulations using a numerical groundwater model. Specifically, the boreholes KFM07A, KFM09A, and KFM09B in Forsmark and the boreholes KLX04, KLX06, and KLX10 in Laxemar were studied. The criteria for the selection of these boreholes were that the boreholes should represent typical conditions of the site, the borehole length should exceed 500 m, and that several major fractured zones should be intersected. The boreholes KFM07A and KLX06, respectively, were selected as reference boreholes for more detailed studies of different sealing schemes. The model setup of the Forsmark model followed the Forsmark 2.2 regional-scale conceptual hydrogeological model. The model domain was approximately 15 km (north-south) x 10 km (west- east) x 1.2 km (depth). The 131 deformation zones and three layers of superficial horizontal sheet joint were modelled deterministically. A stochastic discrete fracture network (DFN) representing fractures and minor deformation zones were also generated between the deterministic deformation zones inside central model volume. The side lengths of the square fractures were from 1,000 m down to 10 m. In order to resolve the details of flow in to and out from the borehole, a more detailed DFN was generated in a zone around the borehole KFM07A, where fractures down to a side length of 0.5 m were considered. The model setup of the Laxemar model followed the SDM-Site Laxemar (Laxemar 2.3) regional scale conceptual hydrogeological model. The model domain was approximately 12 km (north-south) x 20 km (west-east) x 2.1 km (depth). A number of 71 deformation zones were modelled deterministically, and one realization of a stochastic DFN, the so-called hydrogeological DFN model base case, was imported to the model. Similar to the Forsmark case, a more detailed DFN was also generated around the reference borehole KLX06. The

  5. Hydraulic effects of unsealed boreholes. Numerical groundwater flow modelling of the Forsmark and Laxemar sites

    Energy Technology Data Exchange (ETDEWEB)

    Bockgaard, Niclas [Golder Associates AB, Stockholm (Sweden)

    2011-06-15

    The objective of the work was to investigate hydraulic effects of open and poorly sealed boreholes on groundwater flow conditions through simulations using a numerical groundwater model. Specifically, the boreholes KFM07A, KFM09A, and KFM09B in Forsmark and the boreholes KLX04, KLX06, and KLX10 in Laxemar were studied. The criteria for the selection of these boreholes were that the boreholes should represent typical conditions of the site, the borehole length should exceed 500 m, and that several major fractured zones should be intersected. The boreholes KFM07A and KLX06, respectively, were selected as reference boreholes for more detailed studies of different sealing schemes. The model setup of the Forsmark model followed the Forsmark 2.2 regional-scale conceptual hydrogeological model. The model domain was approximately 15 km (north-south) x 10 km (west- east) x 1.2 km (depth). The 131 deformation zones and three layers of superficial horizontal sheet joint were modelled deterministically. A stochastic discrete fracture network (DFN) representing fractures and minor deformation zones were also generated between the deterministic deformation zones inside central model volume. The side lengths of the square fractures were from 1,000 m down to 10 m. In order to resolve the details of flow in to and out from the borehole, a more detailed DFN was generated in a zone around the borehole KFM07A, where fractures down to a side length of 0.5 m were considered. The model setup of the Laxemar model followed the SDM-Site Laxemar (Laxemar 2.3) regional scale conceptual hydrogeological model. The model domain was approximately 12 km (north-south) x 20 km (west-east) x 2.1 km (depth). A number of 71 deformation zones were modelled deterministically, and one realization of a stochastic DFN, the so-called hydrogeological DFN model base case, was imported to the model. Similar to the Forsmark case, a more detailed DFN was also generated around the reference borehole KLX06. The

  6. Displacement along extensive deformation zones at the two SKB sites: Forsmark and Laxemar

    International Nuclear Information System (INIS)

    Beckholmen, Monica; Tiren, Sven A.

    2010-12-01

    The Fennoscandian shield, a part of the East European Craton, is distinguished by the exposed bedrock which is mainly composed of Precambrian metamorphic and igneous rocks. Large parts of the ground surface closely coincides with a late Precambrian denudation surface; the sub-Cambrian peneplain. Palaeozoic and younger sediments were deposited on the peneplain but these sediments have been removed from most areas that now form the mainland of Sweden and Finland and there are just a few remnants left. In the Baltic Sea, located in large-scale depressions on the boundary of in the Fennoscandian Shield/ in the East European Craton/, the Precambrian bedrock is still in large parts covered by Palaeozoic sediments. The Palaeozoic sedimentary rocks, as they are well bedded, may form a memory of the late Palaeozoic and younger tectonic events in the underlying basement rocks. Such data are used here to complement the structural observations made at sites located on the mainland, giving information on displacement along faults. Significant for the Baltic Sea are faults oriented in N-S that appear as segments, displaced relative to each other. Other structures are oriented in E-W, NE-SW and NW-SE. The SKB Forsmark site is located in a relatively flat coastal area within the sub-Cambrian peneplain. The sea area at the Forsmark site has a more accentuated relief than what is found on the mainland, for example, a furrow along the western side of the N-S oriented island Graesoe northeast of Forsmark (below 30m b.s.l. and locally more than 50m lower than Graesoe) and the deep between Aaland and Sweden (301m b.s.l.) about 100km east-southeast of Forsmark. In the Forsmark-site area two sets of structures interfere: a WNWESE trending set with relatively straight faults along the north coast of Uppland and a NNW-SSE to N-S trending set, slightly curved, along the (north)east coast of Uppland. The Forsmark site is located in an elevated WNW trending lath-shaped rock block outlined by

  7. Displacement along extensive deformation zones at the two SKB sites: Forsmark and Laxemar

    Energy Technology Data Exchange (ETDEWEB)

    Beckholmen, Monica; Tiren, Sven A. (GEOSIGMA AB (Sweden))

    2010-12-15

    The Fennoscandian shield, a part of the East European Craton, is distinguished by the exposed bedrock which is mainly composed of Precambrian metamorphic and igneous rocks. Large parts of the ground surface closely coincides with a late Precambrian denudation surface; the sub-Cambrian peneplain. Palaeozoic and younger sediments were deposited on the peneplain but these sediments have been removed from most areas that now form the mainland of Sweden and Finland and there are just a few remnants left. In the Baltic Sea, located in large-scale depressions on the boundary of in the Fennoscandian Shield/ in the East European Craton/, the Precambrian bedrock is still in large parts covered by Palaeozoic sediments. The Palaeozoic sedimentary rocks, as they are well bedded, may form a memory of the late Palaeozoic and younger tectonic events in the underlying basement rocks. Such data are used here to complement the structural observations made at sites located on the mainland, giving information on displacement along faults. Significant for the Baltic Sea are faults oriented in N-S that appear as segments, displaced relative to each other. Other structures are oriented in E-W, NE-SW and NW-SE. The SKB Forsmark site is located in a relatively flat coastal area within the sub-Cambrian peneplain. The sea area at the Forsmark site has a more accentuated relief than what is found on the mainland, for example, a furrow along the western side of the N-S oriented island Graesoe northeast of Forsmark (below 30m b.s.l. and locally more than 50m lower than Graesoe) and the deep between Aaland and Sweden (301m b.s.l.) about 100km east-southeast of Forsmark. In the Forsmark-site area two sets of structures interfere: a WNWESE trending set with relatively straight faults along the north coast of Uppland and a NNW-SSE to N-S trending set, slightly curved, along the (north)east coast of Uppland. The Forsmark site is located in an elevated WNW trending lath-shaped rock block outlined by

  8. Site investigation SFR. Vegetation in streams in the Forsmark area

    International Nuclear Information System (INIS)

    Andersson, Eva; Aquilonius, Karin; Sivars Becker, Lena; Borgiel, Mikael

    2011-09-01

    The streams in the model area of Forsmark have previously been thoroughly investigated regarding water chemistry, hydrology, bottom substrate, flooding, percentage coverage of macrophytes and fish migration. Retention of radionuclides in a stream ecosystem is assumed to occur by sorption to sediments or by uptake of radionuclides by macrophytes and it is therefore of interest to know the biomass and production of macrophytes in the streams included in a safety assessment. The general aim of this study was to examine the relation between biomass and the percentage cover of vegetation in streams in the Forsmark area. In this study streams within and nearby the candidate area in Forsmark was investigated. The somewhat larger streams Forsmarksaan and Olandsaan nearby the candidate area, are assumed to be more similar to future streams developing in Forsmark due to landrise, than the smaller streams present in the candidate area today. In total 22 vegetation samples were gathered in order to estimate the biomass at the sites. Percentage coverage of macrophytes, and dominating species were noted and the above ground macrophytes were sampled for biomass analysis. In the smaller streams, the biomass varied between 6 and almost 358 g dry weight per square metre. In the larger streams, the dry biomass varied between 0 and 247 g dry weight per square meter. There were no significant difference between macrophyte biomass in smaller and the larger stream. In total 13 macrophyte species were found. The biomass dry weight at 100% covering degree varied depending on macrophyte species. Although this was a rather small study, it is evident that the biomasses do vary a wide range between sampling squares in the area. However, although it may be difficult to use this data set to estimate the biomass in a specific square meter in the stream section, the relation between biomass weight and covering degree is sufficient to be used when fitting biomass to macrophyte coverage for entire

  9. Site investigation SFR. Vegetation in streams in the Forsmark area

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Eva (Svensk Nuclear Fuel and Waste Management Co. (Sweden)); Aquilonius, Karin; Sivars Becker, Lena (Studsvik Nuclear AB (Sweden)); Borgiel, Mikael (Sveriges Vattenekologer AB (Sweden))

    2011-09-15

    The streams in the model area of Forsmark have previously been thoroughly investigated regarding water chemistry, hydrology, bottom substrate, flooding, percentage coverage of macrophytes and fish migration. Retention of radionuclides in a stream ecosystem is assumed to occur by sorption to sediments or by uptake of radionuclides by macrophytes and it is therefore of interest to know the biomass and production of macrophytes in the streams included in a safety assessment. The general aim of this study was to examine the relation between biomass and the percentage cover of vegetation in streams in the Forsmark area. In this study streams within and nearby the candidate area in Forsmark was investigated. The somewhat larger streams Forsmarksaan and Olandsaan nearby the candidate area, are assumed to be more similar to future streams developing in Forsmark due to landrise, than the smaller streams present in the candidate area today. In total 22 vegetation samples were gathered in order to estimate the biomass at the sites. Percentage coverage of macrophytes, and dominating species were noted and the above ground macrophytes were sampled for biomass analysis. In the smaller streams, the biomass varied between 6 and almost 358 g dry weight per square metre. In the larger streams, the dry biomass varied between 0 and 247 g dry weight per square meter. There were no significant difference between macrophyte biomass in smaller and the larger stream. In total 13 macrophyte species were found. The biomass dry weight at 100% covering degree varied depending on macrophyte species. Although this was a rather small study, it is evident that the biomasses do vary a wide range between sampling squares in the area. However, although it may be difficult to use this data set to estimate the biomass in a specific square meter in the stream section, the relation between biomass weight and covering degree is sufficient to be used when fitting biomass to macrophyte coverage for entire

  10. Recharge and discharge of near-surface groundwater in Forsmark. Comparison of classification methods

    International Nuclear Information System (INIS)

    Werner, Kent; Johansson, Per-Olof; Brydsten, Lars; Bosson, Emma; Berglund, Sten

    2007-03-01

    This report presents and compares data and models for identification of near-surface groundwater recharge and discharge (RD) areas in Forsmark. The general principles of groundwater recharge and discharge are demonstrated and applied to interpret hydrological and hydrogeological observations made in the Forsmark area. 'Continuous' RD classification methods considered in the study include topographical modelling, map overlays, and hydrological-hydrogeological flow modelling. 'Discrete' (point) methods include field-based and hydrochemistry-based RD classifications of groundwater monitoring well locations. The topographical RD modelling uses the digital elevation model as the only input. The map overlays use background maps of Quaternary deposits, soils, and ground- and field layers of the vegetation/land use map. Further, the hydrological-hydrogeological modelling is performed using the MIKE SHE-MIKE 11 software packages, taking into account e.g. topography, meteorology, hydrogeology, and geometry of watercourses and lakes. The best between-model agreement is found for the topography-based model and the MIKE SHE-MIKE 11 model. The agreement between the topographical model and the map overlays is less good. The agreement between the map overlays on the one hand, and the MIKE SHE and field-based RD classifications on the other, is thought to be less good, as inferred from the comparison made with the topography-based model. However, much improvement of the map overlays can likely be obtained, e.g. by using 'weights' and calibration (such exercises were outside the scope of the present study). For field-classified 'recharge wells', there is a good agreement to the hydrochemistry-based (Piper plot) well classification, but less good for the field-classified 'discharge wells'. In addition, the concentration of the age-dating parameter tritium shows low variability among recharge wells, but a large spread among discharge wells. The usefulness of hydrochemistry-based RD

  11. Application of the Drilling Impact Study (DIS) to Forsmark groundwaters

    International Nuclear Information System (INIS)

    Gascoyne, Mel; Gurban, Ioana

    2008-01-01

    Characterisation of a geological formation as a repository for nuclear fuel waste requires deep drilling into the bedrock to gain an understanding of the geological structure, rock types, groundwater flow and the chemical composition of groundwater and the adjacent rock. The methods of characterisation from a hydrogeochemical point of view, might be affected by the various drilling activities and techniques for determining groundwater composition have been employed so that the composition can be corrected for these activities. SKB has developed and supported the Drilling Impact Study (DIS) project in which a tracer is used as an indicator of contamination to attempt to correct the groundwater composition for dilution or contamination by surface waters. The project began about five years ago with the intention of developing a routine method for determining the extent of contamination of borehole groundwater by drilling water. The main objectives of this work were: 1. Determine the extent of drilling water contamination in permeable zones in a test borehole on the Forsmark site. 2. Correct measured chemical compositions of the groundwaters based on contamination results. 3. Provide a workable methodology for routine correction of groundwater composition. 4. Apply the modified DIS model to suitable borehole zones at the Forsmark site in a systematic fashion 5. Determine uncertainties in DIS modelling. A memorandum was prepared by describing the characteristics of borehole KFM06 and its drilling history. Estimates were made of the amount of drilling water in permeable zones in the borehole and the various approaches to applying results of DIS were described and recommendations made, with an example calculation

  12. Bedrock geology Forsmark. Modelling stage 2.3. Implications for and verification of the deterministic geological models based on complementary data

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, Michael B. (Geological Survey of Sweden, Uppsala (Sweden)); Simeonov, Assen (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)); Isaksson, Hans (GeoVista AB, Luleaa (Sweden))

    2008-12-15

    The Swedish Nuclear Fuel and Waste Management Company is in the process of completing site descriptive modelling at two locations in Sweden, with the objective to site a deep geological repository for spent nuclear fuel. At Forsmark, the results of the stage 2.2 geological modelling formed the input for downstream users. Since complementary ground and borehole geological and geophysical data, acquired after model stage 2.2, were not planned to be included in the deterministic rock domain, fracture domain and deformation zone models supplied to the users, it was deemed necessary to evaluate the implications of these stage 2.3 data for the stage 2.2 deterministic geological models and, if possible, to make use of these data to verify the models. This report presents the results of the analysis of the complementary stage 2.3 geological and geophysical data. Model verification from borehole data has been implemented in the form of a prediction-outcome test. The stage 2.3 geological and geophysical data at Forsmark mostly provide information on the bedrock outside the target volume. Additional high-resolution ground magnetic data and the data from the boreholes KFM02B, KFM11A, KFM12A and HFM33 to HFM37 can be included in this category. Other data complement older information of identical character, both inside and outside this volume. These include the character and kinematics of deformation zones and fracture mineralogy. In general terms, it can be stated that all these new data either confirm the geological modelling work completed during stage 2.2 or are in good agreement with the data that were used in this work. In particular, although the new high-resolution ground magnetic data modify slightly the position and trace length of some stage 2.2 deformation zones at the ground surface, no new or modified deformation zones with a trace length longer than 3,000 m at the ground surface have emerged. It is also apparent that the revision of fracture orientation data

  13. Bedrock geology Forsmark. Modelling stage 2.3. Implications for and verification of the deterministic geological models based on complementary data

    International Nuclear Information System (INIS)

    Stephens, Michael B.; Simeonov, Assen; Isaksson, Hans

    2008-12-01

    The Swedish Nuclear Fuel and Waste Management Company is in the process of completing site descriptive modelling at two locations in Sweden, with the objective to site a deep geological repository for spent nuclear fuel. At Forsmark, the results of the stage 2.2 geological modelling formed the input for downstream users. Since complementary ground and borehole geological and geophysical data, acquired after model stage 2.2, were not planned to be included in the deterministic rock domain, fracture domain and deformation zone models supplied to the users, it was deemed necessary to evaluate the implications of these stage 2.3 data for the stage 2.2 deterministic geological models and, if possible, to make use of these data to verify the models. This report presents the results of the analysis of the complementary stage 2.3 geological and geophysical data. Model verification from borehole data has been implemented in the form of a prediction-outcome test. The stage 2.3 geological and geophysical data at Forsmark mostly provide information on the bedrock outside the target volume. Additional high-resolution ground magnetic data and the data from the boreholes KFM02B, KFM11A, KFM12A and HFM33 to HFM37 can be included in this category. Other data complement older information of identical character, both inside and outside this volume. These include the character and kinematics of deformation zones and fracture mineralogy. In general terms, it can be stated that all these new data either confirm the geological modelling work completed during stage 2.2 or are in good agreement with the data that were used in this work. In particular, although the new high-resolution ground magnetic data modify slightly the position and trace length of some stage 2.2 deformation zones at the ground surface, no new or modified deformation zones with a trace length longer than 3,000 m at the ground surface have emerged. It is also apparent that the revision of fracture orientation data

  14. Electrical Dynamic Simulation Activities in Forsmark NPP

    International Nuclear Information System (INIS)

    Lamell, Per

    2015-01-01

    The original power system analysis was done in the seventies in former ASEA AB software. For approximate twenty years no major new studies was done because of limited numbers of renewal projects. In the end of the nineties the plant started to update the selectivity planning and study of the loading of the safety bus-bars. The simulation and start of the development of simulation models was done in a tool named Simpow. Simpow was also an ASEA/ABB AB software developed from the program used in the seventies. To continue to work with Simpow was a decision made after doing an extensive review of on the marked available commercially software. Also at that time we start to do our first attempt building electrical simulation models of unit 1 and 2 according to the original documentation. The development of models for the unit 1, 2 and 3 became more intensive some years after the millennium. Partly because of event July 25, 2006 and also because of the renewal of unit 1 and 2 and had subsequently been initiated for unit 3 also. Today we have initiated a conversion of our models to a new program called PowerFactory. That due to the withdrawal of support and development on SIMPOW a couple of years ago. To development relevance, accuracy and detail, models are an important issue for FKA (Forsmark Kraftgrupp AB). The model is initially created according to the plant documentation and also including requested information from the original supplier. Continued development and updates of the model is done according to the data received from the contractors via the demands according to requirements in our technical documents on different electrical components in renewal projects. The development of the model is driven by known weaknesses, depending of the type of studies and necessary data related to events. An important part that will be described is to have a verified simulation tool and validated models. An example is that the models have been validated by making start and

  15. The limnic ecosystems at Forsmark and Laxemar-Simpevarp. Site descriptive modelling SDM-Site

    International Nuclear Information System (INIS)

    Norden, Sara; Soederbaeck, Bjoern; Andersson, Eva

    2008-11-01

    The overall objective of this report is to provide a thorough description of the limnic ecosystems at both Forsmark and Laxemar-Simpevarp. This information may be used in the Safety Assessment and as a basis for the Environmental Impact Assessment. Three aims were set up for the report: 1) to characterize and describe the limnic ecosystems today and in the past in the Forsmark and Laxemar-Simpevarp areas and compare these ecosystems with limnic ecosystems in other areas; 2) to evaluate and visualize major pools, fluxes and sinks of elements within the limnic ecosystems; and finally 3) to describe human impact on the limnic ecosystems. The report includes a thorough description of the lakes and streams in Forsmark and Laxemar-Simpevarp and covers the following areas: catchment area characteristics, hydrology, climate, sediment characteristics, physical characteristics of streams, habitat distribution in lakes, biotic components, water chemistry, comparisons with other lakes and streams in the region, and a historical description. Ecosystem models for carbon and mass balances for a number of elements have been calculated to further improve the understanding of the lake ecosystems. Important processes for the safety assessment are described and evaluated in the report. The Forsmark regional model area contains more than 20 permanent lakes and pools. All lakes are small and shallow, and are characterized as oligotrophic hardwater lakes. Calcareous soils in the area give rise to high calcium concentrations in the surface water, which in turn leads to high pH and low nutrient concentrations in water as phosphorus often co-precipitates with calcium. The shallow depths and moderate water colour permit photosynthesis in the entire benthic habitat of the lakes, and the bottoms are covered by dense stands of the macroalgae Chara sp. Moreover, many of the lakes also have a thick microbial mat (>10 cm), consisting of cyanobacteria and diatoms, in the benthic habitat. Fish in

  16. Radon as a groundwater tracer in Forsmark and Laxemar

    International Nuclear Information System (INIS)

    Grolander, Sara

    2009-10-01

    Radon concentrations were measured in different water types in Forsmark and Laxemar during the site investigation and within this study. From these measurements it can be concluded that large differences between surface water, near surface groundwater and deep groundwater can be found in both Laxemar and Forsmark. The differences in radon concentrations between different water types are used in this study to detect interactions between surface water, near surface water and deep groundwater. From the radon measurements it can also be concluded that radon concentration in deep groundwater varies largely with depth. These variations with depth are probably caused by groundwater flow in conductive fracture zones in the bedrock. The focus of this study has been the radon concentration of near surface groundwater and the interaction between near surface groundwater and deep groundwater. Radon measurements have been done using the RAD-7 radon detector within this study. It could be concluded that RAD-7 is a good technique for radon measurements and also easy to use in field. The radon concentrations measured in near surface groundwater in Laxemar within this study were low and homogenous. The variation in radon concentration has been analyses and compared to other parameters. Since the hypothesis of this study has been that there are differences in radon concentrations between recharging and discharging groundwater, the most important parameter to consider is the recharge/discharge field classification of the wells. No correlation between the recharge/discharge classifications of wells and the radon concentrations were found. The lack of correlation between groundwater flow patterns and radon concentration means that it is not possible to detect flow patterns in near surface groundwater using radon as a tracer in the Laxemar area. The lack of correlation can be caused by the fact that there are just a few wells located in areas classified as recharge area. It can also be

  17. Radon as a groundwater tracer in Forsmark and Laxemar

    Energy Technology Data Exchange (ETDEWEB)

    Grolander, Sara

    2009-10-15

    Radon concentrations were measured in different water types in Forsmark and Laxemar during the site investigation and within this study. From these measurements it can be concluded that large differences between surface water, near surface groundwater and deep groundwater can be found in both Laxemar and Forsmark. The differences in radon concentrations between different water types are used in this study to detect interactions between surface water, near surface water and deep groundwater. From the radon measurements it can also be concluded that radon concentration in deep groundwater varies largely with depth. These variations with depth are probably caused by groundwater flow in conductive fracture zones in the bedrock. The focus of this study has been the radon concentration of near surface groundwater and the interaction between near surface groundwater and deep groundwater. Radon measurements have been done using the RAD-7 radon detector within this study. It could be concluded that RAD-7 is a good technique for radon measurements and also easy to use in field. The radon concentrations measured in near surface groundwater in Laxemar within this study were low and homogenous. The variation in radon concentration has been analyses and compared to other parameters. Since the hypothesis of this study has been that there are differences in radon concentrations between recharging and discharging groundwater, the most important parameter to consider is the recharge/discharge field classification of the wells. No correlation between the recharge/discharge classifications of wells and the radon concentrations were found. The lack of correlation between groundwater flow patterns and radon concentration means that it is not possible to detect flow patterns in near surface groundwater using radon as a tracer in the Laxemar area. The lack of correlation can be caused by the fact that there are just a few wells located in areas classified as recharge area. It can also be

  18. Statistical geological discrete fracture network model. Forsmark modelling stage 2.2

    Energy Technology Data Exchange (ETDEWEB)

    Fox, Aaron; La Pointe, Paul [Golder Associates Inc (United States); Simeonov, Assen [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Hermanson, Jan; Oehman, Johan [Golder Associates AB, Stockholm (Sweden)

    2007-11-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is performing site characterization at two different locations, Forsmark and Laxemar, in order to locate a site for a final geologic repository for spent nuclear fuel. The program is built upon the development of Site Descriptive Models (SDMs) at specific timed data freezes. Each SDM is formed from discipline-specific reports from across the scientific spectrum. This report describes the methods, analyses, and conclusions of the geological modeling team with respect to a geological and statistical model of fractures and minor deformation zones (henceforth referred to as the geological DFN), version 2.2, at the Forsmark site. The geological DFN builds upon the work of other geological modelers, including the deformation zone (DZ), rock domain (RD), and fracture domain (FD) models. The geological DFN is a statistical model for stochastically simulating rock fractures and minor deformation zones as a scale of less than 1,000 m (the lower cut-off of the DZ models). The geological DFN is valid within four specific fracture domains inside the local model region, and encompassing the candidate volume at Forsmark: FFM01, FFM02, FFM03, and FFM06. The models are build using data from detailed surface outcrop maps and the cored borehole record at Forsmark. The conceptual model for the Forsmark 2.2 geological revolves around the concept of orientation sets; for each fracture domain, other model parameters such as size and intensity are tied to the orientation sets. Two classes of orientation sets were described; Global sets, which are encountered everywhere in the model region, and Local sets, which represent highly localized stress environments. Orientation sets were described in terms of their general cardinal direction (NE, NW, etc). Two alternatives are presented for fracture size modeling: - the tectonic continuum approach (TCM, TCMF) described by coupled size-intensity scaling following power law distributions

  19. Statistical geological discrete fracture network model. Forsmark modelling stage 2.2

    International Nuclear Information System (INIS)

    Fox, Aaron; La Pointe, Paul; Simeonov, Assen; Hermanson, Jan; Oehman, Johan

    2007-11-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is performing site characterization at two different locations, Forsmark and Laxemar, in order to locate a site for a final geologic repository for spent nuclear fuel. The program is built upon the development of Site Descriptive Models (SDMs) at specific timed data freezes. Each SDM is formed from discipline-specific reports from across the scientific spectrum. This report describes the methods, analyses, and conclusions of the geological modeling team with respect to a geological and statistical model of fractures and minor deformation zones (henceforth referred to as the geological DFN), version 2.2, at the Forsmark site. The geological DFN builds upon the work of other geological modelers, including the deformation zone (DZ), rock domain (RD), and fracture domain (FD) models. The geological DFN is a statistical model for stochastically simulating rock fractures and minor deformation zones as a scale of less than 1,000 m (the lower cut-off of the DZ models). The geological DFN is valid within four specific fracture domains inside the local model region, and encompassing the candidate volume at Forsmark: FFM01, FFM02, FFM03, and FFM06. The models are build using data from detailed surface outcrop maps and the cored borehole record at Forsmark. The conceptual model for the Forsmark 2.2 geological revolves around the concept of orientation sets; for each fracture domain, other model parameters such as size and intensity are tied to the orientation sets. Two classes of orientation sets were described; Global sets, which are encountered everywhere in the model region, and Local sets, which represent highly localized stress environments. Orientation sets were described in terms of their general cardinal direction (NE, NW, etc). Two alternatives are presented for fracture size modeling: - the tectonic continuum approach (TCM, TCMF) described by coupled size-intensity scaling following power law distributions

  20. Hydrogeochemical evaluation. Preliminary site description Forsmark area - version 1.2

    International Nuclear Information System (INIS)

    Laaksoharju, Marcus

    2005-03-01

    Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Forsmark and Laxemar-Simpevarp, on the eastern coast of Sweden to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 which represents the second evaluation of the available Forsmark groundwater analytical data collected up to June, 2004. The Hydrochemical Analytical Group (HAG) had access to data where a total of 1,131 water samples had been collected from the surface and sub-surface environment; 252 samples were collected from drilled boreholes. The deepest fracture groundwater samples with sufficient analytical data reflected depths down to 1 km. Most of the waters sampled (66%) lacked crucial analytical information that restricted the evaluation. Model version 1.2 focuses on geochemical and mixing processes affecting the groundwater composition in the uppermost part of the bedrock, down to repository levels, and eventually extending to 1,000 m depth. The complex groundwater evolution and patterns at Forsmark are a result of many factors such as: a) the present-day topography and proximity to the Baltic Sea, b) past changes in hydrogeology related to glaciation/deglaciation, land uplift and repeated marine/lake water regressions/ transgressions, and c) organic or inorganic alteration of the groundwater composition caused by microbial processes or water/rock interactions. The sampled groundwaters reflect to various degrees processes relating to modern or ancient water/rock interactions and mixing. The groundwater flow regimes at Forsmark are considered local and extend down to depths of around 600 m depending on hydraulic conditions. Close to the Baltic Sea coastline where topographical variation is even less, groundwater flow penetration to depth will subsequently be less marked and such areas will tend to be characterised by groundwater

  1. Hydrogeochemical evaluation. Preliminary site description Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Laaksoharju, Marcus (ed.) [Geopoint AB, Stockholm (Sweden)

    2005-03-15

    Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Forsmark and Laxemar-Simpevarp, on the eastern coast of Sweden to determine their geological, hydrogeochemical and hydrogeological characteristics. Present work completed has resulted in Model version 1.2 which represents the second evaluation of the available Forsmark groundwater analytical data collected up to June, 2004. The Hydrochemical Analytical Group (HAG) had access to data where a total of 1,131 water samples had been collected from the surface and sub-surface environment; 252 samples were collected from drilled boreholes. The deepest fracture groundwater samples with sufficient analytical data reflected depths down to 1 km. Most of the waters sampled (66%) lacked crucial analytical information that restricted the evaluation. Model version 1.2 focuses on geochemical and mixing processes affecting the groundwater composition in the uppermost part of the bedrock, down to repository levels, and eventually extending to 1,000 m depth. The complex groundwater evolution and patterns at Forsmark are a result of many factors such as: a) the present-day topography and proximity to the Baltic Sea, b) past changes in hydrogeology related to glaciation/deglaciation, land uplift and repeated marine/lake water regressions/ transgressions, and c) organic or inorganic alteration of the groundwater composition caused by microbial processes or water/rock interactions. The sampled groundwaters reflect to various degrees processes relating to modern or ancient water/rock interactions and mixing. The groundwater flow regimes at Forsmark are considered local and extend down to depths of around 600 m depending on hydraulic conditions. Close to the Baltic Sea coastline where topographical variation is even less, groundwater flow penetration to depth will subsequently be less marked and such areas will tend to be characterised by

  2. Landscape Forsmark - data, methodology and results for SR-Site

    Energy Technology Data Exchange (ETDEWEB)

    Lindborg, Tobias [ed.; Svensk Kaernbraenslehantering AB (Sweden)

    2010-12-15

    This report presents an integrated description of the landscape at the Forsmark site during the succession from present conditions to the far future. It was produced as a part of the biosphere modelling within the SR-Site safety assessment. The report gives a description of input data, methodology and resulting models used to support the current understanding of the landscape used in SR-Site. It is intended to describe the properties and conditions at the site and to give information essential for demonstrating understanding. The report relies heavily on a number of discipline-specific background reports concerning details of the data analyses and modelling. Long-term landscape development in the Forsmark area is dependent on two main and partly interdependent factors, i.e. climate variations and shoreline displacement. These two factors in combination strongly affect a number of processes, which in turn determine the development of ecosystems. Some examples of such processes are erosion and sedimentation, groundwater recharge and discharge, soil formation, primary production and decomposition of organic matter. The biosphere at the site during the next 1,000 years is assumed to be quite similar to the present situation. The most important changes are the natural infilling of lakes and a slight withdrawal of the sea with its effects on the near-shore areas and the shallow coastal basins. The climate during the rest of the temperate period may vary considerably, with both warmer and colder periods. The main effect of temperature changes will be on the vegetation period. Changed temperatures may give rise to drier or wetter climate and to changed snow cover and frost characteristics, and this can in turn affect the dominant vegetation and mire build-up. The description of the Forsmark ecosystem succession during a glacial cycle is one of the main features of the SR-Site biosphere modelling. The future areas potentially affected by deep groundwater discharge are

  3. Landscape Forsmark - data, methodology and results for SR-Site

    International Nuclear Information System (INIS)

    Lindborg, Tobias

    2010-12-01

    This report presents an integrated description of the landscape at the Forsmark site during the succession from present conditions to the far future. It was produced as a part of the biosphere modelling within the SR-Site safety assessment. The report gives a description of input data, methodology and resulting models used to support the current understanding of the landscape used in SR-Site. It is intended to describe the properties and conditions at the site and to give information essential for demonstrating understanding. The report relies heavily on a number of discipline-specific background reports concerning details of the data analyses and modelling. Long-term landscape development in the Forsmark area is dependent on two main and partly interdependent factors, i.e. climate variations and shoreline displacement. These two factors in combination strongly affect a number of processes, which in turn determine the development of ecosystems. Some examples of such processes are erosion and sedimentation, groundwater recharge and discharge, soil formation, primary production and decomposition of organic matter. The biosphere at the site during the next 1,000 years is assumed to be quite similar to the present situation. The most important changes are the natural infilling of lakes and a slight withdrawal of the sea with its effects on the near-shore areas and the shallow coastal basins. The climate during the rest of the temperate period may vary considerably, with both warmer and colder periods. The main effect of temperature changes will be on the vegetation period. Changed temperatures may give rise to drier or wetter climate and to changed snow cover and frost characteristics, and this can in turn affect the dominant vegetation and mire build-up. The description of the Forsmark ecosystem succession during a glacial cycle is one of the main features of the SR-Site biosphere modelling. The future areas potentially affected by deep groundwater discharge are

  4. Experience from the MTO program at the Forsmark nuclear power plant

    International Nuclear Information System (INIS)

    Rollenhagen, C.; Andersson, O.

    1996-01-01

    Within the nuclear industry there are two events which have had a significant impact on the way of thinking and attitudes to safety, although in different ways. The TMI accident at Harrisburg, USA put the focus on the man-machine interface, the way of working and attitudes to safety. The accident at Chernobyl focused on safety management and safety culture. After the Chernobyl accident, safety culture (IAEA INSAG-4) became a commonly used concept which included an overall perspective on safety and an understanding of the interaction between man, technology and organizational matters (MTO). As a result of this understanding, the MTO concept was introduced at the Forsmark nuclear power plant already in 1988 and is today a conceptual way of thinking which is well integrated in the line organization. One of the purposes of this paper is to present some of the work that has been done at Forsmark nuclear power plant under the heading of MTO, both in the past and more recently. (author) 4 figs., 2 tabs

  5. Indirect estimations and spatial variation in leaf area index of coniferous, deciduous and mixed forest stands in Forsmark and Laxemar

    International Nuclear Information System (INIS)

    Tagesson, Torbern

    2006-12-01

    Two sites in Sweden are investigated for a potential deep repository of the nuclear waste, the Laxemar investigation area (57 deg 5 min N, 16 deg 7 min E) and the Forsmark investigation area (60 deg 4 min N, 18 deg 2 min E). In the characterisation of these sites, development of site descriptive models is an important part. Leaves are the main surface were an exchange of matter and energy between the atmosphere and the biosphere takes place, and leaf area index (LAI) of the vegetation cover is an important variable correlated to a number of ecophysiological parameters and hereby an important parameter in ecosystem models. In the investigation areas, LAI of boreal and temperate ecosystems were therefore estimated indirectly through optical measurements using the LAI-2000 (LI-COR, Cambridge UK) and TRAC (Tracing Radiation and Architecture of Canopies). On average, measured maximum LAI was 3.40 in Laxemar and 3.43 in Forsmark; minimum LAI was 1.65 in Laxemar and 1.97 in Forsmark. Forest inventory data showed that LAI is positively correlated with basal area, stand height, stand volume and breast height tree diameter. For the coniferous stands, there was also a linearly negative relationship with age. In the Laxemar investigation area, there were no significant relationships for LAI with a satellite derived kNN (kNearest Neighbor) data set with stand height, stand volume and stand age. The kNN data set can therefore not be used to extrapolate measured LAI over the Laxemar investigation area. There were significant relationships between LAI and the normalized difference vegetation index (NDVI) for coniferous, deciduous and mixed forest stands in the Laxemar investigation area. A NDVI image could be used to extrapolate LAI over the entire investigation area. For the Forsmark investigation area, effective LAI for all stands were correlated to NDVI and this relationship could then be used for extrapolation. The effective LAI image was afterwards corrected for average

  6. Indirect estimations and spatial variation in leaf area index of coniferous, deciduous and mixed forest stands in Forsmark and Laxemar

    Energy Technology Data Exchange (ETDEWEB)

    Tagesson, Torbern [Dept. of Physical Geography and Ecosystem Analysis, Lund Univ., Lund (Sweden)

    2006-12-15

    Two sites in Sweden are investigated for a potential deep repository of the nuclear waste, the Laxemar investigation area (57 deg 5 min N, 16 deg 7 min E) and the Forsmark investigation area (60 deg 4 min N, 18 deg 2 min E). In the characterisation of these sites, development of site descriptive models is an important part. Leaves are the main surface were an exchange of matter and energy between the atmosphere and the biosphere takes place, and leaf area index (LAI) of the vegetation cover is an important variable correlated to a number of ecophysiological parameters and hereby an important parameter in ecosystem models. In the investigation areas, LAI of boreal and temperate ecosystems were therefore estimated indirectly through optical measurements using the LAI-2000 (LI-COR, Cambridge UK) and TRAC (Tracing Radiation and Architecture of Canopies). On average, measured maximum LAI was 3.40 in Laxemar and 3.43 in Forsmark; minimum LAI was 1.65 in Laxemar and 1.97 in Forsmark. Forest inventory data showed that LAI is positively correlated with basal area, stand height, stand volume and breast height tree diameter. For the coniferous stands, there was also a linearly negative relationship with age. In the Laxemar investigation area, there were no significant relationships for LAI with a satellite derived kNN (kNearest Neighbor) data set with stand height, stand volume and stand age. The kNN data set can therefore not be used to extrapolate measured LAI over the Laxemar investigation area. There were significant relationships between LAI and the normalized difference vegetation index (NDVI) for coniferous, deciduous and mixed forest stands in the Laxemar investigation area. A NDVI image could be used to extrapolate LAI over the entire investigation area. For the Forsmark investigation area, effective LAI for all stands were correlated to NDVI and this relationship could then be used for extrapolation. The effective LAI image was afterwards corrected for average

  7. Recharge and discharge of near-surface groundwater in Forsmark. Comparison of classification methods

    Energy Technology Data Exchange (ETDEWEB)

    Werner, Kent [Golder Associates AB, Uppsala (Sweden); Johansson, Per-Olof [Artesia Grundvattenkonsult AB, Taeby (Sweden); Brydsten, Lars [Umeaa University, Dept. of Ecology and Environmental Science (Sweden); Bosson, Emma; Berglund, Sten [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

    2007-03-15

    This report presents and compares data and models for identification of near-surface groundwater recharge and discharge (RD) areas in Forsmark. The general principles of groundwater recharge and discharge are demonstrated and applied to interpret hydrological and hydrogeological observations made in the Forsmark area. 'Continuous' RD classification methods considered in the study include topographical modelling, map overlays, and hydrological-hydrogeological flow modelling. 'Discrete' (point) methods include field-based and hydrochemistry-based RD classifications of groundwater monitoring well locations. The topographical RD modelling uses the digital elevation model as the only input. The map overlays use background maps of Quaternary deposits, soils, and ground- and field layers of the vegetation/land use map. Further, the hydrological-hydrogeological modelling is performed using the MIKE SHE-MIKE 11 software packages, taking into account e.g. topography, meteorology, hydrogeology, and geometry of watercourses and lakes. The best between-model agreement is found for the topography-based model and the MIKE SHE-MIKE 11 model. The agreement between the topographical model and the map overlays is less good. The agreement between the map overlays on the one hand, and the MIKE SHE and field-based RD classifications on the other, is thought to be less good, as inferred from the comparison made with the topography-based model. However, much improvement of the map overlays can likely be obtained, e.g. by using 'weights' and calibration (such exercises were outside the scope of the present study). For field-classified 'recharge wells', there is a good agreement to the hydrochemistry-based (Piper plot) well classification, but less good for the field-classified 'discharge wells'. In addition, the concentration of the age-dating parameter tritium shows low variability among recharge wells, but a large spread among discharge

  8. Study of the possibility of localising a channel instability in Forsmark-1

    International Nuclear Information System (INIS)

    Karlsson, J.K-H.; Pazsit, I.

    1998-01-01

    A special type of instability occurred in the Swedish BWR Forsmark 1 in 1996. In contrast to the better known global or regional instabilities, the decay ratio appeared to be very high in one half of the core and quite low in the other half. A more detailed analysis showed that the most likely reason for the observed behaviour is a local perturbation of thermohydraulic character induced by the incorrect positioning of a fuel assembly. In such a case it is of importance to determine the position of the unseated assembly already during operation so that it can be easily found during reloading. The subject of this paper is to report on development and application of a method by which the position of such a local perturbation can be determined. The method can be separated into two parts that support and complement each other. First a visualisation technique was elaborated which displays the space-time behaviour of the neutron flux oscillations in the core. This visualisation expedites a very good qualitative comprehension of the situation and can be useful for the operators. It also gives a basis for the application of the localisation algorithm. Second, a quantitative localisation method, based on reactor physical models of the perturbation and of the transfer function between the perturbation and the flux oscillations, was elaborated. This latter takes noise spectra from selected detectors as input and yields the perturbation position as output. The strength of the method lies in its potentially high spatial resolution, which is smaller than the typical distance between two adjacent LPRM detectors. The method was tested on simulated data, and then applied to the Forsmark measurements. The location of the disturbance, found by the algorithm, is in accordance with independent judgements for the case, and close to a position where an unseated assembly was found during refuelling. The purpose of this study was to develop and test the localisation method. To apply the

  9. Quarterly report of the Swedish Nuclear Power Inspectorate. 4th quarter 1984

    International Nuclear Information System (INIS)

    1985-01-01

    During the fourth quarter of 1984 ten power reactors were in operation in Sweden. Two new reactors, Oskarshamn 3 and Forsmark 3, got loading authorization and started the test operation. No serious fault has occurred during the period. (K.A.E.)

  10. Regional hydrogeological simulations for Forsmark - numerical modelling using CONNECTFLOW. Preliminary site description Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Hartley, Lee; Cox, Ian; Hunter, Fiona; Jackson, Peter; Joyce, Steve; Swift, Ben [Serco Assurance, Risley (United Kingdom); Gylling, Bjoern; Marsic, Niko [Kemakta Konsult AB, Stockholm (Sweden)

    2005-05-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) carries out site investigations in two different candidate areas in Sweden with the objective of describing the in-situ conditions for a bedrock repository for spent nuclear fuel. The site characterisation work is divided into two phases, an initial site investigation phase (IPLU) and a complete site investigation phase (KPLU). The results of IPLU are used as a basis for deciding on a subsequent KPLU phase. On the basis of the KPLU investigations a decision is made as to whether detailed characterisation will be performed (including sinking of a shaft). An integrated component in the site characterisation work is the development of site descriptive models. These comprise basic models in three dimensions with an accompanying text description. Central in the modelling work is the geological model, which provides the geometrical context in terms of a model of deformation zones and the rock mass between the zones. Using the geological and geometrical description models as a basis, descriptive models for other geo-disciplines (hydrogeology, hydro-geochemistry, rock mechanics, thermal properties and transport properties) will be developed. Great care is taken to arrive at a general consistency in the description of the various models and assessment of uncertainty and possible needs of alternative models. Here, a numerical model is developed on a regional-scale (hundreds of square kilometres) to understand the zone of influence for groundwater flow that affects the Forsmark area. Transport calculations are then performed by particle tracking from a local-scale release area (a few square kilometres) to identify potential discharge areas for the site and using greater grid resolution. The main objective of this study is to support the development of a preliminary Site Description of the Forsmark area on a regional-scale based on the available data of 30 June 2004 and the previous Site Description. A more specific

  11. Hydrogeochemical evaluation of the Forsmark site, model version 1.1

    Energy Technology Data Exchange (ETDEWEB)

    Laaksoharju, Marcus (ed.) [GeoPoint AB, Sollentuna (Sweden); Gimeno, Maria; Auque, Luis; Gomez, Javier [Univ. of Zaragoza (Spain). Dept. of Earth Sciences; Smellie, John [Conterra AB, Uppsala (Sweden); Tullborg, Eva-Lena [Terralogica AB, Graabo (Sweden); Gurban, Ioana [3D-Terra, Montreal (Canada)

    2004-01-01

    Siting studies for SKB's programme of deep geological disposal of nuclear fuel waste currently involves the investigation of two locations, Forsmark and Simpevarp, on the eastern coast of Sweden to determine their geological, geochemical and hydrogeological characteristics. Present work completed has resulted in model version 1.1 which represents the first evaluation of the available Forsmark groundwater analytical data collected up to May 1, 2003 (i.e. the first 'data freeze'). The HAG group had access to a total of 456 water samples collected mostly from the surface and sub-surface environment (e.g. soil pipes in the overburden, streams and lakes); only a few samples were collected from drilled boreholes. The deepest samples reflected depths down to 200 m. Furthermore, most of the waters sampled (74%) lacked crucial analytical information that restricted the evaluation. Consequently, model version 1.1 focussed on the processes taking place in the uppermost part of the bedrock rather than at repository levels. The complex groundwater evolution and patterns at Forsmark are a result of many factors such as: a) the flat topography and closeness to the Baltic Sea resulting in relative small hydrogeological driving forces which can preserve old water types from being flushed out, b) the changes in hydrogeology related to glaciation/deglaciation and land uplift, c) repeated marine/lake water regressions/transgressions, and d) organic or inorganic alteration of the groundwater caused by microbial processes or water/rock interactions. The sampled groundwaters reflect to various degrees modern or ancient water/rock interactions and mixing processes. Based on the general geochemical character and the apparent age two major water types occur in Forsmark: fresh-meteoric waters with a bicarbonate imprint and low residence times (tritium values above detection limit), and brackish-marine waters with Cl contents up to 6,000 mg/L and longer residence times (tritium

  12. Present status and an appreciation of the consequences for recreation and outdoor leisure activities from siting a nuclear waste repository at Forsmark

    International Nuclear Information System (INIS)

    Ottosson, Pia

    2007-07-01

    This report describes how the area around Forsmark is used with respect to recreation and outdoor life. It also describes the impact of the final repository on recreation and outdoor life if it is located in Forsmark. The studied area is situated in the parish of Forsmark in the municipality of Oesthammar. Forsmark nuclear power plant and the final repository for radioactive operational waste, SFR, are situated within the area and there are both houses and holiday houses. The area is used for leisure pursuit by inhabitants and employees at FKA and SKB, but also by a number of different associations and by tourists. Statistical data shows that the parish of Forsmark is sparsely populated. The area was previously dominated by one big landowner and the land surrounding the nuclear power plant was inaccessible to the general public during that period. The outdoor life is therefore less widespread here than along other parts of the east coast. The value of the area does not lie in paths and trails, bike tracks and bathing places, but in the unspoiled countryside, the wildlife and the bird life. Recreation such as hunting and fishing is very popular in the area. The construction of a final repository will increase traffic and hence increase noise and motion in the area. This will mainly impact the enjoyment value for the people spending time in the area. No other significant consequences are expected as the final repository will be mainly situated within the existing industrial complex and hence the character of the area should remain unchanged

  13. Modelling of Fracture Initiation, Propagation and Creep of a KBS-3V and KBS-3H Repository in Sparsely Fractured Rock with Application to the Design at Forsmark Candidate Site

    International Nuclear Information System (INIS)

    Backers, Tobias; Stephansson, Ove

    2008-01-01

    The stability issues of deposition holes of a repository layout according to the KBS-3 concept in the sparsely fractured Forsmark granites are analysed with the emphasis on fracture mechanics. At the start of the project the rock mass is viewed as a continuum. In a second step explicit fracture networks are introduced and included in the numerical rock fracture models. The software Fracod2D was used for the rock fracture mechanics analysis. Assuming deposition holes located in a continuous, homogeneous elastic rock mass and The presented stress state of the rock mass the following results were obtained: For single KBS-3H deposition holes oriented in the direction of the minimum horizontal stress, Sh, bore hole breakouts are introduced for all depth levels. For KBS-3H holes which are oriented in direction of SH, no significant fracturing can be expected. In case of vertical deposition holes according to KBS-3V an increased risk of fracturing at greater depth levels (> 500m) is evident. At shallow depth levels ( 5MPa gives a favourable situation about spalling for the KBS-3H and KBS-3V layouts. To prevent spalling, it is important to build up a swelling pressure soon after excavation, so that the enhanced stresses in the surrounding of the deposition ii holes are reduced. This has a positive impact on other excavation activities and also on time-dependent fracturing. After excavation and filling of the deposition holes with subsequent increase of swelling pressure, the temperature will increase in the vicinity of the excavation. For the range of swelling pressures predicted for the KBS-3 concept, i.e. 5.5MPa to 7.2MPa, no significant fracturing for the KBS-3H concept with the axis parallel SH at depths below about 600m was discovered. The results from other layouts bare the risk of partly significant fracturing. About 60ka from closing the repository an ice cover of approximately 3km is expected over Forsmark. This dead load increases the in-situ stresses and

  14. Water activities in Forsmark (Part II). The final disposal facility for spent fuel: water activities above ground; Vattenverksamhet i Forsmark (del II). Slutfoervarsanlaeggningen foer anvaent kaernbraensle: Vattenverksamheter ovan mark

    Energy Technology Data Exchange (ETDEWEB)

    Werner, Kent [EmpTec (Sweden); Hamren, Ulrika; Collinder, Per [Ekologigruppen AB (Sweden); Ridderstolpe, Peter [WRS Uppsala AB (Sweden)

    2010-09-15

    The construction of the repository for spent nuclear fuel in Forsmark is associated with a number of measures above ground that constitute water operations according to Chapter 11 in the Swedish Environmental Code. This report, which is an appendix to the Environmental Impact Assessment, describes these water operations, their effects and consequences, and planned measures

  15. Inventory of mammals at Forsmark and Haallnaes

    International Nuclear Information System (INIS)

    Truve, Johan

    2012-08-01

    A selection of terrestrial mammals was surveyed in the SKB site investigation areas near Forsmark and Haallnaes between January and April 2012. The methods that were used include snow tracking along line transects, snow tracking along water, aerial survey and fecal pellet counts. The same species were found in 2012 as in previous surveys performed in 2002, 2003 and 2007. Some species show a large variation in density between years and it is difficult to draw any conclusions about their long term development. Several carnivores, i.e. lynx, fox and otter show a positive growth rate in both areas. The wild boar population is also growing whilst moose density remains fairly stable and roe deer are becoming less numerous

  16. Numerical modelling of solute transport at Forsmark with MIKE SHE. Site descriptive modelling SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Gustafsson, Lars-Goeran; Sassner, Mona (DHI Sverige AB, Stockholm (Sweden)); Bosson, Emma (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden))

    2008-12-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is performing site investigations at two different locations in Sweden, referred to as the Forsmark and Laxemar areas, with the objective of siting a final repository for high-level radioactive waste. Data from the site investigations are used in a variety of modelling activities. This report presents model development and results of numerical transport modelling based on the numerical flow modelling of surface water and near-surface groundwater at the Forsmark site. The numerical modelling was performed using the modelling tool MIKE SHE and is based on the site data and conceptual model of the Forsmark areas. This report presents solute transport applications based on both particle tracking simulations and advection-dispersion calculations. The MIKE SHE model is the basis for the transport modelling presented in this report. Simulation cases relevant for the transport from a deep geological repository have been studied, but also the pattern of near surface recharge and discharge areas. When the main part of the modelling work presented in this report was carried out, the flow modelling of the Forsmark site was not finalised. Thus, the focus of this work is to describe the sensitivity to different transport parameters, and not to point out specific areas as discharge areas from a future repository (this is to be done later, within the framework of the safety assessment). In the last chapter, however, results based on simulations with the re-calibrated MIKE SHE flow model are presented. The results from the MIKE SHE water movement calculations were used by cycling the calculated transient flow field for a selected one-year period as many times as needed to achieve the desired simulation period. The solute source was located either in the bedrock or on top of the model. In total, 15 different transport simulation cases were studied. Five of the simulations were particle tracking simulations, whereas the rest

  17. Decommissioning study of Forsmark NPP

    International Nuclear Information System (INIS)

    Anunti, Aake; Larsson, Helena; Edelborg, Mathias

    2013-06-01

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding

  18. Decommissioning study of Forsmark NPP

    Energy Technology Data Exchange (ETDEWEB)

    Anunti, Aake; Larsson, Helena; Edelborg, Mathias [Westinghouse Electric Sweden AB, Vaesteraas (Sweden)

    2013-06-15

    By Swedish law it is the obligation of the nuclear power utilities to satisfactorily demonstrate how a nuclear power plant can be safely decommissioned and dismantled when it is no longer in service as well as calculate the estimated cost of decommissioning of the nuclear power plant. Svensk Kaernbraenslehantering AB (SKB) has been commissioned by the Swedish nuclear power utilities to meet the requirements of current legislation by studying and reporting on suitable technologies and by estimating the costs of decommissioning and dismantling of the Swedish nuclear power plants. The present report is an overview, containing the necessary information to meet the above needs, for the Forsmark NPP. Information is given for the plant about the inventory of materials and radioactivity at the time for final shutdown. A feasible technique for dismantling is presented and the waste management is described and the resulting waste quantities are estimated. Finally a schedule for the decommissioning phase is given and the costs associated are estimated as a basis for funding.

  19. Final repository for spent nuclear fuel. Underground design Forsmark, Layout D1

    International Nuclear Information System (INIS)

    Brantberger, Martin; Zetterqvist, Anders; Arnbjerg-Nielsen, Torben; Olsson, Tommy; Outters, Nils; Syrjaenen, Pauli

    2006-04-01

    This report comprises the design step D1 related to the underground design for a deep repository located at the Forsmark site. The design is based on the Site Descriptive Model Forsmark v1.2. All studies have been focussed at an area southeast of the Forsmark nuclear plant, which has been considered to be the most promising area for hosting the repository. SKB has developed guidelines for the design of the repository, which further describes the methodology applied for the studies. From these guidelines the following basic objectives for the design step D1 are summarized: to determine whether the final repository can be accommodated within the studied site; to identify site-specific facility critical issues; to test and evaluate the design methodology; to provide feedback to: the design organisation regarding additional studies that needs to be done; the site investigation and modelling organization regarding further investigations required; and the safety assessment team. The possible locations for a tentative deep repository are analysed in Chapter 3 of the report. The most promising area for the repository (denoted 'priority site') has been defined by SKB to be located southeast of the Forsmark nuclear plant and northwest of the gently dipping deformation zone ZFMNE00A2. Regarding the repository depth, present knowledge acquired from the site investigations indicates that it is possible to locate the repository at all stipulated depths according to SKB, that is between 400 m and 700 m depth. The preliminary assessment made in Chapter 3 clearly demonstrates that the repository can be accommodated within the 'priority site'. The potential to accommodate the repository is essentially the same for both 400 m and 500 m depths. The design of the deposition areas is reported in Chapter 4, which includes the design of layout features for all tunnels and deposition holes, orientation of tunnels, calculation of anticipated loss of deposition holes due to the applied

  20. Final repository for spent nuclear fuel. Underground design Forsmark, Layout D1

    Energy Technology Data Exchange (ETDEWEB)

    Brantberger, Martin; Zetterqvist, Anders [Ramboell Sweden AB, Stockholm (Sweden); Arnbjerg-Nielsen, Torben [Ramboell Denmark A/S, Virum (Denmark); Olsson, Tommy [IandT Olsson AB, Uppsala (Sweden); Outters, Nils [Golder Associates AB, Uppsala (Sweden); Syrjaenen, Pauli [Gridpoint Oy, Helsinki (Sweden)

    2006-04-15

    This report comprises the design step D1 related to the underground design for a deep repository located at the Forsmark site. The design is based on the Site Descriptive Model Forsmark v1.2. All studies have been focussed at an area southeast of the Forsmark nuclear plant, which has been considered to be the most promising area for hosting the repository. SKB has developed guidelines for the design of the repository, which further describes the methodology applied for the studies. From these guidelines the following basic objectives for the design step D1 are summarized: to determine whether the final repository can be accommodated within the studied site; to identify site-specific facility critical issues; to test and evaluate the design methodology; to provide feedback to: the design organisation regarding additional studies that needs to be done; the site investigation and modelling organization regarding further investigations required; and the safety assessment team. The possible locations for a tentative deep repository are analysed in Chapter 3 of the report. The most promising area for the repository (denoted 'priority site') has been defined by SKB to be located southeast of the Forsmark nuclear plant and northwest of the gently dipping deformation zone ZFMNE00A2. Regarding the repository depth, present knowledge acquired from the site investigations indicates that it is possible to locate the repository at all stipulated depths according to SKB, that is between 400 m and 700 m depth. The preliminary assessment made in Chapter 3 clearly demonstrates that the repository can be accommodated within the 'priority site'. The potential to accommodate the repository is essentially the same for both 400 m and 500 m depths. The design of the deposition areas is reported in Chapter 4, which includes the design of layout features for all tunnels and deposition holes, orientation of tunnels, calculation of anticipated loss of deposition holes due

  1. Case-study, session 2. Nuclear facilities and local information. Speech by Lennart Franzon (together with L.G. Wahlberg, OKG)

    International Nuclear Information System (INIS)

    Franzon, Lennart; Wahlberg, L.G.

    1989-01-01

    Forsmark NPP is situated 100 miles north of Stockholm on the east coast. The plant has 3 units of about 1 000 MWe each. The annual net production is about 16% of the Swedish electric power consumption. Forsmark was the only Swedish nuclear power plant not yet operating at all at the time of te nuclear power referendum in 1980. The neighbourhood of Forsmark means a radius of about 50 miles from the station, which means about 100 000 inhabitants, including a lot of summer house owners. The first building in use in Forsmark 1973 - seven years before operation start - was a visitors center. Since then 400 000 people have visited Forsmark. The visitors programmes are the most important activities towards the Swedes. To let visitors into a reactor hall balcony, a few meters above the high level waste close to the reactor, is a good way to explain the nuclear power. Many visitors also feel privileged when they together with their friends are able to investigate the radiation protection monitors, where the Chernobyl disaster was detected for the first time outside the Soviet Union in April 1986. Since 1983 both positive and negative aspect of reactor operation are advertised. Data related to electricity supply availability, employment, radiation doses of the employees, radioactive release into air and sea, operational problems, events etc. are all published by the operator in the local newspapers quarterly. The experience is that negative publicity, based on authority reports has decreased. It was found that the most important for the owner/operator is to have the initiative all the time. Similar to Oskarshamn Power Group Forsmark edits a magazine - Forsmarks Tidning - twice a year since 1980, the year of operation start. The magazine is distributed to about 65.000 homes, to authorities, politicians, employees, private companies, etc. About 50% of the neighbours read the magazine. This is considered as success. Through the years of operation of Forsmark it was founds that

  2. Confidence assessment. Site descriptive modelling SDM-Site Forsmark

    International Nuclear Information System (INIS)

    2008-09-01

    The objective of this report is to assess the confidence that can be placed in the Forsmark site descriptive model, based on the information available at the conclusion of the surface-based investigations (SDM-Site Forsmark). In this exploration, an overriding question is whether remaining uncertainties are significant for repository engineering design or long-term safety assessment and could successfully be further reduced by more surface based investigations or more usefully by explorations underground made during construction of the repository. The confidence in the Forsmark site descriptive model, based on the data available at the conclusion of the surface-based site investigations, have been assessed by exploring: Confidence in the site characterisation data base; Key remaining issues and their handling; Handling of alternative models; Consistency between disciplines; and, Main reasons for confidence and lack of confidence in the model. It is generally found that the key aspects of importance for safety assessment and repository engineering of the Forsmark site descriptive model are associated with a high degree of confidence. Because of the robust geological model that describes the site, the overall confidence in Forsmark site descriptive model is judged to be high. While some aspects have lower confidence this lack of confidence is handled by providing wider uncertainty ranges, bounding estimates and/or alternative models. Most, but not all, of the low confidence aspects have little impact on repository engineering design or for long-term safety. Poor precision in the measured data are judged to have limited impact on uncertainties on the site descriptive model, with the exceptions of inaccuracy in determining the position of some boreholes at depth in 3-D space, as well as the poor precision of the orientation of BIPS images in some boreholes, and the poor precision of stress data determined by overcoring at the locations where the pre

  3. Hydrochemistry in surface water and shallow groundwater. Site descriptive modelling SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Troejbom, Mats (Mopelikan, Norrtaelje (SE)); Soederbaeck, Bjoern (Swedish Nuclear Fuel and Waste Management Co., Stockholm (SE)); Johansson, Per-Olof (Artesia Grundvattenkonsult AB, Taeby (SE))

    2007-10-15

    With a mathematical/statistical approach, a large number of visualisations and models reflect the hydrochemistry in the Forsmark area, with the intention to give an understanding of important processes and factors that affect the hydrochemistry in the surface systems. In order to widen the perspective, all data from the Forsmark 2.2 stage including observations from different levels of the bedrock, as well as hydrological measurements and characterisations of the Quaternary deposits, have been included in the analyses. The purpose of this report is to give a general understanding of the site and to explain observed overall patterns as well as anomalies, and, ultimately, to present a conceptual model that explains the present hydrochemistry in the surface system in the light of the past. The report may also function as a basis for further evaluation and testing of scenarios, and may be regarded as an intermediate step between raw data compilations from the vast SICADA database and specialised expert models. The flat topography and the recent withdrawal of the Baltic Sea due to the isostatic land-uplift are two important factors determining the hydrochemistry in the Forsmark area. Marine remnants in the Quaternary deposits, as well as modern sea water intrusions, are therefore strongly influencing the hydrochemistry, especially in areas at low altitude close to the coast. Large-scale marine gradients in the surface system are consistent with the conceptual model that describes the hydrochemical evolution in a paleo-hydrologic perspective. The Forsmark area is covered by glacial remnants, mostly in the form of a till layer, which was deposited during the Weichselian glaciation and deglaciation. When the ice cover retreated about 11,000 years ago, these deposits were exposed on the sea floor. This till layer is characterized by a rich content of calcite, originating from the sedimentary bedrock of Gaevlebukten about 100 km north of Forsmark. The dissolution of this

  4. Hydrochemistry in surface water and shallow groundwater. Site descriptive modelling SDM-Site Forsmark

    International Nuclear Information System (INIS)

    Troejbom, Mats; Soederbaeck, Bjoern; Johansson, Per-Olof

    2007-10-01

    With a mathematical/statistical approach, a large number of visualisations and models reflect the hydrochemistry in the Forsmark area, with the intention to give an understanding of important processes and factors that affect the hydrochemistry in the surface systems. In order to widen the perspective, all data from the Forsmark 2.2 stage including observations from different levels of the bedrock, as well as hydrological measurements and characterisations of the Quaternary deposits, have been included in the analyses. The purpose of this report is to give a general understanding of the site and to explain observed overall patterns as well as anomalies, and, ultimately, to present a conceptual model that explains the present hydrochemistry in the surface system in the light of the past. The report may also function as a basis for further evaluation and testing of scenarios, and may be regarded as an intermediate step between raw data compilations from the vast SICADA database and specialised expert models. The flat topography and the recent withdrawal of the Baltic Sea due to the isostatic land-uplift are two important factors determining the hydrochemistry in the Forsmark area. Marine remnants in the Quaternary deposits, as well as modern sea water intrusions, are therefore strongly influencing the hydrochemistry, especially in areas at low altitude close to the coast. Large-scale marine gradients in the surface system are consistent with the conceptual model that describes the hydrochemical evolution in a paleo-hydrologic perspective. The Forsmark area is covered by glacial remnants, mostly in the form of a till layer, which was deposited during the Weichselian glaciation and deglaciation. When the ice cover retreated about 11,000 years ago, these deposits were exposed on the sea floor. This till layer is characterized by a rich content of calcite, originating from the sedimentary bedrock of Gaevlebukten about 100 km north of Forsmark. The dissolution of this

  5. Expected extreme sea levels at Forsmark and Laxemar-Simpevarp up until year 2100

    International Nuclear Information System (INIS)

    Brydsten, Lars; Engqvist, Anders; Naeslund, Jens-Ove; Lindborg, Tobias

    2009-01-01

    Literature data on factors that can affect the highest expected shoreline during the operational lifetime of a final repository up until ca 2100 AD have been compiled for Forsmark and Laxemar/Simpevarp. The study takes into consideration eustasy (global sea level), isostasy (isostatic rebound) and their trends, as well as regional (North Sea) and local (Baltic Sea) annual extremes of today's sea levels and those in year 2100. The most uncertain factor of these is the future global sea level change. For this factor, three possible scenarios have been included from the literature, forming an rough uncertainty interval around a case with an 'intermediate' global sea level. To this end, the study thus makes use of information on global sea level change that has been published since the IPCC's (UN Intergovernmental Panel on Climate Change) most recent report (2007). The local cumulative impact on the shoreline of the eustatic and isostatic components for both the Forsmark and Laxemar/Simpevarp coastal areas is that the maximum sea level occurs at the end of the investigation period, by year 2100. The interaction of these estimates is discussed in terms of coastal oceanographic aspects and estimated return periods for local extreme sea level-impacting events, including estimated storm surge. Maximum sea levels in year 2100 based on the sea level rise estimates by Rahmstorf are + 254 cm for Forsmark and + 297 cm for Laxemar/Simpevarp, both of these levels with an uncertainty interval of about ± 70 cm. The numbers apply for the worst possible case in regard to future sea level rise, and for occasions of short duration during heavy storms. In this context it is important to note that the data on which these estimates are based are the subject of intense research, and that revisions are therefore to be expected

  6. Expected extreme sea levels at Forsmark and Laxemar-Simpevarp up until year 2100

    Energy Technology Data Exchange (ETDEWEB)

    Brydsten, Lars (Umeaa Univ., Umeaa (Sweden)); Engqvist, Anders (Royal Institute of Technology, Stockholm (Sweden)); Naeslund, Jens-Ove; Lindborg, Tobias (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden))

    2009-01-15

    Literature data on factors that can affect the highest expected shoreline during the operational lifetime of a final repository up until ca 2100 AD have been compiled for Forsmark and Laxemar/Simpevarp. The study takes into consideration eustasy (global sea level), isostasy (isostatic rebound) and their trends, as well as regional (North Sea) and local (Baltic Sea) annual extremes of today's sea levels and those in year 2100. The most uncertain factor of these is the future global sea level change. For this factor, three possible scenarios have been included from the literature, forming an rough uncertainty interval around a case with an 'intermediate' global sea level. To this end, the study thus makes use of information on global sea level change that has been published since the IPCC's (UN Intergovernmental Panel on Climate Change) most recent report (2007). The local cumulative impact on the shoreline of the eustatic and isostatic components for both the Forsmark and Laxemar/Simpevarp coastal areas is that the maximum sea level occurs at the end of the investigation period, by year 2100. The interaction of these estimates is discussed in terms of coastal oceanographic aspects and estimated return periods for local extreme sea level-impacting events, including estimated storm surge. Maximum sea levels in year 2100 based on the sea level rise estimates by Rahmstorf are + 254 cm for Forsmark and + 297 cm for Laxemar/Simpevarp, both of these levels with an uncertainty interval of about +- 70 cm. The numbers apply for the worst possible case in regard to future sea level rise, and for occasions of short duration during heavy storms. In this context it is important to note that the data on which these estimates are based are the subject of intense research, and that revisions are therefore to be expected

  7. Modelling of present and future hydrology and solute transport at Forsmark. SR-Site Biosphere

    Energy Technology Data Exchange (ETDEWEB)

    Bosson, Emma (Swedish Nuclear Fuel and Waste Management Co., Stocholm (Sweden)); Sassner, Mona; Sabel, Ulrika; Gustafsson, Lars-Goeran (DHI Sverige AB (Sweden))

    2010-10-15

    Radioactive waste from nuclear power plants in Sweden is managed by the Swedish Nuclear Fuel and Waste Management Co, SKB. SKB has performed site investigations at two different locations in Sweden, referred to as the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a final repository for high-level radioactive waste. In 2009 a decision was made to focus on the Forsmark site. This decision was based on a large amount of empirical evidence suggesting Forsmark to be more suitable for a geological repository /SKB 2010b/. This report presents model results of numerical flow and transport modelling of surface water and near-surface groundwater at the Forsmark site for present and future conditions. Both temperate and periglacial climates have been simulated. Also different locations of the shoreline have been applied to the model, as well as different models of vegetation and Quaternary deposits. The modelling was performed using the modelling tool MIKE SHE and was based on the SDM-Site Forsmark MIKE SHE model (presented by Bosson et al. in SKB report R-08-09). The present work is a part of the biosphere modelling performed for the SR-Site safety assessment. The Forsmark area has a flat, small-scale topography. The study area is almost entirely below 20 m.a.s.l. (metres above sea level). There is a strong correlation between the topography of the ground surface and the ground water level in the Quaternary deposits (QD); thus, the surface water divides and the groundwater divides for the QD can be assumed to coincide. No major water courses flow through the catchment. Small brooks, which often dry out in the summer, connect the different sub-catchments with each other. The main lakes in the area, Lake Bolundsfjaerden, Lake Fiskarfjaerden, Lake Gaellsbotraesket and Lake Eckarfjaerden, all have sizes of less than one km2. The lakes are in general shallow. Approximately 70% of the catchment areas are covered by forest. Agricultural land is only present in

  8. Modelling of present and future hydrology and solute transport at Forsmark. SR-Site Biosphere

    International Nuclear Information System (INIS)

    Bosson, Emma; Sassner, Mona; Sabel, Ulrika; Gustafsson, Lars-Goeran

    2010-10-01

    Radioactive waste from nuclear power plants in Sweden is managed by the Swedish Nuclear Fuel and Waste Management Co, SKB. SKB has performed site investigations at two different locations in Sweden, referred to as the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a final repository for high-level radioactive waste. In 2009 a decision was made to focus on the Forsmark site. This decision was based on a large amount of empirical evidence suggesting Forsmark to be more suitable for a geological repository /SKB 2010b/. This report presents model results of numerical flow and transport modelling of surface water and near-surface groundwater at the Forsmark site for present and future conditions. Both temperate and periglacial climates have been simulated. Also different locations of the shoreline have been applied to the model, as well as different models of vegetation and Quaternary deposits. The modelling was performed using the modelling tool MIKE SHE and was based on the SDM-Site Forsmark MIKE SHE model (presented by Bosson et al. in SKB report R-08-09). The present work is a part of the biosphere modelling performed for the SR-Site safety assessment. The Forsmark area has a flat, small-scale topography. The study area is almost entirely below 20 m.a.s.l. (metres above sea level). There is a strong correlation between the topography of the ground surface and the ground water level in the Quaternary deposits (QD); thus, the surface water divides and the groundwater divides for the QD can be assumed to coincide. No major water courses flow through the catchment. Small brooks, which often dry out in the summer, connect the different sub-catchments with each other. The main lakes in the area, Lake Bolundsfjaerden, Lake Fiskarfjaerden, Lake Gaellsbotraesket and Lake Eckarfjaerden, all have sizes of less than one km2. The lakes are in general shallow. Approximately 70% of the catchment areas are covered by forest. Agricultural land is only present in

  9. Quantitative assessment of radionuclide retention in the near-surface system at Forsmark. Development of a reactive transport model using Forsmark 1.2 data

    International Nuclear Information System (INIS)

    Grandia, Fidel; Sena, Clara; Arcos, David; Molinero, Jorge; Duro, Lara; Bruno, Jordi

    2007-12-01

    entering the system from the deep source is effectively retained (in this case precipitated into solid phases) in the vicinity of the source. Finally, model results indicate that strontium is retained by two different geochemical processes: (1) cation exchange within illite interlayers and (2) precipitation into a Sr x Ca 1-x CO 3 solid solution. Even though there are two distinct retention mechanisms affecting strontium, the clay system exhibits the lowest efficiency for retention of this radionuclide compared to the other two simulated radionuclides. Cation exchange is the dominating retention process in both the clay and the till system, but the contribution of carbonate solid solution is not negligible; its relative importance depends on the initial pool of carbonate minerals in the system. The overall efficiency of both systems to retain strontium shows a clear decrease with time. However, the efficiency for strontium retention of both systems is still higher than 60% after simulation times of hundreds of years. From this study it can be concluded that the near-surface system at Forsmark constitutes a geochemically reactive barrier able to retain radionuclides by several key processes. Such retention mechanisms produce an effective overall retardation of the migration of the studied radionuclides

  10. JENDL-3.3 thermal reactor benchmark test

    International Nuclear Information System (INIS)

    Akie, Hiroshi

    2001-01-01

    Integral tests of JENDL-3.2 nuclear data library have been carried out by Reactor Integral Test WG of Japanese Nuclear Data Committee. The most important problem in the thermal reactor benchmark testing was the overestimation of the multiplication factor of the U fueled cores. With several revisions of the data of 235 U and the other nuclides, JENDL-3.3 data library gives a good estimation of multiplication factors both for U and Pu fueled thermal reactors. (author)

  11. Organizational development at Forsmark NPP

    International Nuclear Information System (INIS)

    Metzen, H.

    2001-01-01

    Forsmark is a three unit BWR site with a total capacity of 3200 MW. Units 1 and two are identical and went into commercial operation in 1980 and 1981. Unit 3 is of a later design with an output of 1200 MW and has been operating since 1985. The average availability for the site has been over 90% for the last 10 years, and the total busbar cost has been competitive. A consistent management strategy has been used to achieve the good results. Several organizational modifications have been made during the years to adapt the organization to changing internal and external conditions. An overall goal regarding staffing has been to keep the number of employees at the same level as in 1985 when Unit 3 went into commercial operation. During the time period from 1975, when the operational organization was formed, until today, the focus for the organization has changed several times. During the commissioning period the focus was on training and establishing routines and procedures. During the first years of operation development of maintenance programs and taking over activities from the supplier dominated. Next area in focus was increasing availability and making the outages more efficient. Several minor modifications to the plant were made to support maintenance activities. More focus on cost reduction and increasing the production through technical modifications were next. After 15 years of operation the need for replacement of components to ensure reliable operation was evident. A program for major modifications was developed, aiming at 40 years lifetime. Deregulation of the Nordic Electricity Market now calls for further reductions in production costs. (author)

  12. Epilithic algal assemblages in the Forsmark Biotest basin

    Energy Technology Data Exchange (ETDEWEB)

    Snoeijs, P.

    1987-04-01

    The Forsmark Biotest Basin is an artificial offshore brackish lake, through which the cooling water is led from the Forsmark Nuclear Power Station on the Swedish east coast. The Biotest Basin differs from the Bothnian Sea surrounding it by a temperature elevation of up to 10 degrees C, no ice cover in winter, and an artificial, fast current. At 11 sites in- and outside the basin, benthic algal assemblages on stones in the hydrolittoral belt were sampled every third week during one year. Cover abundances were estimated for all algae occurring on the stones, but for diatoms only when they formed blooms. The results of the vegetation analyses are given. Diversity indices and dominance-diversity curves were computed for each site on the basis of pooled data for the cold season and for the rest of the year. The algae included both unicellular and multicellular forms. In total 88 taxa were distinguished in the species lists: 29 Cyanophyta, 7 Rhodophyta, 1 Chrysophyceae, 9 Fucophyceae, 17 Diatomophyceae and 25 Chlorophyta. In terms of percentage cover-abundance, blue-green and green algae increased with temperature, while red and brown algae and diatoms decreased with temperature in the interval between the minimum (0 degrees C) and the maximum (25.7 degrees C) water temperatures that were measured during the investigation period. Melosira spp. and Nitzschia filiformis proved to be the diatoms most favoured by the cooling water discharge. Lower diversity and greater dominance of one or a few species over the other was caused by thermal discharge at sites with fast-flowing water, but the opposite occurred at sites with quiescent water, mainly due to a greater number and higher abundances of blue-green algal species and thread-like green algae at the latter sites. This report also gives some notes on taxonomy of the encountered species.

  13. Preliminary site description Forsmark area - version 1.1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-03-01

    This report presents the interim version (model version 1.1) of the preliminary Site Descriptive Model for Forsmark. The basis for this interim version is quality-assured, geoscientific and ecological field data from Forsmark that were available in the SKB databases SICADA and GIS at April 30, 2003 as well as version 0 of the Site Descriptive Model. The new data acquired during the initial site investigation phase to the date of data freeze 1.1 constitute the basis for the updating of version 0 to version 1.1. These data originate from surface investigations on the candidate area with its regional environment and from drilling and investigations in boreholes. The surface-based data sets were rather extensive whereas the data sets from boreholes were limited to information from one 1,000 m deep cored borehole (KFM01A) and eight 150 to 200 m deep percussion-drilled boreholes in the Forsmark candidate area. Discipline specific models are developed for a selected regional and local model volume and these are then integrated into a site description. The current methodologies for developing the discipline specific models and the integration of these are documented in methodology reports or strategy reports. In the present work, the guidelines given in those reports were followed to the extent possible with the data and information available at the time for data freeze for model version 1.1. Compared with version 0 there are considerable additional features in the version 1.1, especially in the geological description and in the description of the near surface. The geological models of lithology and deformation zones are based on borehole information and much higher resolution surface data. The existence of highly fractured sub-horizontal zones has been verified and these are now part of the model of the deformation zones. A discrete fracture network (DFN) model has also been developed. The rock mechanics model is based on strength information from SFR and an empirical

  14. Chemistry data from surface ecosystems in Forsmark and Laxemar-Simpevarp. Site specific data used for estimation of CR and Kd values in SR-Site

    International Nuclear Information System (INIS)

    Troejbom, Mats; Norden, Sara

    2010-11-01

    This report is a background report for the biosphere analysis of the SR-Site Safety Assessment. This work aims to compile information from the Forsmark and Laxemar-Simpevarp sites in order to select and provide relevant site data for parameter sed in the Radionuclide Dose Model. This report contains an overview of all available chemistry data from the surface ecosystems at Forsmark and Laxemar-Simpevarp areas, comprising hydrochemistry of shallow groundwater, porewater, lake water, stream water and sea water as well as the chemical composition of the regolith and biota of the terrestrial, limnic and marine ecosystems. Detailed references to data reports are tabulated and all sampling points are shown in a large number of maps in Chapter 2. An explorative analysis in Chapter 3 is the basis for the final selection of site data described in Chapter 4

  15. Analysis with SCDAP/RELAP5 of reflooding of an overheated core in Forsmark 3 BWR after loss of electric power

    International Nuclear Information System (INIS)

    Nilsson, Lars.

    1993-01-01

    In foregoing SIK-2.2 project two severe accident sequences for Forsmark 3 comprising loss of electric power (Total Blackout, TB) without recovery actions (e.g. emergency cooling) were analysed with SCDAP/RELAP5. Code version MOD2.5/V3f was applied and a single core channel input model was used. Present analysis was done with the same initiating events as in SIK-2.2, but assuming recovery of auxiliary feed water and/or emergency core cooling systems to take place after heat-up of the core, in compliance with the plans of the SIK-2.3 project. A new test version of the SCDAP/RELAP5 code, version MOD3/V7af, was used here. The geometrical input model was extended from having one, into five parallel core zones, still with ten axial core sub volumes. Calculations were performed for three TB cases, one without cooling recovery, and two with injection of cold water at a rate of 45 kg/s, beginning when the maximum cladding temperature has reached 1522 K. The results show that a considerably more efficient cooling was obtained spraying the water to the top of the core, compared to the case where the cooling water was introduced into the downcomer, leading to bottom reflooding

  16. Numerical modelling of solute transport at Forsmark with MIKE SHE. Site descriptive modelling SDM-Site Forsmark

    International Nuclear Information System (INIS)

    Gustafsson, Lars-Goeran; Sassner, Mona; Bosson, Emma

    2008-12-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is performing site investigations at two different locations in Sweden, referred to as the Forsmark and Laxemar areas, with the objective of siting a final repository for high-level radioactive waste. Data from the site investigations are used in a variety of modelling activities. This report presents model development and results of numerical transport modelling based on the numerical flow modelling of surface water and near-surface groundwater at the Forsmark site. The numerical modelling was performed using the modelling tool MIKE SHE and is based on the site data and conceptual model of the Forsmark areas. This report presents solute transport applications based on both particle tracking simulations and advection-dispersion calculations. The MIKE SHE model is the basis for the transport modelling presented in this report. Simulation cases relevant for the transport from a deep geological repository have been studied, but also the pattern of near surface recharge and discharge areas. When the main part of the modelling work presented in this report was carried out, the flow modelling of the Forsmark site was not finalised. Thus, the focus of this work is to describe the sensitivity to different transport parameters, and not to point out specific areas as discharge areas from a future repository (this is to be done later, within the framework of the safety assessment). In the last chapter, however, results based on simulations with the re-calibrated MIKE SHE flow model are presented. The results from the MIKE SHE water movement calculations were used by cycling the calculated transient flow field for a selected one-year period as many times as needed to achieve the desired simulation period. The solute source was located either in the bedrock or on top of the model. In total, 15 different transport simulation cases were studied. Five of the simulations were particle tracking simulations, whereas the rest

  17. Fracture mineralogy of the Forsmark site. SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Sandstroem, Bjoern (Dept. of Earth Sciences, Univ. of Goeteborg (Sweden)); Tullborg, Eva-Lena (Terralogica AB, Graabo (Sweden)); Smellie, John (Conterra AB, Luleaa (Sweden)); MacKenzie, Angus B. (SUERC, Scottish Enterprise Technology Park, East Kilbride (United Kingdom)); Suksi, Juhani (Dept. of Chemistry, Univ. of Helsinki, Helsinki (Finland))

    2008-08-15

    Detailed investigations of the fracture mineralogy and altered wall rock have been carried out as part of the site characterisation programme between 2003 and 2007 at Forsmark. The results have been published in a number of P-reports and in contributions to scientific journals. This report summarises and evaluates the data obtained during the detailed fracture mineralogical studies. The report includes descriptions of the identified fracture minerals and their chemical composition. A sequence of fracture mineralisations has been distinguished and provides information of the low to moderate temperature (brittle) geological and hydrogeological evolution at the site. Special focus has been paid to the chemical and stable isotopic composition of calcite to obtain palaeohydrogeological information. Chemical analyses of bulk fracture filling material have been carried out to identify possible sinks for certain elements and also to reveal the presence of minor phases rich in certain elements which have not been possible to detect by X-ray diffraction (XRD). Statistical analysis of the mineralogy in fractures outside deformation zones (i.e. within fracture domains FFM01, FFM02, FFM03 and FFM06) have been carried out concerning variation of fracture mineral distribution at depth and in different fracture domains. Uranium contents and uranium-series isotopes have been analysed on fracture coating material from hydraulically conductive fractures. Such analyses are also available from the groundwaters and the results are combined in order to reveal recent (< 1 Ma) removal/deposition of uranium in the fracture system. The redox conditions in the fracture system have been evaluated based on mineralogical and chemical indicators as well as Moessbauer analyses

  18. Application of noise analysis for the study of core local instability at Forsmark 1

    International Nuclear Information System (INIS)

    Oguma, Ritsuo

    1997-10-01

    Core local instability was recently experienced at Forsmark 1 BWR. The event has been studied by applying noise analysis to data collected in January 1997 for the stability test. The result indicated that there was a region in the left corner of the core which was subject to instability due to neutronic and thermal-hydraulic coupling. The result of the noise analysis suggested two types of disturbance source, one in the vicinity of the detector string LPRM10 having resonant oscillation at 0.5 Hz and another relatively wide band noise in the neighbourhood of LPRM18. Three hypotheses have been examined as the possible cause, operational factor, abnormal fuel assembly, and wide band low frequency disturbance. Although the real cause has not been made clear from the noise analysis, it is likely that the operational factor played an important role as the cause. Further investigations are expected to be performed in the future. In order to detect the local instability it is important to have a stability monitor with a capability of monitoring a sufficient number of LPRMs so as to cover the whole core. This is important since local instability is a type of anomaly which should not occur during reactor operation

  19. Input and turnover of forest tree litter in the Forsmark and Oskarshamn areas

    Energy Technology Data Exchange (ETDEWEB)

    Mjoefors, Kristina; Johansson, Maj-Britt; Nilsson, Aake [Dept. of Forest Soi ls, Swedish Univ. of Agricultural Sciences (Sweden); Hyvoenen, Riitta [Dept. of Eco logy, Swedish Univ. of Agricultural Sciences (Sweden)

    2007-04-15

    The site investigations reported here were conducted to provide data for the comprehensive descriptive ecosystem model that is being constructed. This report provides estimates of annual inputs of aboveground litter from trees (dry mass and amounts of C and N), litter decomposition rates and changes in organic and inorganic components in litter during decomposition. The study in the Forsmark area comprised two Norway spruce (Picea abies (L.) Karst) stands (sites F1 and F3), and a mixed stand of Norway spruce and alder (Alnus glutinosa (L.) Gaertn.) (site F2). The study in the Oskarshamn area comprised one common oak stand (Quercus robur L.) (site O1), one Scots pine stand (Pinus silvestris L.) (site O2) and one Norway spruce stand (site O3). In the Forsmark area, the aboveground litterfall from trees was of similar magnitude at sites F1 and F2, but considerably lower at site F3. At the former sites the average annual litterfall amounted to 195 and 231 gdw/m{sup 2} respectively, whereas the latter site received only 136 gdw/m{sup 2}. There was also a large variation in annual litterfall between stands in the Oskarshamn area. The spruce stand at site O3 exhibited the highest litterfall (almost 400 gdw/m{sup 2}), followed by the oak stand at site O1 (with almost 300 gdw/m{sup 2}), whereas the pine stand at site O2 had the lowest (less than 150 gdw/m{sup 2}). The proportion of needles/leaves in the total litterfall varied between 65% and 75% for the stands. The amount of carbon (C) returned in aboveground litterfall amounted to between 60 and 110 gdw/m{sup 2}/yr at the forest sites within the Forsmark area. The corresponding range for the sites in the Oskarshamn area was 70 to 190 gdw/m{sup 2}/yr. At sites O1 and O2 in Oskarshamn, about 3.6 gdw/m{sup 2}/yr of nitrogen (N) were returned annually to the forest floor by the aboveground litterfall. This was over four times the N amount deposited in the Scots pine stand in the same area (about 0.8 gdw/m{sup 2}/yr). At the

  20. Input and turnover of forest tree litter in the Forsmark and Oskarshamn areas

    International Nuclear Information System (INIS)

    Mjoefors, Kristina; Johansson, Maj-Britt; Nilsson, Aake; Hyvoenen, Riitta

    2007-04-01

    The site investigations reported here were conducted to provide data for the comprehensive descriptive ecosystem model that is being constructed. This report provides estimates of annual inputs of aboveground litter from trees (dry mass and amounts of C and N), litter decomposition rates and changes in organic and inorganic components in litter during decomposition. The study in the Forsmark area comprised two Norway spruce (Picea abies (L.) Karst) stands (sites F1 and F3), and a mixed stand of Norway spruce and alder (Alnus glutinosa (L.) Gaertn.) (site F2). The study in the Oskarshamn area comprised one common oak stand (Quercus robur L.) (site O1), one Scots pine stand (Pinus silvestris L.) (site O2) and one Norway spruce stand (site O3). In the Forsmark area, the aboveground litterfall from trees was of similar magnitude at sites F1 and F2, but considerably lower at site F3. At the former sites the average annual litterfall amounted to 195 and 231 gdw/m 2 respectively, whereas the latter site received only 136 gdw/m 2 . There was also a large variation in annual litterfall between stands in the Oskarshamn area. The spruce stand at site O3 exhibited the highest litterfall (almost 400 gdw/m 2 ), followed by the oak stand at site O1 (with almost 300 gdw/m 2 ), whereas the pine stand at site O2 had the lowest (less than 150 gdw/m 2 ). The proportion of needles/leaves in the total litterfall varied between 65% and 75% for the stands. The amount of carbon (C) returned in aboveground litterfall amounted to between 60 and 110 gdw/m 2 /yr at the forest sites within the Forsmark area. The corresponding range for the sites in the Oskarshamn area was 70 to 190 gdw/m 2 /yr. At sites O1 and O2 in Oskarshamn, about 3.6 gdw/m 2 /yr of nitrogen (N) were returned annually to the forest floor by the aboveground litterfall. This was over four times the N amount deposited in the Scots pine stand in the same area (about 0.8 gdw/m 2 /yr). At the Forsmark sites, the N return in

  1. Discussion of the concept of safety indicators from the point of view of TfUX2 accident sequence for Forsmark 3

    International Nuclear Information System (INIS)

    Bujor, A.

    1991-01-01

    This paper contains general considerations on the safety indicators, with details at the system level and for the operator actions. For the system analysis, a modular analysis at a low detailed level is proposed (Module System Approach) in order to emphasize the safety related aspects at the subsystem (module) level. The operator actions are divided in ''active actions'' (actions in the control room during incident/accident situations) and ''passive actions'' (actions during tests, maintenance, repairs, etc.) and are analysed separately. In the second part, a discussion of a possible way to apply some SI to the TfUX2 accident sequence for FORSMARK-3, is done. For the analysis of the Auxiliary Feedwater Systems (AFWS) an equation is proposed to derive target values for the failure probability on demand at the train level, given the target value at the system level, including the common cause failures between the redundant trains. (author) 6 tabs., 18 refs

  2. SR-Site - sulphide content in the groundwater at Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Tullborg, E-L (Terralogica (Sweden)); Smellie, J (Conterra (Sweden)); Nilsson, A-Ch (Geosigma (Sweden)); Gimeno, M J; Auque, LF (Univ. of Zaragoza (Spain)); Bruchert, V (Stockholms Universitet (Sweden)); Molinero, J (Amphos21 (Spain))

    2010-12-15

    Sulphide concentrations in groundwater play a key role in the long-term reliability of the metal canisters containing the radioactive waste within a disposal facility for nuclear waste. This is because sulphide in the groundwaters circulating in the vicinity of the deposition tunnels can react with copper in the canisters causing corrosion and therefore reducing their expected lifetime; in a worst case scenario erosion of the bentonite buffer material will expose the canister more rapidly to the fracture groundwater.Sulphide in the groundwater is predominantly microbially produced and thereby controlled by the content of oxidised sulphur sources, organics (carbon sources), reductants (mainly Fe(II), DOC, H{sub 2} and CH{sub 4}), and also flow and mixing of different groundwater types. In addition, achieved saturation in respect to amorphous Fe-monosulphide will control the possible maximum values and will also limit the Fe2+ and S2- values in the groundwater. The aim of this report is to assess realistic, representative and reliable sulphide groundwater concentrations at present conditions in Forsmark and also to evaluate possible changes during different climatic conditions covering the repository operation period (some tens to hundreds of years), post closure conditions (some thousand of years) and the proceeding temperate period (some tens of thousands of years) which may be extended due to enhanced greenhouse effects etc. It is expected that this period will be followed by the onset of the next glaciation during which periglacial (permafrost), glacial and postglacial conditions may succeed each other. To achieve these aims, an evaluation is performed of all the sulphide-related data reported from the Forsmark site investigations /Laaksoharju et al. 2008/ and later monitoring campaigns, all of which are stored in the Sicada database. This evaluation shows that values from the Complete Chemical Characterisation (CCC) sampling are usually lower than those measured

  3. SR-Site - sulphide content in the groundwater at Forsmark

    International Nuclear Information System (INIS)

    Tullborg, E-L; Smellie, J; Nilsson, A-Ch; Gimeno, M J; Auque, LF; Bruchert, V; Molinero, J

    2010-12-01

    Sulphide concentrations in groundwater play a key role in the long-term reliability of the metal canisters containing the radioactive waste within a disposal facility for nuclear waste. This is because sulphide in the groundwaters circulating in the vicinity of the deposition tunnels can react with copper in the canisters causing corrosion and therefore reducing their expected lifetime; in a worst case scenario erosion of the bentonite buffer material will expose the canister more rapidly to the fracture groundwater.Sulphide in the groundwater is predominantly microbially produced and thereby controlled by the content of oxidised sulphur sources, organics (carbon sources), reductants (mainly Fe(II), DOC, H 2 and CH 4 ), and also flow and mixing of different groundwater types. In addition, achieved saturation in respect to amorphous Fe-monosulphide will control the possible maximum values and will also limit the Fe 2+ and S 2- values in the groundwater. The aim of this report is to assess realistic, representative and reliable sulphide groundwater concentrations at present conditions in Forsmark and also to evaluate possible changes during different climatic conditions covering the repository operation period (some tens to hundreds of years), post closure conditions (some thousand of years) and the proceeding temperate period (some tens of thousands of years) which may be extended due to enhanced greenhouse effects etc. It is expected that this period will be followed by the onset of the next glaciation during which periglacial (permafrost), glacial and postglacial conditions may succeed each other. To achieve these aims, an evaluation is performed of all the sulphide-related data reported from the Forsmark site investigations /Laaksoharju et al. 2008/ and later monitoring campaigns, all of which are stored in the Sicada database. This evaluation shows that values from the Complete Chemical Characterisation (CCC) sampling are usually lower than those measured during

  4. Dynamics of TRIGA-3 Salazar Reactor

    International Nuclear Information System (INIS)

    Gallardo S, L.F.

    1990-01-01

    The theoretical study of temporal behavior of a nuclear reactor is of great importance, since it allows to know, in advance, the conditions to which a reactor is going to be submitted. The reliability of two computer codes (AIREK-JEN and PLANKIN) designed to reproduce the temporal behavior of nuclear reactors, generally power reactors, when they are applied to reproduce the dynamic behavior of TRIGA-3 Salazar Reactor is analyzed. In the first chapters, the fundamental equations that solve this computer codes are deduced, and also the main characteristics of TRIGA-3 Salazar Reactor and the necessary data to run the programs are presented; later the results obtained with the computer codes and the experimental results reported in the operational logbook of the reactor are compared, with the result that such computer codes are applicable to the temporal study of TRIGA-3 Salazar Reactor. (Author)

  5. Elemental composition of a deep sediment core from Lake Stocksjoen in the Forsmark area

    Energy Technology Data Exchange (ETDEWEB)

    Stroemgren, Maarten [Umeaa Univ. (Sweden). Dept. of Ecology and Environmental Sciences; Brunberg, Anna-Kristina [Uppsala Univ. (Sweden). Dept. of Ecology and Evolution/Limnology

    2006-10-15

    A deep sediment core was taken from Lake Stocksjoen, situated within the Forsmark site investigation area. The 55 cm long sediment core, representing the entire history of the lake (approx 430 years) was sliced in 5 cm portions and analysed for various chemical elements, using ICP-MS technique. In total, 54 different elements - classified as main elements, heavy metals and trace elements - were analysed. In general terms, three different patterns of stratigraphy were derived from all the analysed elements. Calcium, manganese, lead and mercury occurred in highest concentrations in the upper sediments (<30 cm depth). Phosphorus, zinc, cadmium, antimony, tin and strontium occurred in more even proportions throughout the sediment core. All the other elements were substantially reduced in the upper parts (<30 cm) compared to the deeper parts of the sediment core. Metals that are considered as airborne pollutants were found in low or moderate concentrations. This is in concert with other investigations of pollutants that have been performed in the Forsmark area. The sediment of Lake Stocksjoen is highly organic, and has been so during the entire history of the lake. Much of the organic Material seems to be refractory and less susceptible for mineralisation and respiration during the prevailing environmental conditions. This corresponds well with the characteristic gelatinous cyanophycee gyttja found in the lower parts of the sediment core. Although speculative, the pronounced changes in elemental composition of the sediment at 30 cm depth may correspond to the final isolation of the lake from the Baltic Sea, which occurred approximately 230 years ago. The deeper parts (below 30 cm depth) thus may represent the time period with regular intrusions of brackish water into the lake basin. One important factor governing the environmental conditions and the resulting elemental composition of the sediment is the unusually thick 'microbial mat', which is characteristic

  6. Rock-block configuration in Uppland and the Aalands-hav basin, the regional surroundings of the SKB site in Forsmark, Sea and land areas, eastern Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Beckholmen, Monica; Tiren, Sven A. (GEOSIGMA AB (Sweden))

    2010-12-15

    The Forsmark SKB site lies at the west-northwest trending shoreline in northern Uppland, sheltered from the sea by one of the larger islands in the Uppland archipelago, Graesoe. To assess the structures around Forsmark also in the sea area, the bottom structures of the Aalands-hav basin were investigated by means of depth readings from sea charts. Two rock-block maps with rock blocks at different scales were constructed and analysed for their top surface elevation. The topography in Uppland is more broken in the sea area east and northeast of Forsmark than it is on land. The major structure in the Aalands-hav basin is a westnorth- westerly line that passes southwest of Aaland, with a very steep gradient from the Aaland archipelago down to an exceptionally low sea-floor valley. On its southern side it rises in steps to a low flat basin divided into a deeper western half and a somewhat shallower eastern half. The deep west-north-westerly zone can be traced on-land past Oeregrund and Forsmark. West of Oeregrund however, the main trough swings into a north-northwesterly direction, just west of Graesoe. The southern border south of Oeregrund and Forsmark, shows a major drop in elevation northern side down. Forsmark thus lies on a ribbon with lower ground on both its southern and northern boundaries. This west-north-westerly belt is cut in two by a major north-south lineament that cuts through the archipelago between Aaland and Graesoe with a very deep canyon. This structure was seismically active in June 2006. The southern part of this line constitutes the western border of the low basin and has a steep gradient on its western side up to the Uppland mainland. The deep basin is filled with Jotnian metasediments. South of this basin, the Uppland mainland continues under water towards the east. South of Aaland an east-north-easterly ridge separates the low basin to the north from an east-west trending trough which is the eastern continuation of a major onland structure

  7. Rock-block configuration in Uppland and the Aalands-hav basin, the regional surroundings of the SKB site in Forsmark, Sea and land areas, eastern Sweden

    International Nuclear Information System (INIS)

    Beckholmen, Monica; Tiren, Sven A.

    2010-12-01

    The Forsmark SKB site lies at the west-northwest trending shoreline in northern Uppland, sheltered from the sea by one of the larger islands in the Uppland archipelago, Graesoe. To assess the structures around Forsmark also in the sea area, the bottom structures of the Aalands-hav basin were investigated by means of depth readings from sea charts. Two rock-block maps with rock blocks at different scales were constructed and analysed for their top surface elevation. The topography in Uppland is more broken in the sea area east and northeast of Forsmark than it is on land. The major structure in the Aalands-hav basin is a westnorth- westerly line that passes southwest of Aaland, with a very steep gradient from the Aaland archipelago down to an exceptionally low sea-floor valley. On its southern side it rises in steps to a low flat basin divided into a deeper western half and a somewhat shallower eastern half. The deep west-north-westerly zone can be traced on-land past Oeregrund and Forsmark. West of Oeregrund however, the main trough swings into a north-northwesterly direction, just west of Graesoe. The southern border south of Oeregrund and Forsmark, shows a major drop in elevation northern side down. Forsmark thus lies on a ribbon with lower ground on both its southern and northern boundaries. This west-north-westerly belt is cut in two by a major north-south lineament that cuts through the archipelago between Aaland and Graesoe with a very deep canyon. This structure was seismically active in June 2006. The southern part of this line constitutes the western border of the low basin and has a steep gradient on its western side up to the Uppland mainland. The deep basin is filled with Jotnian metasediments. South of this basin, the Uppland mainland continues under water towards the east. South of Aaland an east-north-easterly ridge separates the low basin to the north from an east-west trending trough which is the eastern continuation of a major onland structure

  8. Chemistry data from surface ecosystems in Forsmark and Laxemar-Simpevarp. Site specific data used for estimation of CR and K{sub d} values in SR-Site

    Energy Technology Data Exchange (ETDEWEB)

    Troejbom, Mats [Mats Troejbom Konsult AB (Sweden); Norden, Sara [Svensk Kaernbraenslehantering AB (Sweden)

    2010-11-15

    This report is a background report for the biosphere analysis of the SR-Site Safety Assessment. This work aims to compile information from the Forsmark and Laxemar-Simpevarp sites in order to select and provide relevant site data for parameter sed in the Radionuclide Dose Model. This report contains an overview of all available chemistry data from the surface ecosystems at Forsmark and Laxemar-Simpevarp areas, comprising hydrochemistry of shallow groundwater, porewater, lake water, stream water and sea water as well as the chemical composition of the regolith and biota of the terrestrial, limnic and marine ecosystems. Detailed references to data reports are tabulated and all sampling points are shown in a large number of maps in Chapter 2. An explorative analysis in Chapter 3 is the basis for the final selection of site data described in Chapter 4

  9. The use of plutonium in Swedish reactors

    International Nuclear Information System (INIS)

    Forsstroem, H.

    1982-09-01

    The report deals with the utilization of plutonium in Swedish nuclear power plants. The plutonium content of the mixed oxide fuel will normally be 3-7 per cent. The processing of spent nuclear fuel will produce about 6 ton plutonium. The use of mixed oxide fuel in Forsmark 3 and Oskarshamn 3 is discussed. The fuel cycle will start with the manufacturing of the fuel elements abroad and proceeds with transport and utilization, storing of spent fuel about 40 years in Sweden followed by direct disposal. The manufacture and use of mixed oxide (MOX) fuel is based on well-known techniques. Approximately 20 000 MOX fuel rods have been irradiated and the fuel is essentially equivalent to uranium oxide fuel. 30-50 per cent of the core may be composed of MOX-fuel without any effect on the operation and safety of the reactor which has been originally designed for uranium fuel. The evaluation of international fuel cycle (INFCE) states that the proliferation risks are very small. The recycling of plutonium will reduce demand for enriched uranium and the calculations show that 6.3 ton plutonium will replace the enrichment of 600 ton natural uranium. (G.B.)

  10. Updated model for radionuclide transport in the near-surface till at Forsmark - Implementation of decay chains and sensitivity analyses

    International Nuclear Information System (INIS)

    Pique, Angels; Pekala, Marek; Molinero, Jorge; Duro, Lara; Trinchero, Paolo; Vries, Luis Manuel de

    2013-02-01

    The Forsmark area has been proposed for potential siting of a deep underground (geological) repository for radioactive waste in Sweden. Safety assessment of the repository requires radionuclide transport from the disposal depth to recipients at the surface to be studied quantitatively. The near-surface quaternary deposits at Forsmark are considered a pathway for potential discharge of radioactivity from the underground facility to the biosphere, thus radionuclide transport in this system has been extensively investigated over the last years. The most recent work of Pique and co-workers (reported in SKB report R-10-30) demonstrated that in case of release of radioactivity the near-surface sedimentary system at Forsmark would act as an important geochemical barrier, retarding the transport of reactive radionuclides through a combination of retention processes. In this report the conceptual model of radionuclide transport in the quaternary till at Forsmark has been updated, by considering recent revisions regarding the near-surface lithology. In addition, the impact of important conceptual assumptions made in the model has been evaluated through a series of deterministic and probabilistic (Monte Carlo) sensitivity calculations. The sensitivity study focused on the following effects: 1. Radioactive decay of 135 Cs, 59 Ni, 230 Th and 226 Ra and effects on their transport. 2. Variability in key geochemical parameters, such as the composition of the deep groundwater, availability of sorbing materials in the till, and mineral equilibria. 3. Variability in hydraulic parameters, such as the definition of hydraulic boundaries, and values of hydraulic conductivity, dispersivity and the deep groundwater inflow rate. The overarching conclusion from this study is that the current implementation of the model is robust (the model is largely insensitive to variations in the parameters within the studied ranges) and conservative (the Base Case calculations have a tendency to

  11. Thermal properties Forsmark. Modelling stage 2.3 Complementary analysis and verification of the thermal bedrock model, stage 2.

    Energy Technology Data Exchange (ETDEWEB)

    Sundberg, Jan; Wrafter, John; Laendell, Maerta (Geo Innova AB (Sweden)); Back, Paer-Erik; Rosen, Lars (Sweco AB (Sweden))

    2008-11-15

    This report present the results of thermal modelling work for the Forsmark area carried out during modelling stage 2.3. The work complements the main modelling efforts carried out during modelling stage 2.2. A revised spatial statistical description of the rock mass thermal conductivity for rock domain RFM045 is the main result of this work. Thermal modelling of domain RFM045 in Forsmark model stage 2.2 gave lower tail percentiles of thermal conductivity that were considered to be conservatively low due to the way amphibolite, the rock type with the lowest thermal conductivity, was modelled. New and previously available borehole data are used as the basis for revised stochastic geological simulations of domain RFM045. By defining two distinct thermal subdomains, these simulations have succeeded in capturing more of the lithological heterogeneity present. The resulting thermal model for rock domain RFM045 is, therefore, considered to be more realistic and reliable than that presented in model stage 2.2. The main conclusions of modelling efforts in model stage 2.3 are: - Thermal modelling indicates a mean thermal conductivity for domain RFM045 at the 5 m scale of 3.56 W/(mK). This is slightly higher than the value of 3.49 W/(mK) derived in model stage 2.2. - The variance decreases and the lower tail percentiles increase as the scale of observation increases from 1 to 5 m. Best estimates of the 0.1 percentile of thermal conductivity for domain RFM045 are 2.24 W/(mK) for the 1 m scale and 2.36 W/(mK) for the 5 m scale. This can be compared with corresponding values for domain RFM029 of 2.30 W/(mK) for the 1 m scale and 2.87 W/(mK)for the 5 m scale. - The reason for the pronounced lower tail in the thermal conductivity distribution for domain RFM045 is the presence of large bodies of the low-conductive amphibolite. - The modelling results for domain RFM029 presented in model stage 2.2 are still applicable. - As temperature increases, the thermal conductivity decreases

  12. Removal of groundwater from final repository in Forsmark. Description of consequences for nature values and forest production; Bortledande av grundvatten fraan slutfoervarsanlaeggningen i Forsmark. Beskrivning av konsekvenser foer naturvaerden och skogsproduktion

    Energy Technology Data Exchange (ETDEWEB)

    Hamren, Ulrika; Collinder, Per; Allmer, Johan (Ekologigruppen AB (Sweden))

    2010-11-15

    The Swedish Nuclear Fuel and Waste Management Co (SKB) has chosen Forsmark in the Municipality of Oesthammar as site for the final repository for spent nuclear fuel. This report describes consequences for nature values and forestry due to groundwater diversion during construction and operation of the repository. The report concerns nature values that depend on, or are favoured by, a groundwater table close to or above the ground surface

  13. Solute transport in coupled inland-coastal water systems. General conceptualisation and application to Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Jarsjoe, Jerker; Destouni, Georgia; Persson, Klas; Prieto, Carmen (Dept. of Physical Geography, Quaternary Geology, Stockholm Univ., Stockholm (Sweden))

    2007-12-15

    We formulate a general theoretical conceptualisation of solute transport from inland sources to downstream recipients, considering main recipient load contributions from all different nutrient and pollutant sources that may exist within any catchment. Since the conceptualisation is model independent, its main hydrological factors and mass delivery factors can be quantified on the basis of inputs to and outputs from any considered analytical or numerical model. Some of the conceptually considered source contribution and transport pathway combinations are however commonly neglected in catchment-scale solute transport and attenuation modelling, in particular those related to subsurface sources, diffuse sources at the land surface and direct groundwater transport into the recipient. The conceptual framework provides a possible tool for clarification of underlying and often implicit model assumptions, which can be useful for e.g. inter-model comparisons. In order to further clarify and explain research questions that may be of particular importance for transport pathways from deep groundwater surrounding a repository, we concretise and interpret some selected transport scenarios for model conditions in the Forsmark area. Possible uncertainties in coastal discharge predictions, related to uncertain spatial variation of evapotranspiration within the catchment, were shown to be small for the relatively large, focused surface water discharges from land to sea, because local differences were averaged out along the length of the main water flow paths. In contrast, local flux values within the diffuse groundwater flow field from land to sea are more uncertain, although estimates of mean values and total sums of submarine groundwater discharge (SGD) along some considerable coastline length may be robust. The present results show that 80% to 90% of the total coastal discharge of Forsmark occurred through focused flows in visible streams, whereas the remaining 10% to 20% was

  14. The terrestrial ecosystems at Forsmark and Laxemar-Simpevarp. SR-Site Biosphere

    Energy Technology Data Exchange (ETDEWEB)

    Loefgren, Anders [ed.; EcoAnalytica, Haegersten (Sweden)

    2010-12-15

    The ecosystem is in most cases the link between radionuclides released from a repository and the exposure of humans and other biota to them. This report describes the terrestrial ecosystems in the Forsmark and Laxemar-Simpevarp areas by summarizing and performing cross-disciplinary analyses of data from a large number of reports produced during the site investigations, Figure 1-2. The report describes the terrestrial landscape, divided here into the three main categories: forests, wetlands and agriculture land, by identifying properties that are important for element accumulation and transport

  15. The terrestrial ecosystems at Forsmark and Laxemar-Simpevarp. SR-Site Biosphere

    International Nuclear Information System (INIS)

    Loefgren, Anders

    2010-12-01

    The ecosystem is in most cases the link between radionuclides released from a repository and the exposure of humans and other biota to them. This report describes the terrestrial ecosystems in the Forsmark and Laxemar-Simpevarp areas by summarizing and performing cross-disciplinary analyses of data from a large number of reports produced during the site investigations, Figure 1-2. The report describes the terrestrial landscape, divided here into the three main categories: forests, wetlands and agriculture land, by identifying properties that are important for element accumulation and transport

  16. Preliminary site description Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Skagius, Kristina [ed.

    2005-06-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterisation at two different locations, the Forsmark and Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. An integrated component in the characterisation work is the development of a site descriptive model that constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere as well as those ongoing natural processes that affect their long-term evolution. The present report documents the site descriptive modelling activities (version 1.2) for the Forsmark area. The overall objectives of the version 1.2 site descriptive modelling are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations. The modelling work is based on primary data, i.e. quality-assured, geoscientific and ecological field data available in the SKB databases SICADA and GIS, available July 31, 2004. The work has been conducted by a project group and associated discipline-specific working groups. The members of the project group represent the disciplines of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and surface ecosystems (including overburden, surface hydrogeochemistry and hydrology). In addition, some group members have specific qualifications of importance in this type of project e.g. expertise in RVS (Rock Visualisation System) modelling, GIS-modelling and in statistical data analysis. The overall strategy to achieve a site description is to develop discipline-specific models by interpretation and analyses of the primary data. The different discipline-specific models are then integrated into a site description. Methodologies for developing the discipline-specific models are documented in

  17. Preliminary site description Forsmark area - version 1.2

    International Nuclear Information System (INIS)

    Skagius, Kristina

    2005-06-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterisation at two different locations, the Forsmark and Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. An integrated component in the characterisation work is the development of a site descriptive model that constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere as well as those ongoing natural processes that affect their long-term evolution. The present report documents the site descriptive modelling activities (version 1.2) for the Forsmark area. The overall objectives of the version 1.2 site descriptive modelling are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations. The modelling work is based on primary data, i.e. quality-assured, geoscientific and ecological field data available in the SKB databases SICADA and GIS, available July 31, 2004. The work has been conducted by a project group and associated discipline-specific working groups. The members of the project group represent the disciplines of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and surface ecosystems (including overburden, surface hydrogeochemistry and hydrology). In addition, some group members have specific qualifications of importance in this type of project e.g. expertise in RVS (Rock Visualisation System) modelling, GIS-modelling and in statistical data analysis. The overall strategy to achieve a site description is to develop discipline-specific models by interpretation and analyses of the primary data. The different discipline-specific models are then integrated into a site description. Methodologies for developing the discipline-specific models are documented in

  18. Chemical conditions in present and future ecosystems in Forsmark - implications for selected radionuclides in the safety assessment SR-Site

    International Nuclear Information System (INIS)

    Troejbom, Mats; Grolander, Sara

    2010-12-01

    This report is a background report for the biosphere analysis of the SR-Site Safety Assessment. This work aims to describe the future development of the chemical conditions at Forsmark, based on the present chemical conditions at landscape level taking landscape development and climate cases into consideration. The results presented contribute to the overall understanding of the present and future chemistry in the Forsmark area, and specifically, to the understanding of the behaviour of some selected radionuclides in the surface system. The future development of the chemistry at the site is qualitatively discussed with focus on the interglacial within the next 10,000 years. The effects on the chemical environment of future climate cases as Global Warming and cold permafrost climates are also briefly discussed. The work is presented in two independent parts describing background radionuclide activities in the Forsmark area and the distribution and behaviour of a large number of stable elements in the landscape. In a concluding section, implications of the future chemical environment of a selection of radionuclides important in the Safety Assessment are discussed based on the knowledge of stable elements. The broad range of elements studied show that there are general and expected patterns for the distribution and behaviour in the landscape of different groups of elements. Mass balances reveal major sources and sinks, pool estimations show where elements are accumulated in the landscape and estimations of time-scales give indications of the potential future development. This general knowledge is transferred to radionuclides not measured in order to estimate their behaviour and distribution in the landscape. It could be concluded that the future development of the chemical environment in the Forsmark area might affect element specific parameters used in de radionuclide model in different directions depending on element. The alternative climate cases, Global Warming

  19. Chemical conditions in present and future ecosystems in Forsmark - implications for selected radionuclides in the safety assessment SR-Site

    Energy Technology Data Exchange (ETDEWEB)

    Troejbom, Mats (Mats Troejbom Konsult AB (Sweden)); Grolander, Sara (Facilia AB (Sweden))

    2010-12-15

    This report is a background report for the biosphere analysis of the SR-Site Safety Assessment. This work aims to describe the future development of the chemical conditions at Forsmark, based on the present chemical conditions at landscape level taking landscape development and climate cases into consideration. The results presented contribute to the overall understanding of the present and future chemistry in the Forsmark area, and specifically, to the understanding of the behaviour of some selected radionuclides in the surface system. The future development of the chemistry at the site is qualitatively discussed with focus on the interglacial within the next 10,000 years. The effects on the chemical environment of future climate cases as Global Warming and cold permafrost climates are also briefly discussed. The work is presented in two independent parts describing background radionuclide activities in the Forsmark area and the distribution and behaviour of a large number of stable elements in the landscape. In a concluding section, implications of the future chemical environment of a selection of radionuclides important in the Safety Assessment are discussed based on the knowledge of stable elements. The broad range of elements studied show that there are general and expected patterns for the distribution and behaviour in the landscape of different groups of elements. Mass balances reveal major sources and sinks, pool estimations show where elements are accumulated in the landscape and estimations of time-scales give indications of the potential future development. This general knowledge is transferred to radionuclides not measured in order to estimate their behaviour and distribution in the landscape. It could be concluded that the future development of the chemical environment in the Forsmark area might affect element specific parameters used in de radionuclide model in different directions depending on element. The alternative climate cases, Global Warming

  20. Rock thermal property measurements with the Posiva TERO56 drill hole device in the forsmark study site

    International Nuclear Information System (INIS)

    Kukkonen, I.; Suppala, I.; Korpisalo, A.

    2007-10-01

    Thermal properties were measured in situ in Forsmark at the SKB study site constructed for large-scale thermal conductivity investigations in an outcrop of anisotropic granite. The Posiva TERO56 drill hole tool was used for in situ measurements in four 20 m deep boreholes KFM90C, D, E and F located within very short distances of each other (less than 2.3 m). Measurements were done at depths of 10-18 m in water-filled holes. The bedrock is granite with thin amphibolite and pegmatite layers and thin felsic veins. The measurement principle of the TERO56 logging device is based on conduction of heat from a cylindrical source placed in a borehole and the thermal parameter values are calculated with a least squares inversion algorithm. Measurements in Forsmark consisted typically of 6 hours heating time followed by 10 hours cooling time, but in one measurement the heating time was reduced to of 2 h 45 min and the cooling time to 5 hours. Average thermal conductivity values range from 3.37 to 3.91 W m -1 K -1 with standard deviations between 0.01 and 0.04 W m -1 K -1 . The result is plausible considering the quite homogeneous target geology and short distances between different experiment stations. Diffusivity values, however, vary much more, and averages range from 0.68 to 2.08 A 10 -6 m 2 s -1 with standard deviations ranging from 0.04 to 0.09 A 10 -6 m 2 s -1 . Variations may be attributed to small flow effects or time-dependent temperature trends related to thermal equilibration of the probe. (orig.)

  1. Quantitative assessment of radionuclide retention in the near-surface system at Forsmark. Development of a reactive transport model using Forsmark 1.2 data

    Energy Technology Data Exchange (ETDEWEB)

    Grandia, Fidel; Sena, Clara; Arcos, David; Molinero, Jorge; Duro, Lara; Bruno, Jordi (Amphos XXI Consulting S.L., Barcelona (Spain))

    2007-12-15

    The main objective of this work is to assess the migration behaviour of selected long-lived radionuclides through the near-surface system of Forsmark, with special focus on the evaluation of the capacity of the Quaternary deposits and sediments for radionuclide retention. The work reported here is based on data and information from Forsmark Site Descriptive Model version 1.2. From the geological point of view, the near-surface systems in the Forsmark area consist of Quaternary deposits and sediments that overlay the granitic bedrock. Glacial till is the more abundant outcropping Quaternary deposit and the remainder is made of clayey deposits. These types of near-surface sediments show distinctive hydraulic and geochemical features. The main reactive mineral in the till deposits, for the time horizons considered in this work, is calcium carbonate together with minor amounts of clay minerals (e.g. illite). The till deposits forms aquifers with relatively high hydraulic conductivities. In contrast, glacial and post-glacial clays are basically composed of illite with low to very low amounts of calcium carbonate, and containing organic matter-rich layers (gyttja), which can promote reducing conditions in the porewaters. All these clays exhibits relatively low hydraulic conductivity values. Five radionuclides have been selected for conceptualization and qualitative evaluation of retention process: U as an actinide, Se as a redox-sensitive radionuclide, Cs as a monovalent cation, Sr as a divalent cation, and I as an anion radionuclide. Overall, radionuclide retention capacity in the surface systems at Forsmark can be provided by sorption on charged surfaces of clays and oxyhydroxides, co-precipitation with sulphates, sulphides, oxyhydroxides and carbonates, and sorption on organic matter. Two-dimensional coupled hydrogeological and reactive solute transport models have been developed to simulate the geochemical behaviour of U, Cs and Sr. These three radionuclides have

  2. Explorative analysis of major components and isotopes. SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Smellie, John (Conterra AB (Sweden)); Tullborg, Eva-Lena (Terralogica AB (Sweden)); Nilsson, Ann-Chatrin (Geosigma AB (Sweden)); Sandstroem, Bjoern (Goeteborg Univ. (Sweden)); Waber, Niklaus (Univ. of Bern (Switzerland)); Gimeno, Maria (Univ. of Zaragoza (Spain)); Gascoyne, Mel (GGP Inc. (United Kingdom))

    2008-09-15

    The overall objectives of the hydrogeochemical description for Forsmark are to establish a detailed understanding of the hydrogeochemical conditions at the site and to develop models that fulfil the needs identified by the safety assessment groups during the site investigation phase. Issues of concern to safety assessment are radionuclide transport and technical barrier behaviour, both of which are dependent on the chemistry of groundwater and pore water and their evolution with time. The work has involved the development of descriptive and mathematical models for groundwaters in relation to rock domains, fracture domains and deformation zones. Past climate events are the major driving force for hydrogeochemical changes and therefore are of fundamental importance for understanding the palaeohydrogeological, palaeohydrogeochemical and present evolution of groundwater in the crystalline bedrock of the Fennoscandian Shield. Understanding current undisturbed hydrochemical conditions at the proposed repository site is important when predicting future changes in groundwater chemistry. The causes behind copper corrosion and/or bentonite degradation are of particular interest as they may jeopardise the long-term integrity of the planned SKB repository system. Thus, the following variables are considered for the hydrogeochemical site descriptive modelling: pH, Eh, sulphur species, iron, manganese, carbonate, phosphate, nitrogen species, total dissolved solids (TDS), isotopes, colloids, fulvic and humic acids and microorganisms. In addition, dissolved gases (e.g. carbon dioxide, methane and hydrogen) are of interest because of their likely participation in microbial reactions. In this series of reports, the final hydrogeochemical evaluation work of the site investigation at the Forsmark site, is presented. The work was conducted by SKB's hydrogeochemical project group, ChemNet, which consists of independent consultants and university researchers with expertise in

  3. Explorative analysis of major components and isotopes. SDM-Site Forsmark

    International Nuclear Information System (INIS)

    Smellie, John; Tullborg, Eva-Lena; Nilsson, Ann-Chatrin; Sandstroem, Bjoern; Waber, Niklaus; Gimeno, Maria; Gascoyne, Mel

    2008-09-01

    The overall objectives of the hydrogeochemical description for Forsmark are to establish a detailed understanding of the hydrogeochemical conditions at the site and to develop models that fulfil the needs identified by the safety assessment groups during the site investigation phase. Issues of concern to safety assessment are radionuclide transport and technical barrier behaviour, both of which are dependent on the chemistry of groundwater and pore water and their evolution with time. The work has involved the development of descriptive and mathematical models for groundwaters in relation to rock domains, fracture domains and deformation zones. Past climate events are the major driving force for hydrogeochemical changes and therefore are of fundamental importance for understanding the palaeohydrogeological, palaeohydrogeochemical and present evolution of groundwater in the crystalline bedrock of the Fennoscandian Shield. Understanding current undisturbed hydrochemical conditions at the proposed repository site is important when predicting future changes in groundwater chemistry. The causes behind copper corrosion and/or bentonite degradation are of particular interest as they may jeopardise the long-term integrity of the planned SKB repository system. Thus, the following variables are considered for the hydrogeochemical site descriptive modelling: pH, Eh, sulphur species, iron, manganese, carbonate, phosphate, nitrogen species, total dissolved solids (TDS), isotopes, colloids, fulvic and humic acids and microorganisms. In addition, dissolved gases (e.g. carbon dioxide, methane and hydrogen) are of interest because of their likely participation in microbial reactions. In this series of reports, the final hydrogeochemical evaluation work of the site investigation at the Forsmark site, is presented. The work was conducted by SKB's hydrogeochemical project group, ChemNet, which consists of independent consultants and university researchers with expertise in

  4. Description of climate, surface hydrology, and near-surface hydrogeology. Preliminary site description. Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Johansson, Per-Olof [Artesia Grundvattenkonsult AB, Stockholm (Sweden); Werner, Kent [SWECO VIAK AB/Golder Associates AB, Stockholm (Sweden); Bosson, Emma; Berglund, Sten [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Juston, John [DBE Sweden, Uppsala (Sweden)

    2005-06-15

    obtained with the corresponding Forsmark version 1.1 DarcyTools groundwater flow model, i.e. average inflows (upward flows) of 1.3 (MIKE SHE) and 2.3 (DarcyTools) mmxyear-1, respectively. Also the results from the particle tracking simulations show that the groundwater flow is dominated by its vertical component. The dominant transport of particles in the rock occurs in the fracture zones. Therefore, the shortest travel times are observed for the registration/ observation zones underlain by large fracture zones. However, it should be noted that the present particle tracking results are based on the Forsmark 1.1 hydrogeological model of the rock, and that changes in the spatial patterns of particle release areas can be expected when the present model is updated in accordance with the Forsmark 1.2 hydrogeological model of the rock. A relatively large amount of new data has been available for the Forsmark version 1.2 modelling of surface hydrology and near-surface hydrogeology. Specifically, the evaluation of time series of local meteorological data and surface water and groundwater levels, enabling comparisons between different processes and hydrological sub-systems, has lead to an improved understanding of the site that supports some of the fundamental aspects of the descriptive model. However, significant uncertainties still exist regarding the interactions between different sub-systems and the spatial and temporal variability of model parameters. In particular, the site-specific basis for setting boundary conditions in hydrological models (i.e. meteorological data) and for evaluating calculated water balances and surface water discharges (i.e. discharge measurements) is still quite weak. The available local meteorological time series are very short and longer time series are needed to get reliable correlations to nearby regional SMHI-stations. Local continuous discharge measurements were not available for the Forsmark 1.2 modelling. Future time series from such

  5. Results from Marine geological investigations outside Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Nyberg, Johan; Elhammer, Anders; Sohlenius, Gustav; Kjellin, Bernt; Nordgren, Paer (Geological Survey of Sweden (Sweden))

    2011-08-15

    A detailed marine geological survey was conducted in a 10 km2 large area outside Forsmark comprising hydro acoustic, 100 m spacing between survey lines, and groundtruthing. These data, together with reanalyzed survey data retrieved in 2002 from the same area, were used to produce maps of seabed and underlying bedrock surface morphology as well as horizontal and vertical extension of sediments. An esker is discovered running approximately in a north northwesterly-south southeasterly direction in the area, which may be causing submarine groundwater discharge. Pockmarks, which are caused by sediment gas of thermogenic and/or microbial origin, are detected in the area. In addition to the original commissioned survey, bedrock surface and seabed morphology as well as horizontal and vertical extension of sediments in a larger adjacent area were reanalyzed and produced from survey lines retrieved during a commission by SKB in 2002 and during SGUs regular mapping program in 2002, 2008 and 2009

  6. Results from Marine geological investigations outside Forsmark

    International Nuclear Information System (INIS)

    Nyberg, Johan; Elhammer, Anders; Sohlenius, Gustav; Kjellin, Bernt; Nordgren, Paer

    2011-08-01

    A detailed marine geological survey was conducted in a 10 km 2 large area outside Forsmark comprising hydro acoustic, 100 m spacing between survey lines, and groundtruthing. These data, together with reanalyzed survey data retrieved in 2002 from the same area, were used to produce maps of seabed and underlying bedrock surface morphology as well as horizontal and vertical extension of sediments. An esker is discovered running approximately in a north northwesterly-south southeasterly direction in the area, which may be causing submarine groundwater discharge. Pockmarks, which are caused by sediment gas of thermogenic and/or microbial origin, are detected in the area. In addition to the original commissioned survey, bedrock surface and seabed morphology as well as horizontal and vertical extension of sediments in a larger adjacent area were reanalyzed and produced from survey lines retrieved during a commission by SKB in 2002 and during SGUs regular mapping program in 2002, 2008 and 2009

  7. The potential for cold climate conditions and permafrost in Forsmark in the next 60 000 years

    Energy Technology Data Exchange (ETDEWEB)

    Brandefelt, Jenny; Naeslund, Jens-Ove [Svensk Kaernbraenslehantering, Stockholm (Sweden); Zhang, Qiong [Dept. of Meteorology, Stockholm Univ., Stockholm (Sweden); Hartikainen, Juha [School of Engineering, Aalto Univ., Aalto (Finland)

    2013-05-15

    simulations with an Earth system model of intermediate complexity (EMIC) and a state-of-the-art Earth System Model (ESM). To span the possible combinations of future orbital variations and possible future atmospheric CO{sub 2} concentrations, three sets of simulations were performed. The first set consists of a suite of EMIC simulations performed for the future periods of minimum summer insolation at high northern latitudes (17 ka and 54 ka AP) with the atmospheric CO{sub 2} concentration varying in the range 180 - 400 ppmv. These are equilibrium simulations with constant forcing conditions. The second set consists of two EMIC simulations with constant atmospheric CO{sub 2} concentration of 200 or 400 ppmv respectively and insolation variations for the full period from the present to 61 ka AP. The third set of simulations consists of two ESM equilibrium simulations with insolation for 17ka and 54ka AP and atmospheric CO{sub 2} concentration set to 200 ppmv and 180 ppmv respectively. This set was used, in combination with published results from climate model inter-comparisons, to estimate the uncertainty in the EMIC results due to the simplified model formulation. The annual average bias-corrected air temperature at 2 m height (T2m) at Forsmark (with respect to observations) varies from 0.96 deg C to 5.3 deg C (1.6 deg C to 5.7 deg C) in the EMIC simulations for orbital year 17 ka AP (54 ka AP) when the atmospheric CO{sub 2} concentration is varied from 180 ppmv to 400 ppmv. The insolation difference between orbital year 17 ka AP and 54 ka AP results in a difference in the annual average Forsmark T2m of c. 0.3 - 1.2 deg C with a tendency towards larger differences for lower atmospheric CO2 concentration. These results indicate that the future atmospheric CO{sub 2} concentration is more important than insolation variations for future climate in Forsmark in the next 60 ka. The climate models used in the present study do not include glacier and ice sheet dynamics, which presents

  8. The potential for cold climate conditions and permafrost in Forsmark in the next 60 000 years

    International Nuclear Information System (INIS)

    Brandefelt, Jenny; Naeslund, Jens-Ove; Zhang, Qiong; Hartikainen, Juha

    2013-05-01

    of intermediate complexity (EMIC) and a state-of-the-art Earth System Model (ESM). To span the possible combinations of future orbital variations and possible future atmospheric CO 2 concentrations, three sets of simulations were performed. The first set consists of a suite of EMIC simulations performed for the future periods of minimum summer insolation at high northern latitudes (17 ka and 54 ka AP) with the atmospheric CO 2 concentration varying in the range 180 - 400 ppmv. These are equilibrium simulations with constant forcing conditions. The second set consists of two EMIC simulations with constant atmospheric CO 2 concentration of 200 or 400 ppmv respectively and insolation variations for the full period from the present to 61 ka AP. The third set of simulations consists of two ESM equilibrium simulations with insolation for 17ka and 54ka AP and atmospheric CO 2 concentration set to 200 ppmv and 180 ppmv respectively. This set was used, in combination with published results from climate model inter-comparisons, to estimate the uncertainty in the EMIC results due to the simplified model formulation. The annual average bias-corrected air temperature at 2 m height (T2m) at Forsmark (with respect to observations) varies from 0.96 deg C to 5.3 deg C (1.6 deg C to 5.7 deg C) in the EMIC simulations for orbital year 17 ka AP (54 ka AP) when the atmospheric CO 2 concentration is varied from 180 ppmv to 400 ppmv. The insolation difference between orbital year 17 ka AP and 54 ka AP results in a difference in the annual average Forsmark T2m of c. 0.3 - 1.2 deg C with a tendency towards larger differences for lower atmospheric CO2 concentration. These results indicate that the future atmospheric CO 2 concentration is more important than insolation variations for future climate in Forsmark in the next 60 ka. The climate models used in the present study do not include glacier and ice sheet dynamics, which presents a potential warm bias in the simulated climate. Comparison

  9. SKI - ASAR - F3. As operated Safety Analysis Report. Recurring safety review 1996 Forsmark 3

    International Nuclear Information System (INIS)

    1997-12-01

    According to Swedish law, the reactor owner is responsible for performing a safety review and writing a ''ASAR''-report. The Nuclear Power Inspectorate (SKI) examines this report, and reports the findings to the government (the ''SKI-ASAR'' report). Each Swedish reactor should pass through three full ASAR reviews during its life-time, similar to the licensing inspection before start-up of the reactor. The first series ASAR was delivered by FKA to SKI in December 1996, and forms the basis for the SKI analysis in the present report

  10. Using largest Lyapunov exponent to confirm the intrinsic stability of boiling water reactors

    International Nuclear Information System (INIS)

    Gavilian-Moreno, Carlos; Espinosa-Paredes, Gilberto

    2016-01-01

    The aim of this paper is the study of instability state of boiling water reactors with a method based in largest Lyapunov exponents (LLEs). Detecting the presence of chaos in a dynamical system is an important problem that is solved by measuring the LLE. Lyapunov exponents quantify the exponential divergence of initially close state-space trajectories and estimate the amount of chaos in a system. This method was applied to a set of signals from several nuclear power plant (NPP) reactors under commercial operating conditions that experienced instabilities events, apparently each of a different nature. Laguna Verde and Forsmark NPPs with in-phase instabilities, and Cofrentes NPP with out-of-phases instability. This study presents the results of intrinsic instability in the boiling water reactors of three NPPs. In the analyzed cases the limit cycle was not reached, which implies that the point of equilibrium exerts influence and attraction on system evolution

  11. Using largest Lyapunov exponent to confirm the intrinsic stability of boiling water reactors

    Energy Technology Data Exchange (ETDEWEB)

    Gavilian-Moreno, Carlos [Iberdrola Generacion, S.A., Cofrentes Nuclear Power Plant, Project Engineering Department, Paraje le Plano S/N, Valencia (Spain); Espinosa-Paredes, Gilberto [Area de ingeniera en Recursos Energeticos, Universidad Autonoma Metropolitana-Iztapalapa, Mexico city (Mexico)

    2016-04-15

    The aim of this paper is the study of instability state of boiling water reactors with a method based in largest Lyapunov exponents (LLEs). Detecting the presence of chaos in a dynamical system is an important problem that is solved by measuring the LLE. Lyapunov exponents quantify the exponential divergence of initially close state-space trajectories and estimate the amount of chaos in a system. This method was applied to a set of signals from several nuclear power plant (NPP) reactors under commercial operating conditions that experienced instabilities events, apparently each of a different nature. Laguna Verde and Forsmark NPPs with in-phase instabilities, and Cofrentes NPP with out-of-phases instability. This study presents the results of intrinsic instability in the boiling water reactors of three NPPs. In the analyzed cases the limit cycle was not reached, which implies that the point of equilibrium exerts influence and attraction on system evolution.

  12. Using Largest Lyapunov Exponent to Confirm the Intrinsic Stability of Boiling Water Reactors

    Directory of Open Access Journals (Sweden)

    Carlos J. Gavilán-Moreno

    2016-04-01

    Full Text Available The aim of this paper is the study of instability state of boiling water reactors with a method based in largest Lyapunov exponents (LLEs. Detecting the presence of chaos in a dynamical system is an important problem that is solved by measuring the LLE. Lyapunov exponents quantify the exponential divergence of initially close state-space trajectories and estimate the amount of chaos in a system. This method was applied to a set of signals from several nuclear power plant (NPP reactors under commercial operating conditions that experienced instabilities events, apparently each of a different nature. Laguna Verde and Forsmark NPPs with in-phase instabilities, and Cofrentes NPP with out-of-phases instability. This study presents the results of intrinsic instability in the boiling water reactors of three NPPs. In the analyzed cases the limit cycle was not reached, which implies that the point of equilibrium exerts influence and attraction on system evolution.

  13. Preliminary site description Forsmark area - version 1.1

    International Nuclear Information System (INIS)

    2004-03-01

    This report presents the interim version (model version 1.1) of the preliminary Site Descriptive Model for Forsmark. The basis for this interim version is quality-assured, geoscientific and ecological field data from Forsmark that were available in the SKB databases SICADA and GIS at April 30, 2003 as well as version 0 of the Site Descriptive Model. The new data acquired during the initial site investigation phase to the date of data freeze 1.1 constitute the basis for the updating of version 0 to version 1.1. These data originate from surface investigations on the candidate area with its regional environment and from drilling and investigations in boreholes. The surface-based data sets were rather extensive whereas the data sets from boreholes were limited to information from one 1,000 m deep cored borehole (KFM01A) and eight 150 to 200 m deep percussion-drilled boreholes in the Forsmark candidate area. Discipline specific models are developed for a selected regional and local model volume and these are then integrated into a site description. The current methodologies for developing the discipline specific models and the integration of these are documented in methodology reports or strategy reports. In the present work, the guidelines given in those reports were followed to the extent possible with the data and information available at the time for data freeze for model version 1.1. Compared with version 0 there are considerable additional features in the version 1.1, especially in the geological description and in the description of the near surface. The geological models of lithology and deformation zones are based on borehole information and much higher resolution surface data. The existence of highly fractured sub-horizontal zones has been verified and these are now part of the model of the deformation zones. A discrete fracture network (DFN) model has also been developed. The rock mechanics model is based on strength information from SFR and an empirical

  14. Development and application of reactor noise diagnostics

    Energy Technology Data Exchange (ETDEWEB)

    Karlsson, Joakim K.H

    1999-04-01

    A number of problems in reactor noise diagnostics have been investigated within the framework of the present thesis. The six papers presented cover three relatively different areas, namely the use of analytical calculations of the neutron noise in simple reactor models, some aspects of boiling water reactor (BWR) stability and diagnostics of core barrel motion in pressurized water reactors (PWRs). The noise induced by small vibrations of a strong absorber has been the subject of several previous investigations. For a conventional {delta}-function source model, the equations can not be linearized in the traditional manner. Thus, a new source model, which is called the {epsilon}/d model, was developed. The correct solution has been derived in the {epsilon}/d model for both 1-D and 2-D reactor models. Recently, several reactor diagnostic problems have occurred which include a control rod partially inserted into the reactor core. In order to study such problems, we have developed an analytically solvable, axially non-homogenous, 2-D reactor model. This model has also been used to study the noise induced by a rod maneuvering experiment. Comparisons of the noise with the results of different reactor kinetic approximations have yielded information on the validity of the approximations in this relatively realistic model. In case of an instability event in a BWR, the noise may consist of one or several co-existing modes of oscillation and besides the fundamental mode, a regional first azimuthal mode has been observed in e.g. the Swedish BWR Ringhals-1. In order to determine the different stability characteristics of the different modes separately, it is important to be able to decompose the noise into its mode constituents. A separation method based on factorisation of the flux has been attempted previously, but without success. The reason for the failure of the factorisation method is the presence of the local component of the noise and its axial correlation properties. In

  15. Development and application of reactor noise diagnostics

    International Nuclear Information System (INIS)

    Karlsson, Joakim K.H.

    1999-04-01

    A number of problems in reactor noise diagnostics have been investigated within the framework of the present thesis. The six papers presented cover three relatively different areas, namely the use of analytical calculations of the neutron noise in simple reactor models, some aspects of boiling water reactor (BWR) stability and diagnostics of core barrel motion in pressurized water reactors (PWRs). The noise induced by small vibrations of a strong absorber has been the subject of several previous investigations. For a conventional δ-function source model, the equations can not be linearized in the traditional manner. Thus, a new source model, which is called the ε/d model, was developed. The correct solution has been derived in the ε/d model for both 1-D and 2-D reactor models. Recently, several reactor diagnostic problems have occurred which include a control rod partially inserted into the reactor core. In order to study such problems, we have developed an analytically solvable, axially non-homogenous, 2-D reactor model. This model has also been used to study the noise induced by a rod maneuvering experiment. Comparisons of the noise with the results of different reactor kinetic approximations have yielded information on the validity of the approximations in this relatively realistic model. In case of an instability event in a BWR, the noise may consist of one or several co-existing modes of oscillation and besides the fundamental mode, a regional first azimuthal mode has been observed in e.g. the Swedish BWR Ringhals-1. In order to determine the different stability characteristics of the different modes separately, it is important to be able to decompose the noise into its mode constituents. A separation method based on factorisation of the flux has been attempted previously, but without success. The reason for the failure of the factorisation method is the presence of the local component of the noise and its axial correlation properties. In the paper

  16. Updated model for radionuclide transport in the near-surface till at Forsmark - Implementation of decay chains and sensitivity analyses

    Energy Technology Data Exchange (ETDEWEB)

    Pique, Angels; Pekala, Marek; Molinero, Jorge; Duro, Lara; Trinchero, Paolo; Vries, Luis Manuel de [Amphos 21 Consulting S.L., Barcelona (Spain)

    2013-02-15

    The Forsmark area has been proposed for potential siting of a deep underground (geological) repository for radioactive waste in Sweden. Safety assessment of the repository requires radionuclide transport from the disposal depth to recipients at the surface to be studied quantitatively. The near-surface quaternary deposits at Forsmark are considered a pathway for potential discharge of radioactivity from the underground facility to the biosphere, thus radionuclide transport in this system has been extensively investigated over the last years. The most recent work of Pique and co-workers (reported in SKB report R-10-30) demonstrated that in case of release of radioactivity the near-surface sedimentary system at Forsmark would act as an important geochemical barrier, retarding the transport of reactive radionuclides through a combination of retention processes. In this report the conceptual model of radionuclide transport in the quaternary till at Forsmark has been updated, by considering recent revisions regarding the near-surface lithology. In addition, the impact of important conceptual assumptions made in the model has been evaluated through a series of deterministic and probabilistic (Monte Carlo) sensitivity calculations. The sensitivity study focused on the following effects: 1. Radioactive decay of {sup 135}Cs, {sup 59}Ni, {sup 230}Th and {sup 226}Ra and effects on their transport. 2. Variability in key geochemical parameters, such as the composition of the deep groundwater, availability of sorbing materials in the till, and mineral equilibria. 3. Variability in hydraulic parameters, such as the definition of hydraulic boundaries, and values of hydraulic conductivity, dispersivity and the deep groundwater inflow rate. The overarching conclusion from this study is that the current implementation of the model is robust (the model is largely insensitive to variations in the parameters within the studied ranges) and conservative (the Base Case calculations have a

  17. Review of possible correlations between in situ stress and PFL fracture transmissivity data at Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Martin, Derek (University of Alberta (United States)); Follin, Sven (SF GeoLogic AB (Sweden))

    2011-11-15

    In laboratory samples, the fracture transmissivity decreases significantly as the confining stress increases. While these experimental relationships are widely accepted and validated on laboratory samples, it is unknown if such relationships exist in situ or if these relationships can be scaled from the centimetre-scale laboratory tests to the metre-scale of in situ fractures. The purpose of this work is to assess the relationship between the structural-hydraulic data gathered in deep, cored boreholes at Forsmark and the in situ stress state acting on the these fractures. In conclusion, there does not appear to be sufficient evidence from these analyses to support the notion that the magnitude of the flow along the fractures at Forsmark is solely controlled by the in situ stress acting on the fracture. This should not be surprising because the majority of the fractures formed more than 1 billion years ago and the current in situ stress state has only been active for the past 12 million years. It is more likely that the transmissivity values are controlled by fracture roughness, open channels within the fracture, fracture stiffness and fracture infilling material

  18. Groundwater flow modelling of periods with temperate climate conditions - Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Joyce, Steven; Simpson, Trevor; Hartley, Lee; Applegate, David; Hoek, Jaap; Jackson, Peter; Swan, David (Serco Technical Consulting Services (United Kingdom)); Marsic, Niko (Kemakta Konsult AB (Sweden)); Follin, Sven (SF GeoLogic AB (Sweden))

    2010-11-15

    As a part of the license application for a final repository for spent nuclear fuel at Forsmark, the Swedish Nuclear Fuel and Waste Management Company (SKB) has undertaken a series of groundwater flow modelling studies. These represent time periods with different climate conditions and the simulations carried out contribute to the overall evaluation of the repository design and long-term radiological safety. This report concerns the modelling of a repository at the Forsmark site during temperate conditions; i.e. from post-closure and throughout the temperate period up until the receding shoreline leaves the modelling domain at around 12,000 AD. The collation and implementation of onsite hydrogeological and hydrogeochemical data from previous reports are used in the construction of a hydrogeological base case (reference case conceptualisation) and then in an examination of various areas of uncertainty within the current understanding by a series of model variants. The hydrogeological base case models at three different scales, 'repository', 'site' and 'regional', make use of continuous porous medium (CPM), equivalent continuous porous medium (ECPM) and discrete fracture network (DFN) models. The use of hydrogeological models allow for the investigation of the groundwater flow from a deep disposal facility to the biosphere and for the calculation of performance measures that will provide an input to the site performance assessment. The focus of the study described in this report has been to perform numerical simulations of the hydrogeological system from post-closure and throughout the temperate period. Besides providing quantitative results for the immediate temperate period following post-closure, these results are also intended to give a qualitative indication of the evolution of the groundwater system during future temperate periods within an ongoing cycle of glacial/inter-glacial events

  19. Comparison of site descriptive models for Olkiluoto, Finland and Forsmark, Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Geier, J.; Bath, A.; Stephansson, O.; Luukkonen, A.

    2012-08-15

    The proposed high-level radioactive waste repository sites at Olkiluoto and Forsmark share broadly similar geologic histories and regional settings. Despite differences in lithology, rock strength and patterns of brittle deformation, the sites show similarities in terms of hydrogeochemistry and hydrogeology. These similarities reflect a dominating influence of saline and brackish water intrusion during inundation by the postglacial Littorina Sea and Baltic Sea, followed by exposure to meteoric waters following postglacial uplift and transition to a Baltic coastal setting. Both sites also contain deep bedrock saline groundwater, though this is more evident at Olkiluoto than at Forsmark. A comparative study of site descriptive models for the two sites identifies the following key differences that could potentially impact safety of a repository: (1) Redox controls, buffering and biogeochemistry at proposed repository depths; (2) Salinity gradients at and below proposed repository depths; (3) Methane concentrations at and below proposed repository depths; (4) Depths to which glacial water and Littorina water penetrated; (5) Cation hydrogeochemistry and water-rock reaction; (6) Pore water compositions in rock matrix; (7) Rock fabric, secondary minerals and alteration with respect to radionuclide retention; (8) Brittle deformation fabric differences on multiple scales that affect vertical hydraulic conductivity; (9) Differences in apparent frequency of encountering water-conducting networks at proposed repository depths; (10) Shallow bedrock hydraulic properties; (11) Unique intrusive or dissolution features; (12) Connectivity of site-scale models to regional-scale features; (13) Mesoproterozoic rocks in vicinity and possibilities for human-intrusion scenarios; (14) Rock stresses and bedrock strength and deformability at proposed repository depths; (15) Thermal anisotropy. These differences are all potentially significant to safety functions, but none are so severe that

  20. Investigation of discrete-fracture network conceptual model uncertainty at Forsmark

    International Nuclear Information System (INIS)

    Geier, Joel

    2011-04-01

    In the present work a discrete fracture model has been further developed and implemented using the latest SKB site investigation data. The model can be used for analysing the fracture network and to model flow through the rock in Forsmark. The aim has been to study uncertainties in the hydrological discrete fracture network (DFN) for the repository model. More specifically the objective has been to study to which extent available data limits uncertainties in the DFN model and how data that can be obtained in future underground work can further limit these uncertainties. Moreover, the effects on deposition hole utilisation and placement have been investigated as well as the effects on the flow to deposition holes

  1. Preliminary assessment of potential underground stability (wedge and spalling) at Forsmark, Simpevarp and Laxemar sites

    Energy Technology Data Exchange (ETDEWEB)

    Martin, Derek [Univ. of Alberta, Edmonton (Canada). Geotechnical Engineering

    2005-12-15

    In SKB's Underground Design Premises the objective in the early design phase is to estimate if there is sufficient space for the repository at a site. One of the conditions that could limit the space available is stability of the underground openings, i.e., deposition tunnels and deposition boreholes. The purpose of this report is to provide a preliminary assessment of the potential for wedge instability and spalling that may be encountered at the Forsmark, Simpevarp and Laxemar sites based on information from the site investigations program up to July 30, 2004. The rock mass spalling strength was defined using the in-situ results from SKB's Aespoe Pillar Stability Experiment and AECL's Mine-by Experiment. These experiments suggest that the rock mass spalling strength for crystalline rocks can be estimated as 0.57 of the mean laboratory uniaxial compressive strength. A probability-based methodology utilizing this in-situ rock mass spalling strength has been developed for assessing the risk for spalling in a repository at the Forsmark, Simpevarp and Laxemar sites. The in-situ stresses and the uniaxial compressive strength data from these sites were used as the bases for the analyses. Preliminary findings from all sites suggest that, generally, the risk for spalling increases as the depth of the repository increases, simply because the stress magnitudes increase with depth. The depth at which the risk for spalling is significant, depends on the individual sites which are discussed below. The greatest uncertainty in the spalling analyses for Forsmark is related to the uncertainty in the horizontal stress magnitudes and associated stress gradients with depth. The confidence in these analyses can only be increased by increasing the confidence in the stress and geology model for the site. From the analyses completed it appears that spalling in the deposition tunnels can be controlled by orienting the tunnels approximately parallel to the maximum horizontal

  2. Preventive maintenance at the Forsmark Nuclear Power Plant

    International Nuclear Information System (INIS)

    Danielsson, H.

    1985-01-01

    The maintenance system at the Forsmark Nuclear Power Plant began in 1975, and was drawn up in co-operation with other power stations within the control of the Swedish State Power Board. Preventive maintenance (PM) is part of the system and has been in operation since 1978. Great efforts have been made to build up the system and to gather input data. Since 1981, the system has been in continuous use; follow-ups and system and quality improvements in database contents have been carried out. Great effort has also been devoted to maintaining a high quality of database contents and to the interplay between the different PM measures. We believe that PM plays an important role in the safety and economic operation of the power station and that it is essential that interest in PM should exist at all levels of the power company. (author)

  3. Forsmark site investigation. Programme for long-term observations of geosphere and biosphere after completed site investigations

    International Nuclear Information System (INIS)

    2007-06-01

    The site investigation at Forsmark was terminated the last of June, 2007. Hundreds of investigations have been conducted during a period of more than five years. Monitoring of a number of geoscientific parameters and biological objects has been one important part of the site investigation programme. Monitoring is defined as recurrent measurements of the same parameters/objects, so that time series are generated. Long-term monitoring of for example weather parameters, surface water discharge in brooks, and the groundwater head in a large number of boreholes has been conducted during the site investigations. Furthermore, repeated sampling of precipitation, surface water and groundwater in soil and rock for hydrochemical analyses has been carried out, and the groundwater flow in isolated borehole sections has been measured several times. Besides, some biological objects, for example rare bird species, have been invented each year of the site investigation. The measured parameters and the invented objects are characterized by a certain degree of time dependent variability, which is also site-specific. The aim of the monitoring is primarily to establish the 'undisturbed' conditions, the so called 'baseline'. If a deep repository is sited at Forsmark, many site-specific conditions will change, due to natural causes as well as to the construction works. Knowledge about the undisturbed conditions strengthens the ability to reveal and quantify such changes and to distinguish natural changes from those caused by the human activities. Another object of monitoring is to, by the study of the variability pattern of the monitored parameters, elevate the knowledge about the underlying, often complex causes governing the variations. In this way the description of site-specific conditions may be more precise and the prospects of modelling important processes are improved. After completion of the site investigations, a period of about two years will follow, when the investigation

  4. Forsmark site investigation. Programme for long-term observations of geosphere and biosphere after completed site investigations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-06-15

    The site investigation at Forsmark was terminated the last of June, 2007. Hundreds of investigations have been conducted during a period of more than five years. Monitoring of a number of geoscientific parameters and biological objects has been one important part of the site investigation programme. Monitoring is defined as recurrent measurements of the same parameters/objects, so that time series are generated. Long-term monitoring of for example weather parameters, surface water discharge in brooks, and the groundwater head in a large number of boreholes has been conducted during the site investigations. Furthermore, repeated sampling of precipitation, surface water and groundwater in soil and rock for hydrochemical analyses has been carried out, and the groundwater flow in isolated borehole sections has been measured several times. Besides, some biological objects, for example rare bird species, have been invented each year of the site investigation. The measured parameters and the invented objects are characterized by a certain degree of time dependent variability, which is also site-specific. The aim of the monitoring is primarily to establish the 'undisturbed' conditions, the so called 'baseline'. If a deep repository is sited at Forsmark, many site-specific conditions will change, due to natural causes as well as to the construction works. Knowledge about the undisturbed conditions strengthens the ability to reveal and quantify such changes and to distinguish natural changes from those caused by the human activities. Another object of monitoring is to, by the study of the variability pattern of the monitored parameters, elevate the knowledge about the underlying, often complex causes governing the variations. In this way the description of site-specific conditions may be more precise and the prospects of modelling important processes are improved. After completion of the site investigations, a period of about two years will follow, when

  5. Water activities in Forsmark (Part II). The final disposal facility for spent fuel: water activities above ground

    International Nuclear Information System (INIS)

    Werner, Kent; Hamren, Ulrika; Collinder, Per; Ridderstolpe, Peter

    2010-09-01

    The construction of the repository for spent nuclear fuel in Forsmark is associated with a number of measures above ground that constitute water operations according to Chapter 11 in the Swedish Environmental Code. This report, which is an appendix to the Environmental Impact Assessment, describes these water operations, their effects and consequences, and planned measures

  6. A basis for modelling of radionuclide flow in the Forsmark biotest basin

    International Nuclear Information System (INIS)

    Notter, M.; Snoeijs, P.; Argaerde, L.; Elert, M.

    1987-01-01

    Certain radionuclides are discharged together with the cooling water of Forsmark power station. Of these, Mn-54, Co-60, Zn-65 and Ag-110 m are easily detectable in the environment. This report gives a conceptual five-compartment model for the flows of radionuclides within the basin ecosystem. The available data from biological and radio-ecological investigations in the biotest basin were used to quantify the amounts of radionuclides in each of the reservoirs. The subsystem water-sediment-primary producers was pointed out to be the most interesting part of the ecosystem for studying radionuclides with mathematical modelling in the future. (orig./DG)

  7. Forsmark site investigation. Programme for further investigations of geosphere and biosphere

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-01-01

    Since the beginning of 2002, SKB (the Swedish Nuclear Fuel and Waste Management Co) has been conducting a site investigation in Forsmark in the municipality of Oesthammar for siting of the deep repository for spent nuclear fuel. An equivalent investigation is also being conducted at Simpevarp and Laxemar in Oskarshamn Municipality. SKB's goal is to submit an application under the Environmental Code and the Nuclear Activities Act for siting of the deep repository at one of these sites by the end of 2008/beginning of 2009. When the application is submitted, everything of importance for the deep repository's safety, constructability and environmental impact shall have been investigated and analyzed. The investigations shall also provide data as a basis for selecting a site and configuring the facility to suit conditions on the site.SKB submitted a programme for the initial site investigation in Forsmark at the end of 2001. The investigations described there have now been completed. This report describes the programme that has now been prepared for the remainder of the site investigation. The points of departure are the general goals for the Deep Repository Project during the site investigation phase, the data needed for evaluation of the site, plus experience and results from the work to date. The programme has been prepared with the support of investigation data as of August 2004. The investigations described here will, as before, be conducted with great consideration given to residents, property owners and natural and cultural values so that they are not unnecessarily exposed to impact or disturbances. Just as before, the programme will be continuously adapted to the knowledge that is gradually accumulated on the site. All important changes will be reported to the authorities and other concerned parties. The investigations that have been conducted (as of August 2004) and their results can be summarized in the following points: The surface characterization

  8. Forsmark site investigation. Programme for further investigations of geosphere and biosphere

    International Nuclear Information System (INIS)

    2005-01-01

    Since the beginning of 2002, SKB (the Swedish Nuclear Fuel and Waste Management Co) has been conducting a site investigation in Forsmark in the municipality of Oesthammar for siting of the deep repository for spent nuclear fuel. An equivalent investigation is also being conducted at Simpevarp and Laxemar in Oskarshamn Municipality. SKB's goal is to submit an application under the Environmental Code and the Nuclear Activities Act for siting of the deep repository at one of these sites by the end of 2008/beginning of 2009. When the application is submitted, everything of importance for the deep repository's safety, constructability and environmental impact shall have been investigated and analyzed. The investigations shall also provide data as a basis for selecting a site and configuring the facility to suit conditions on the site.SKB submitted a programme for the initial site investigation in Forsmark at the end of 2001. The investigations described there have now been completed. This report describes the programme that has now been prepared for the remainder of the site investigation. The points of departure are the general goals for the Deep Repository Project during the site investigation phase, the data needed for evaluation of the site, plus experience and results from the work to date. The programme has been prepared with the support of investigation data as of August 2004. The investigations described here will, as before, be conducted with great consideration given to residents, property owners and natural and cultural values so that they are not unnecessarily exposed to impact or disturbances. Just as before, the programme will be continuously adapted to the knowledge that is gradually accumulated on the site. All important changes will be reported to the authorities and other concerned parties. The investigations that have been conducted (as of August 2004) and their results can be summarized in the following points: The surface characterization of the

  9. The Forsmark biotest basin. An instrument for environmental research. Experiences of large cooling water discharges in Sweden (1969-1993) and research perspectives for the future

    International Nuclear Information System (INIS)

    Snoeijs, P.

    1994-01-01

    This report presents the Biotest basin at Forsmark (Sweden) as an instrument for experimental environmental research, and indicates possibilities for its future use. the basin consists of a 1 km 2 artificial enclosure in the Baltic Sea that receives cooling water discharge from the Forsmark nuclear power plant. Cooling water discharge was initiated in 1980, and since then the basin has been serving as the main Swedish instrument for field studies on the effects of enhanced temperature and low-dose radioactivity on aquatic ecosystems. Environmental effects of large cooling water discharges from power plants to the sea have been studied at other sites in Sweden too, and for the sake of completeness of background information this report provides a survey and an extensive bibliography of all previous research on cooling water discharges in Sweden during the last 25 years. The aim of scientific research in the Biotest basin is to provide an independent academically-based assessment of the effects of the discharges of heat to the aquatic environment and of the pathways of pollutants through the ecosystems. Until now the research has mainly been describing the ecological effects of the cooling water flow through the basin under normal operation of the power plant. In the future it will be possible to manipulate the basin for large field experiments. An important perspective for the future is that of climatic change; the Forsmark Biotest basin provides excellent conditions for field studies on possible biological effects. This includes e.g. temperature effects on basic biological processes (growth, metabolism, reproduction etc.), population genetics, and combination effects of heat and toxic substances. 60 refs, 3 figs, 6 tabs

  10. Basis for applying for exemption according to species protection regulation. Final repository for spent nuclear fuel at Forsmark; Underlag till ansoekan om dispens enligt artskyddsfoerordningen. Slutfoervar foer anvaent kaernbraensle i Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    2011-02-15

    SKB will submit applications for permits and admissibility under the Environmental Act and under the Nuclear Activities Act to construct and operate a disposal facility for spent nuclear fuel at Forsmark. In the final repository the spent nuclear fuel from Swedish nuclear power plants is placed in order to protect human health and the environment against harmful effects of ionizing radiation. Construction and operation of the disposal facility in Forsmark will make an impact, give effects and consequences for the natural environment. Utilization of land for the construction of the facility and the impact on ground water as a result of groundwater drainage is expected to have negative consequences for the species included in species protection regulation. Thus, the planned activity require exemption from species protection regulation (SFS 2007:845). The purpose of this document is to provide a basis for an application for exemption under 14 paragraph species protection regulation from the prohibitions of 4, 6, 7 and 8 paragraph species protection regulation. A basis for the exemption application is that the proposed activity is considered to have an 'overriding public interest' prescribed in 14 paragraph species protection regulation. The document reports the impact, effects and consequences of the planned activities on species covered in the species protection regulation. The impact on protected species can be divided into two categories: - Direct effects on protected species and their habitats by utilization of the land. - Indirect effects on protected species and their habitats in the drainage of groundwater and the effect on groundwater levels. The document also includes a description of planned actions to prevent, restrict and compensate for the effects and consequences that the activity may cause. By applying for an exemption under 14 paragraph species protection regulation in a separate order from the application for permit according to chapters 9

  11. Basis for applying for exemption according to species protection regulation. Final repository for spent nuclear fuel at Forsmark; Underlag till ansoekan om dispens enligt artskyddsfoerordningen. Slutfoervar foer anvaent kaernbraensle i Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    2011-02-15

    SKB will submit applications for permits and admissibility under the Environmental Act and under the Nuclear Activities Act to construct and operate a disposal facility for spent nuclear fuel at Forsmark. In the final repository the spent nuclear fuel from Swedish nuclear power plants is placed in order to protect human health and the environment against harmful effects of ionizing radiation. Construction and operation of the disposal facility in Forsmark will make an impact, give effects and consequences for the natural environment. Utilization of land for the construction of the facility and the impact on ground water as a result of groundwater drainage is expected to have negative consequences for the species included in species protection regulation. Thus, the planned activity require exemption from species protection regulation (SFS 2007:845). The purpose of this document is to provide a basis for an application for exemption under 14 paragraph species protection regulation from the prohibitions of 4, 6, 7 and 8 paragraph species protection regulation. A basis for the exemption application is that the proposed activity is considered to have an 'overriding public interest' prescribed in 14 paragraph species protection regulation. The document reports the impact, effects and consequences of the planned activities on species covered in the species protection regulation. The impact on protected species can be divided into two categories: - Direct effects on protected species and their habitats by utilization of the land. - Indirect effects on protected species and their habitats in the drainage of groundwater and the effect on groundwater levels. The document also includes a description of planned actions to prevent, restrict and compensate for the effects and consequences that the activity may cause. By applying for an exemption under 14 paragraph species protection regulation in a separate order from the application for permit according to chapters 9 and 11

  12. SR-Site - hydrogeochemical evolution of the Forsmark site

    International Nuclear Information System (INIS)

    Salas, Joaquin; Molinero, Jorge; Juarez, Iker; Gimeno, Maria Jose; Auque, Luis; Gomez, Javier

    2010-12-01

    The present work has involved the development of a methodology in order to simulate the evolution of the groundwater composition within the candidate repository site of the Forsmark area. A series of climate periods is expected to be probable after the repository closure (temperate, periglacial and glacial) and, eventually, the area could be submerged under seawaters or under a lake of glacial melt waters. These environmental conditions will affect groundwater flow and composition around of the candidate repository volume. The present report summarizes the results obtained by the calculations which reproduce the hydrogeochemical evolution in the Forsmark area, and within the candidate repository volume. The hydrogeochemical evolution of groundwaters is one of the key factors affecting the chemical stability of the buffer and the canister. In this way, the main objective of the hydrogeochemical simulations is to assay the evolution of a series of safety assessment factors, such as salinity, redox potential, pH, and concentrations of iron, sulphide and potassium, among others. Using ConnectFlow, previous hydrological calculations have provided the transport of (1) the fractions of selected reference waters (Deep Saline, Old Meteoric, Glacial, Littorina and Altered Meteoric groundwaters), or (2) salinities, depending on the working team (Serco or Terrasolve). The results of the regional-scale groundwater flow modelling for each specific climate period are used as input of the geochemical models. Groundwater compositions have been modelled using PHREEQC, through mixing and chemical reactions between the waters obtained from the hydrogeological models and the reactive fracture-filling minerals. Both models (hydrological and geochemical) are not fully coupled, and it allows a description of the geochemical heterogeneity, which otherwise would be hard to attain. The stage of the open repository has been non-numerically analysed. Aspects as salinity, redox conditions

  13. SR-Site - hydrogeochemical evolution of the Forsmark site

    Energy Technology Data Exchange (ETDEWEB)

    Salas, Joaquin; Molinero, Jorge; Juarez, Iker (Amphos 21 (Spain)); Gimeno, Maria Jose; Auque, Luis; Gomez, Javier (Univ. of Zaragoza (Spain))

    2010-12-15

    The present work has involved the development of a methodology in order to simulate the evolution of the groundwater composition within the candidate repository site of the Forsmark area. A series of climate periods is expected to be probable after the repository closure (temperate, periglacial and glacial) and, eventually, the area could be submerged under seawaters or under a lake of glacial melt waters. These environmental conditions will affect groundwater flow and composition around of the candidate repository volume. The present report summarizes the results obtained by the calculations which reproduce the hydrogeochemical evolution in the Forsmark area, and within the candidate repository volume. The hydrogeochemical evolution of groundwaters is one of the key factors affecting the chemical stability of the buffer and the canister. In this way, the main objective of the hydrogeochemical simulations is to assay the evolution of a series of safety assessment factors, such as salinity, redox potential, pH, and concentrations of iron, sulphide and potassium, among others. Using ConnectFlow, previous hydrological calculations have provided the transport of (1) the fractions of selected reference waters (Deep Saline, Old Meteoric, Glacial, Littorina and Altered Meteoric groundwaters), or (2) salinities, depending on the working team (Serco or Terrasolve). The results of the regional-scale groundwater flow modelling for each specific climate period are used as input of the geochemical models. Groundwater compositions have been modelled using PHREEQC, through mixing and chemical reactions between the waters obtained from the hydrogeological models and the reactive fracture-filling minerals. Both models (hydrological and geochemical) are not fully coupled, and it allows a description of the geochemical heterogeneity, which otherwise would be hard to attain. The stage of the open repository has been non-numerically analysed. Aspects as salinity, redox conditions

  14. Decommissioning of a small reactor (BR3 reactor, Belgium)

    International Nuclear Information System (INIS)

    Dadoumont, J.; Massaut, V.; Klein, M.; Demeulemeester, Y.

    2002-01-01

    Since 1989, SCK-CEN has been dismantling its PWR reactor BR3 (Belgian Reactor No. 3). After gaining a great deal of experience in remote dismantling of highly radioactive components during the actual dismantling of the two sets of internals, the BR3 team completed the cutting of its reactor pressure vessel (RPV). During the feasibility phase of the RPV dismantling, a decision was made to cut it under water in the refuelling pool of the plant, after having removed it from its cavity. The RPV was cut into segments using a milling cutter and a bandsaw machine. These mechanical techniques have shown their ability for this kind of operations. Prior to the segmentation, the thermal insulation situated around the RPV was remotely removed and disposed of. The paper will describe all these operations. The BR3 decommissioning activities also include the dismantling of contaminated loops and equipment. After a careful sorting of the pieces, optimized management routes are selected in order to minimize the final amount of radioactive waste to be disposed of. Some development of different methods of decontamination were carried out: abrasive blasting (or sand blasting), chemical decontamination (Oxidizing-Reducing process using Cerium). The main goal of the decontamination program is to recycle most of the metallic materials either in the nuclear world or in the industrial world by reaching the respective recycling or clearance level. Overall the decommissioning of the BR3 reactor has shown the feasibility of performing such a project in a safe and economical way. Moreover, BR3 has developed methodologies and decontamination processes to economically reduce the amount of radwaste produced. (author)

  15. Report of comment to the Nuclear Power Inspectorate concerning the final waste repository at Forsmark (SFR)

    International Nuclear Information System (INIS)

    1983-04-01

    The institute gives its support to the construction of the final depository of low and medium level radioactive waste at Forsmark. The main outline has been presented by the Swedish Nuclear Fuel Supply Company in their application. Prior to putting into operation necessary instructions have to be issued and prior to closing the depository its impact on the environment is to be examined. (G.B.)

  16. The terrestrial ecosystems at Forsmark and Laxemar-Simpevarp. Site descriptive modelling SDM site

    Energy Technology Data Exchange (ETDEWEB)

    Loefgren, Anders [EcoAnalytica, Haegersten (Sweden); ed.

    2008-12-15

    This report describes the terrestrial ecosystems in the Forsmark and Laxemar-Simpevarp areas by summarizing ecological data and data from disciplines such as hydrology, quaternary geology and chemistry. The description therefore includes a number of different processes that drive element fluxes in the ecosystems, such as net primary production, heterotrophic respiration, transpiration, and horizontal transport from land to streams and lakes. Moreover, the human appropriation of the landscape is described with regard to land use and potential and actual utilization of food resources both today and in a historical perspective

  17. The terrestrial ecosystems at Forsmark and Laxemar-Simpevarp. Site descriptive modelling SDM site

    International Nuclear Information System (INIS)

    Loefgren, Anders

    2008-12-01

    This report describes the terrestrial ecosystems in the Forsmark and Laxemar-Simpevarp areas by summarizing ecological data and data from disciplines such as hydrology, quaternary geology and chemistry. The description therefore includes a number of different processes that drive element fluxes in the ecosystems, such as net primary production, heterotrophic respiration, transpiration, and horizontal transport from land to streams and lakes. Moreover, the human appropriation of the landscape is described with regard to land use and potential and actual utilization of food resources both today and in a historical perspective

  18. Summary of discrete fracture network modelling as applied to hydrogeology of the Forsmark and Laxemar sites

    International Nuclear Information System (INIS)

    Hartley, Lee; Roberts, David

    2013-04-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is responsible for the development of a deep geological repository for spent nuclear fuel. The permitting of such a repository is informed by assessment studies to estimate the risks of the disposal method. One of the potential risks involves the transport of radionuclides in groundwater from defective canisters in the repository to the accessible environment. The Swedish programme for geological disposal of spent nuclear fuel has involved undertaking detailed surface-based site characterisation studies at two different sites, Forsmark and Laxemar-Simpevarp. A key component of the hydrogeological modelling of these two sites has been the development of Discrete Fracture Network (DFN) concepts of groundwater flow through the fractures in the crystalline rocks present. A discrete fracture network model represents some of the characteristics of fractures explicitly, such as their, orientation, intensity, size, spatial distribution, shape and transmissivity. This report summarises how the discrete fracture network methodology has been applied to model groundwater flow and transport at Forsmark and Laxemar. The account has involved summarising reports previously published by SKB between 2001 and 2011. The report describes the conceptual framework and assumptions used in interpreting site data, and in particular how data has been used to calibrate the various parameters that define the discrete fracture network representation of bedrock hydrogeology against borehole geologic and hydraulic data. Steps taken to confirm whether the developed discrete fracture network models provide a description of regional-scale groundwater flow and solute transport consistent with wider hydraulic tests hydrochemical data from Forsmark and Laxemar are discussed. It illustrates the use of derived hydrogeological DFN models in the simulations of the temperate period hydrogeology that provided input to radionuclide transport

  19. Summary of discrete fracture network modelling as applied to hydrogeology of the Forsmark and Laxemar sites

    Energy Technology Data Exchange (ETDEWEB)

    Hartley, Lee; Roberts, David

    2013-04-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is responsible for the development of a deep geological repository for spent nuclear fuel. The permitting of such a repository is informed by assessment studies to estimate the risks of the disposal method. One of the potential risks involves the transport of radionuclides in groundwater from defective canisters in the repository to the accessible environment. The Swedish programme for geological disposal of spent nuclear fuel has involved undertaking detailed surface-based site characterisation studies at two different sites, Forsmark and Laxemar-Simpevarp. A key component of the hydrogeological modelling of these two sites has been the development of Discrete Fracture Network (DFN) concepts of groundwater flow through the fractures in the crystalline rocks present. A discrete fracture network model represents some of the characteristics of fractures explicitly, such as their, orientation, intensity, size, spatial distribution, shape and transmissivity. This report summarises how the discrete fracture network methodology has been applied to model groundwater flow and transport at Forsmark and Laxemar. The account has involved summarising reports previously published by SKB between 2001 and 2011. The report describes the conceptual framework and assumptions used in interpreting site data, and in particular how data has been used to calibrate the various parameters that define the discrete fracture network representation of bedrock hydrogeology against borehole geologic and hydraulic data. Steps taken to confirm whether the developed discrete fracture network models provide a description of regional-scale groundwater flow and solute transport consistent with wider hydraulic tests hydrochemical data from Forsmark and Laxemar are discussed. It illustrates the use of derived hydrogeological DFN models in the simulations of the temperate period hydrogeology that provided input to radionuclide transport

  20. Characteristics and ontogeny of oligotrophic hardwater lakes in the Forsmark area, central Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Brunberg, A.K.; Blomqvist, P. [Uppsala Univ. (Sweden). Dept. of Limnology

    1999-12-01

    This is the first part of a report characterising the lakes of Uppsala county, with special emphasis on the coastal lakes in the Forsmark area.The aim of the study is to characterise different main types of lakes within the Forsmark area and to create a basis for prediction of their ontogeny, that can be used also for new lakes which due to shoreline displacement will be formed during the next 10 000 years. Areas where future research is needed to fully understand the functioning of the lake ecosystems and their ontogeny should also be identified. This first part of the study identifies and describes one of the most common lake types in the area, the oligotrophic hardwater lake. The geology in the catchments of the Forsmark area includes a bedrock dominated by granites and gneisses, covered by calcareous glacial till and postglacial clay. The catchments are dominated by forest, and the oligotrophic hardwater lakes are to a large extent surrounded by mires. Inflow as well as outflow of water is often diffuse, via the surrounding mire. The lakes are small and shallow, with nutrient poor and highly alkaline water. Three key habitats have been identified within the lakes; the pelagic zone, characterised by low production of biota;, the presumably moderately productive emergent macrophyte zone, dominated by Sphagnum and Phragmites;, and the light exposed soft-bottom zone with Chara meadows and an unusually rich and presumably highly productive microbial sediment community. The oligotrophic hardwater lakes have their origin as depressions in the bottom of the Baltic Sea, which are successively transported upwards due to the land-rise process in the area. As the basins are isolated from the sea , a gradual change from a brackish to freshwater conditions occur. When the lakes have become completely isolated, the oligotrophic hardwater stage follows, due to inflow of carbonate-rich and well buffered groundwater. In the next successional stage, Sphagnum mosses start to

  1. Characteristics and ontogeny of oligotrophic hardwater lakes in the Forsmark area, central Sweden

    International Nuclear Information System (INIS)

    Brunberg, A.K.; Blomqvist, P.

    1999-12-01

    This is the first part of a report characterising the lakes of Uppsala county, with special emphasis on the coastal lakes in the Forsmark area.The aim of the study is to characterise different main types of lakes within the Forsmark area and to create a basis for prediction of their ontogeny, that can be used also for new lakes which due to shoreline displacement will be formed during the next 10 000 years. Areas where future research is needed to fully understand the functioning of the lake ecosystems and their ontogeny should also be identified. This first part of the study identifies and describes one of the most common lake types in the area, the oligotrophic hardwater lake. The geology in the catchments of the Forsmark area includes a bedrock dominated by granites and gneisses, covered by calcareous glacial till and postglacial clay. The catchments are dominated by forest, and the oligotrophic hardwater lakes are to a large extent surrounded by mires. Inflow as well as outflow of water is often diffuse, via the surrounding mire. The lakes are small and shallow, with nutrient poor and highly alkaline water. Three key habitats have been identified within the lakes; the pelagic zone, characterised by low production of biota;, the presumably moderately productive emergent macrophyte zone, dominated by Sphagnum and Phragmites;, and the light exposed soft-bottom zone with Chara meadows and an unusually rich and presumably highly productive microbial sediment community. The oligotrophic hardwater lakes have their origin as depressions in the bottom of the Baltic Sea, which are successively transported upwards due to the land-rise process in the area. As the basins are isolated from the sea , a gradual change from a brackish to freshwater conditions occur. When the lakes have become completely isolated, the oligotrophic hardwater stage follows, due to inflow of carbonate-rich and well buffered groundwater. In the next successional stage, Sphagnum mosses start to

  2. Solid/liquid partition coefficients (Kd) for selected soils and sediments at Forsmark and Laxemar-Simpevarp

    Energy Technology Data Exchange (ETDEWEB)

    Sheppard, Steve; Long, Jeff; Sanipelli, Barb [ECOMatters Inc., Pinawa (Canada); Sohlenius, Gustav [Geological Survey of Sweden (SGU), Uppsala (Sweden)

    2009-03-15

    Soil and sediment solid/liquid partition coefficients (Kd) are used to indicate the relative mobility of radionuclides and elements of concern from nuclear fuel waste, as well as from other sources. The Kd data are inherently extremely variable, but also vary systematically with key environmental attributes. For soil Kd, the key variables are pH, clay content and organic carbon content. For sediment Kd, water type (freshwater versus marine) and sediment type (benthic versus suspended) are important. This report summarized Kd data for soils and sediments computed from indigenous stable element concentrations measured at the Forsmark and Laxemar-Simpevarp sites. These were then compared to several literature sources of Kd data for Ce, Cl, Co, Cr, Cs, Fe, Ho, I, La, Mn, Mo, Nb, Nd, Ni, Np, Pa, Pb, Pu, Ra, Sb, Se, Sm, Sn, Sr, Tc, Th, Tm, U and Yb. The Kd data computed from indigenous stable element concentrations may be especially relevant for assessment of long-lived radionuclides from deep disposal of waste, because the long time frame for the potential releases is more consistent with the steady state measured using indigenous stable elements. For almost every one of these elements in soils, a statistically meaningful regression equation was developed to allow estimation of Kd for any soil given a modest amount of information about the soil. Nonetheless, the median residual geometric standard deviation (GSD) was 4.3-fold, implying confidence bounds of about 18-fold above and below the best estimate Kd. For sediment, the values are categorised simply by water type and sediment type. The median GSD for sediment Kd as measured at the Forsmark and Laxemar-Simpevarp sites was 2.5-fold, but the median GSD among literature values was as high as 8.6-fold. Clearly, there remains considerable uncertainty in Kd values, and it is important to account for this in assessment applications

  3. Solid/liquid partition coefficients (Kd) for selected soils and sediments at Forsmark and Laxemar-Simpevarp

    International Nuclear Information System (INIS)

    Sheppard, Steve; Long, Jeff; Sanipelli, Barb; Sohlenius, Gustav

    2009-03-01

    Soil and sediment solid/liquid partition coefficients (Kd) are used to indicate the relative mobility of radionuclides and elements of concern from nuclear fuel waste, as well as from other sources. The Kd data are inherently extremely variable, but also vary systematically with key environmental attributes. For soil Kd, the key variables are pH, clay content and organic carbon content. For sediment Kd, water type (freshwater versus marine) and sediment type (benthic versus suspended) are important. This report summarized Kd data for soils and sediments computed from indigenous stable element concentrations measured at the Forsmark and Laxemar-Simpevarp sites. These were then compared to several literature sources of Kd data for Ce, Cl, Co, Cr, Cs, Fe, Ho, I, La, Mn, Mo, Nb, Nd, Ni, Np, Pa, Pb, Pu, Ra, Sb, Se, Sm, Sn, Sr, Tc, Th, Tm, U and Yb. The Kd data computed from indigenous stable element concentrations may be especially relevant for assessment of long-lived radionuclides from deep disposal of waste, because the long time frame for the potential releases is more consistent with the steady state measured using indigenous stable elements. For almost every one of these elements in soils, a statistically meaningful regression equation was developed to allow estimation of Kd for any soil given a modest amount of information about the soil. Nonetheless, the median residual geometric standard deviation (GSD) was 4.3-fold, implying confidence bounds of about 18-fold above and below the best estimate Kd. For sediment, the values are categorised simply by water type and sediment type. The median GSD for sediment Kd as measured at the Forsmark and Laxemar-Simpevarp sites was 2.5-fold, but the median GSD among literature values was as high as 8.6-fold. Clearly, there remains considerable uncertainty in Kd values, and it is important to account for this in assessment applications

  4. Solute transport in coupled inland-coastal water systems. General conceptualisation and application to Forsmark

    International Nuclear Information System (INIS)

    Jarsjoe, Jerker; Destouni, Georgia; Persson, Klas; Prieto, Carmen

    2007-12-01

    We formulate a general theoretical conceptualisation of solute transport from inland sources to downstream recipients, considering main recipient load contributions from all different nutrient and pollutant sources that may exist within any catchment. Since the conceptualisation is model independent, its main hydrological factors and mass delivery factors can be quantified on the basis of inputs to and outputs from any considered analytical or numerical model. Some of the conceptually considered source contribution and transport pathway combinations are however commonly neglected in catchment-scale solute transport and attenuation modelling, in particular those related to subsurface sources, diffuse sources at the land surface and direct groundwater transport into the recipient. The conceptual framework provides a possible tool for clarification of underlying and often implicit model assumptions, which can be useful for e.g. inter-model comparisons. In order to further clarify and explain research questions that may be of particular importance for transport pathways from deep groundwater surrounding a repository, we concretise and interpret some selected transport scenarios for model conditions in the Forsmark area. Possible uncertainties in coastal discharge predictions, related to uncertain spatial variation of evapotranspiration within the catchment, were shown to be small for the relatively large, focused surface water discharges from land to sea, because local differences were averaged out along the length of the main water flow paths. In contrast, local flux values within the diffuse groundwater flow field from land to sea are more uncertain, although estimates of mean values and total sums of submarine groundwater discharge (SGD) along some considerable coastline length may be robust. The present results show that 80% to 90% of the total coastal discharge of Forsmark occurred through focused flows in visible streams, whereas the remaining 10% to 20% was

  5. Mineralogy, geochemistry, porosity and redox properties of rocks from Forsmark. Compilation of data from the regional model volume for SR-Site

    Energy Technology Data Exchange (ETDEWEB)

    Sandstroem, Bjoern (WSP Sverige AB, Stockholm (Sweden)); Stephens, Michael B. (Geological Survey of Sweden, Uppsala (Sweden))

    2009-11-15

    This report is a compilation of the data acquired during the Forsmark site investigation programme on the mineralogy, geochemistry, redox properties and porosity of different rock types at Forsmark. The aim is to provide a final summary of the available data for use during the SR-Site modelling work. Data presented in this report represent the regional model volume and have previously been published in various SKB reports. The data have been extracted from the SKB database Sicada and are presented as calculated median values, data range and lower/upper quartile. The representativity of all samples used for the calculations have been evaluated and data from samples where there is insufficient control on the rock type have been omitted. Rock samples affected by alteration have been omitted from the unaltered samples and are presented separately based on type of alteration (e.g. oxidised or albitized rock)

  6. Integral test of JENDL-3.3 for fast reactors

    International Nuclear Information System (INIS)

    Chiba, Gou

    2003-01-01

    An integral test of JENDL-3.3 was performed for fast reactors. Various types of fast reactors were analyzed. Calculation values of the nuclear characteristics were greatly especially affected by the revisions of the cross sections of U-235 capture and elastic scattering reactions. The C/E values were improved for ZPPR cross where plutonium is mainly fueled, but not for BFS cores where uranium is mainly fueled. (author)

  7. A coupled regolith-lake development model applied to the Forsmark site

    Energy Technology Data Exchange (ETDEWEB)

    Brydsten, Lars; Stroemgren, Maarten (Umeaa Univ., Umeaa (Sweden))

    2010-11-15

    The Quaternary geology at the Forsmark site has been characterized using both a map of Quaternary deposits and a regolith depth model (RDM) that show the stratigraphy and thickness of different deposits. Regolith refers to all the unconsolidated deposits overlying the bedrock. The surface geology and regolith depth are important parameters for hydrogeological and geochemical modelling and for the overall understanding of the area. The safety assessment analysis should focus on processes involved during a period of 120,000 years, which includes a full glacial cycle; however, the investigations within the site description model do not cover the temporal change of the regolith, a limitation that does not fulfil the requirements for the safety assessment. To this end, this study constructs a model that can predict the surface geology, stratigraphy, and thickness of different strata at any time during a glacial cycle and applies this model to the Forsmark site. The Weichselian ice sheet covered the study area until around 9500 BC. The deglaciation revealed a marine landscape with bedrock, till and glacial clay. For the safety assessment, the most important unconsolidated strata are clay or silt: these small grains can bind nuclear elements more easily than coarser sediment particles. Thick layers of clay can be found where post-glacial clay settled on top of glacial clay, especially where the middle-aged erosion of postglacial clay is missing and where there is an uninterrupted sequence of accumulation of finegrained particles. Such areas could be found in deep marine basins that later become lakes when raised into a supra-marine position. The coupled regolith-lake development model (RLDM) predicts the course of events described above during an interglacial, especially the dynamics of the clay and silt particles. The RLDM is divided into two modules: a marine module that predicts the sediment dynamics caused by wind waves and a lake module that predicts the lake infill

  8. A coupled regolith-lake development model applied to the Forsmark site

    International Nuclear Information System (INIS)

    Brydsten, Lars; Stroemgren, Maarten

    2010-11-01

    The Quaternary geology at the Forsmark site has been characterized using both a map of Quaternary deposits and a regolith depth model (RDM) that show the stratigraphy and thickness of different deposits. Regolith refers to all the unconsolidated deposits overlying the bedrock. The surface geology and regolith depth are important parameters for hydrogeological and geochemical modelling and for the overall understanding of the area. The safety assessment analysis should focus on processes involved during a period of 120,000 years, which includes a full glacial cycle; however, the investigations within the site description model do not cover the temporal change of the regolith, a limitation that does not fulfil the requirements for the safety assessment. To this end, this study constructs a model that can predict the surface geology, stratigraphy, and thickness of different strata at any time during a glacial cycle and applies this model to the Forsmark site. The Weichselian ice sheet covered the study area until around 9500 BC. The deglaciation revealed a marine landscape with bedrock, till and glacial clay. For the safety assessment, the most important unconsolidated strata are clay or silt: these small grains can bind nuclear elements more easily than coarser sediment particles. Thick layers of clay can be found where post-glacial clay settled on top of glacial clay, especially where the middle-aged erosion of postglacial clay is missing and where there is an uninterrupted sequence of accumulation of finegrained particles. Such areas could be found in deep marine basins that later become lakes when raised into a supra-marine position. The coupled regolith-lake development model (RLDM) predicts the course of events described above during an interglacial, especially the dynamics of the clay and silt particles. The RLDM is divided into two modules: a marine module that predicts the sediment dynamics caused by wind waves and a lake module that predicts the lake infill

  9. Surveys of mammal populations in the areas adjacent to Forsmark and Tierp. A pilot study 2001-2002

    Energy Technology Data Exchange (ETDEWEB)

    Cederlund, Goeran; Hammarstroem, Angelica; Wallin, Kjell [Svensk Viltfoervaltning AB, Ramsberg (Sweden)

    2003-04-01

    larger ditches. The methods have been evaluated and should all be used next year with minor changes. Some of the basic data presented in the report are as follows: Moose were unevenly distributed in a 480/km{sup 2} area along the coast (mean density 7.2 moose/10 km{sup 2} ). No red deer was fund while roe deer density varied between 13 deer/10 km{sup 2} (Tierp) and 59 deer/10 km{sup 2} (Forsmark). Hare density in the fields were between 2.5 hares/10 km{sup 2} (Control area) and 3.4 hares/10 km{sup 2} (Tierp) while in the forest density varied between 0.2 hares/10 km{sup 2} (Tierp) and 4.4 hares/10 km{sup 2} (Forsmark) Red listed species like wolf and otter are present in the areas, although in low numbers. No wolf tracks were found, but a few individuals were observed elsewhere in the region during the winter. As indicated by track indexes, red fox and marten are common predators in all three areas. Lynx is present, but at low numbers (0.2 lynx/10 km{sup 2} ). Occasional tracks of wild boar were found in the transects. Based on the results from this pilot study, we suggest some modification of the methods and additional methods for density estimates (for example using capture-recapture techniques of fox and badger)

  10. Surveys of mammal populations in the areas adjacent to Forsmark and Tierp. A pilot study 2001-2002

    International Nuclear Information System (INIS)

    Cederlund, Goeran; Hammarstroem, Angelica; Wallin, Kjell

    2003-04-01

    larger ditches. The methods have been evaluated and should all be used next year with minor changes. Some of the basic data presented in the report are as follows: Moose were unevenly distributed in a 480/km 2 area along the coast (mean density 7.2 moose/10 km 2 ). No red deer was fund while roe deer density varied between 13 deer/10 km 2 (Tierp) and 59 deer/10 km 2 (Forsmark). Hare density in the fields were between 2.5 hares/10 km 2 (Control area) and 3.4 hares/10 km 2 (Tierp) while in the forest density varied between 0.2 hares/10 km 2 (Tierp) and 4.4 hares/10 km 2 (Forsmark) Red listed species like wolf and otter are present in the areas, although in low numbers. No wolf tracks were found, but a few individuals were observed elsewhere in the region during the winter. As indicated by track indexes, red fox and marten are common predators in all three areas. Lynx is present, but at low numbers (0.2 lynx/10 km 2 ). Occasional tracks of wild boar were found in the transects. Based on the results from this pilot study, we suggest some modification of the methods and additional methods for density estimates (for example using capture-recapture techniques of fox and badger)

  11. Forsmark site characterisation - Borehole KFM22 and KFM23: Derivation of porewater data by diffusion experiments

    Energy Technology Data Exchange (ETDEWEB)

    Waber, H. N. [Rock Water Interaction, University of Bern, Bern (Switzerland); Smellie, J. A. T. [Conterra AB, Partille (Sweden)

    2012-04-15

    Within the Detum Project (Detailed Investigations in Forsmark) a 'Methodology comparison for porewater extraction and characterisation techniques' was initiated. This has centred on two shallow boreholes drilled at Soederviken within the northern part of the Forsmark characterisation site. The comparison includes different methodologies to characterise the chemical and isotopic composition of porewater residing in the connected pore space of the rock matrix. The present report describes the chemical and isotopic information of the porewater obtained by out-diffusion experiments and the diffusive isotope equilibration technique applied to originally water saturated drillcore samples. In addition, petrophysical data and solute transport properties of the rock matrix, all necessary for porewater characterisation, have also been elaborated. Specially conditioned drillcore samples were obtained from depths of less than 100 m from boreholes KFM22 and KFM23. Porewater has been extracted successfully from seven samples by laboratory out-diffusion and diffusive isotope exchange methods. The methodology to extract and analyse the porewater is outlined and the analytical data are tabulated. The data are critically reviewed for potential experimental artefacts and their significance with respect to in situ conditions. The connected pore space in the core material representing borehole KFM22 and KFM23 was measured on different types of originally saturated drillcore samples using gravimetric and isotope mass balance methods. Out-diffusion experiments were performed on kg-sized drillcore samples to derive the in situ concentration of the chemically conservative compounds chloride and bromide. The attainment of equilibrium conditions in the out-diffusion experiments was monitored by the concentration change of chloride and bromide as a function of time. The water isotope composition of porewater was determined by the diffusive isotope equilibration technique and by

  12. BWR-stability investigation at Forsmark 1

    International Nuclear Information System (INIS)

    Bergdahl, B.G.; Reisch, F.; Oguma, R.; Lorenzen, J.; Aakerhielm, F.

    1988-01-01

    A series of noise measurements have been conducted at Forsmark 1 during start-up operation after the revision summer '87. The main purpose was to investigate BWR-stability problems, i.e. resonant power oscillations of 0.5 Hz around 65% power and 4100 kg/s core flow, which tend to arise at high power and low core flow conditions. The analysis was performed to estimate the noise source which gives rise to the oscillation, to evaluate the measure of stability, i.e. the Decay Ratio (Dr) as well as to investigate other safety related problems. The result indicates that the oscillation is due to the dynamic coupling between the neutron kinetics and thermal hydraulics via void reactivity feedback. The Dr ranged between values of 0.7 and > 0.9, instead of expected 0.6 (Dr=1 is defined as instability). These high values imply that the core cannot suppress oscillations fast enough and a small perturbation can cause scram. Further it was found that the entire core is oscillating in phase (LPRM's) with varying strength where any connection to the consequences of different fuel (8x8, 9x9) being present simultaneously cannot be excluded. This report elucidates the importance of an on-line BWR-stability surveillance system with functions like stability condition monitoring and control system diagnosis. (orig.)

  13. Description of climate, surface hydrology, and near-surface hydrogeology. Preliminary site description. Forsmark area - version 1.2

    International Nuclear Information System (INIS)

    Johansson, Per-Olof; Werner, Kent; Bosson, Emma; Berglund, Sten; Juston, John

    2005-06-01

    The present report is a background report describing the meteorological conditions and the modelling of surface hydrology and near-surface hydrogeology in support of the Forsmark version 1.2 SDM based on the data available in the Forsmark 1.2 ''data freeze'' (July 31, 2004). The area covered in the conceptual and descriptive modelling is characterised by a low relief and a small-scale topography. Almost the whole area is located below 20 m a s l (metres above sea level). The corrected mean annual precipitation is 600-650 mm and the mean annual evapotranspiration can be estimated to a little more than 400 mm, leaving approximately 200 mm x year-1 for runoff. Till is the dominating Quaternary deposit covering approximately 75% of the area. In most of the area, the till is sandy. Bedrock outcrops are frequent but cover only approximately 5% of the area. Direct groundwater recharge from precipitation is the dominant source of groundwater recharge. The small-scale topography implies that many local, shallow groundwater flow systems are formed in the Quaternary deposits, overlaying more large-scale flow systems associated with groundwater flows at greater depths. Groundwater level time series from wells in till and bedrock within the same areas show a considerably higher groundwater level in the till than in the bedrock. The sediment stratigraphy of lakes and wetlands is crucial for their function as discharge areas for groundwater. Comparisons between measured lake water levels and groundwater levels below and around lakes indicate that the lakes in some cases may act as sources of groundwater recharge. Specifically, observations from Lake Bolundsfjaerden and Lake Eckarfjaerden show that such conditions were at hand during the dry summer of 2003. However, whether the observed water level relations correspond to significant water fluxes depends also on the hydrogeological properties of the lake sediments and the underlying Quaternary deposits. ''Old'' water with high

  14. Water Activities in Forsmark (Part I). Removal of groundwater from final repository for spent fuel; Vattenverksamhet i Forsmark (del I). Bortledande av grundvatten fraan slutfoervarsanlaeggningen foer anvaent kaernbraensle

    Energy Technology Data Exchange (ETDEWEB)

    Werner, Kent [EmpTec (Sweden); Hamren, Ulrika; Collinder, Per [Ekologigruppen AB (Sweden)

    2010-12-15

    The construction, operation and decommissioning of the repository for spent nuclear fuel in Forsmark are associated with a number of measures that constitute water operations according to Chapter 11 in the Environmental Code. This report is an appendix to the Environmental Impact Assessment (EIA) and describes water operations in the form of groundwater diversion from the repository (the report is also included in the permit application according to the Nuclear Activities Act). The main objective of the report is to describe hydrogeological and hydrological effects and the consequences that may arise in the surroundings of the repository due to the groundwater diversion. Moreover, the report presents prevention measures to reduce the effects of the groundwater diversion and mitigation measures that aim at its consequences

  15. BIM som Informationsbärare in i Förvaltningen : En studie vid Forsmarks Kraftgrupp

    OpenAIRE

    Svens, Therése

    2013-01-01

    BIM, Building Information Modeling, börjar vinna mark inom byggbranschen i Sverige och är en vedertagen process i vart och vartannat byggprojekt. Forsmarks Kraftgrupp står inför både upprustningar av sina anläggningar och nyproduktion av bland annat kontor, verkstad och hotell. BIM framstår nu som en lukrativ metod för att dra ner på projektkostnaderna, men även för att få ytterligare ordning och struktur på den enorma mängd dokumentation som ackumulerat under de dryga trettio åren av drift. ...

  16. A preliminary carbon budget for two oligotrophic hardwater lakes in the Forsmark area, Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Nilsson, Eva [Uppsala Univ. (Sweden). Dept. of Limnology

    2001-06-01

    The Swedish Nuclear Fuel and Waste Management Co (SKB) is responsible for management and disposal of Swedish radioactive waste. The company is planning to construct repositories that will keep radioactive waste away from humans for hundreds of thousands of years. In a safety assessment of the repositories hypothetical releases are used to evaluate the robustness of the repositories. It is important to know how the radioactive nuclides would react if they were released and by which way they could enter the living biota. SFR are responsible for the disposal of low radioactive waste and close to the nuclear plant in Forsmark there is a storage for low radioactive waste. At the moment this storage is located in the bedrock far below the sea level but due to land-rise in the area it will in the future be located above sea level. Hence, it is of importance to know how the surface ecosystems in the area are functioning. A carbon budget for the aquatic ecosystem above SFR in Oeresundsgrepen exist, but it is also important to have a carbon budget for the surface systems in the Forsmark area since SFR in the future will be situated above sea level. Carbon budgets can be used to get a picture of how an ecosystem functions. The carbon flow shows how carbon is transported through a food web from lower trophic levels, e.g. plants and bacteria to higher trophic levels such as fish. Oligotrophic hardwater lakes are the most important lakes in the Forsmark area. This report aims to give a picture of a potential flow of carbon through the ecosystem in two oligotrophic hard-water lakes, Lake Haellefjaerd and Lake Eckarfjaerden. Macrophyte, mainly Chara, were calculated to make up the largest part of the biomass and production in both lakes. Benthic bacteria and microphytobenthos (benthic photosynthesising microorganisms) were other large contributors to the production. Benthic bacteria were found responsible for a major part of respiration and, hence, consumption of carbon in the

  17. A preliminary carbon budget for two oligotrophic hardwater lakes in the Forsmark area, Sweden

    International Nuclear Information System (INIS)

    Nilsson, Eva

    2001-06-01

    The Swedish Nuclear Fuel and Waste Management Co (SKB) is responsible for management and disposal of Swedish radioactive waste. The company is planning to construct repositories that will keep radioactive waste away from humans for hundreds of thousands of years. In a safety assessment of the repositories hypothetical releases are used to evaluate the robustness of the repositories. It is important to know how the radioactive nuclides would react if they were released and by which way they could enter the living biota. SFR are responsible for the disposal of low radioactive waste and close to the nuclear plant in Forsmark there is a storage for low radioactive waste. At the moment this storage is located in the bedrock far below the sea level but due to land-rise in the area it will in the future be located above sea level. Hence, it is of importance to know how the surface ecosystems in the area are functioning. A carbon budget for the aquatic ecosystem above SFR in Oeresundsgrepen exist, but it is also important to have a carbon budget for the surface systems in the Forsmark area since SFR in the future will be situated above sea level. Carbon budgets can be used to get a picture of how an ecosystem functions. The carbon flow shows how carbon is transported through a food web from lower trophic levels, e.g. plants and bacteria to higher trophic levels such as fish. Oligotrophic hardwater lakes are the most important lakes in the Forsmark area. This report aims to give a picture of a potential flow of carbon through the ecosystem in two oligotrophic hard-water lakes, Lake Haellefjaerd and Lake Eckarfjaerden. Macrophyte, mainly Chara, were calculated to make up the largest part of the biomass and production in both lakes. Benthic bacteria and microphytobenthos (benthic photosynthesising microorganisms) were other large contributors to the production. Benthic bacteria were found responsible for a major part of respiration and, hence, consumption of carbon in the

  18. Dynamics of TRIGA-3 Salazar Reactor.; Dinamica del Reactor TRIGA Mark III del Centro Nuclear de Mexico.

    Energy Technology Data Exchange (ETDEWEB)

    Gallardo S, L F

    1991-12-31

    The theoretical study of temporal behavior of a nuclear reactor is of great importance, since it allows to know, in advance, the conditions to which a reactor is going to be submitted. The reliability of two computer codes (AIREK-JEN and PLANKIN) designed to reproduce the temporal behavior of nuclear reactors, generally power reactors, when they are applied to reproduce the dynamic behavior of TRIGA-3 Salazar Reactor is analyzed. In the first chapters, the fundamental equations that solve this computer codes are deduced, and also the main characteristics of TRIGA-3 Salazar Reactor and the necessary data to run the programs are presented; later the results obtained with the computer codes and the experimental results reported in the operational logbook of the reactor are compared, with the result that such computer codes are applicable to the temporal study of TRIGA-3 Salazar Reactor. (Author).

  19. 3D CAD model of the subcritical nuclear reactor of IPN; Modelo CAD 3D del reactor nuclear subcritico del IPN

    Energy Technology Data Exchange (ETDEWEB)

    Pahuamba V, F. de J.; Delfin L, A.; Gomez T, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Ibarra R, G.; Del Valle G, E.; Sanchez R, A., E-mail: narehc@hotmail.com [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN, Edif. 9, Unidad Profesional Adolfo Lopez Mateos, San Pedro Zacatenco, 07738 Ciudad de Mexico (Mexico)

    2016-09-15

    The three-dimensional (3D) CAD model of the subcritical reactor Chicago model 9000 of Instituto Politecnico Nacional (IPN) allows obtaining a 3D view with the dimensions of each of its components, such as: natural uranium cylindrical rods, fuel elements, hexagonal reactor core arrangement, cylindrical stainless steel tank containing the core, fuel element support grids and reactor water cleaning system. As a starting point for the development of the model, the Chicago model 9000 subcritical reactor manual provided by the manufacturer was used, the measurement and verification of the components to adapt the geometric, physical and mechanical characteristics was carried out and materials standards were used to obtain a design that allows to elaborate a new manual according to the specifications. In addition, the 3D models of the building of the Advanced Physics Laboratory, neutron generator, cobalt source and the corridors connecting to the subcritical reactor facility were developed, allowing an animated ride, developed by computer-aided design software. The manual provided by the company Nuclear Chicago, dates from the year 1959 and presents diverse deviations in the design and dimensions of the reactor components. The model developed; in addition to supporting the development of the new manual represents a learning tool to visualize the reactor components. (Author)

  20. Direct harvesting of Helium-3 (3He) from heavy water nuclear reactors

    International Nuclear Information System (INIS)

    Bentoumi, G.; Didsbury, R.; Jonkmans, G.; Rodrigo, L.; Sur, B.

    2013-01-01

    The thermal neutron activation of deuterium inside a heavy-water-moderated or -cooled nuclear reactor produces a build-up of tritium in the heavy water. The in situ decay of tritium can, for certain reactor types and operating conditions, produce potentially useable amounts of 3 He, which can be directly extracted via the heavy-water cover gas without first separating, collecting and storing tritium outside the reactor. It is estimated that the amount of 3 He available for recovery from the moderator cover gas of a 700 MWe class Pressurized Heavy Water Reactor (PHWR) ranges from 0.1 to 0.7 m 3 (STP) per annum, varying with the tritium activity buildup in the moderator. The harvesting of 3 He would generate approximately 12.7 m 3 (STP) of 3 He, worth more than $30M at current market rates, over a typical 25-year operating cycle of the PHWR. This paper discusses the production of 3 He in the moderator of a PHWR and its extraction from the 4 He moderator cover gas system using conventional methods. (author)

  1. D-3He fuel cycles for neutron lean reactors

    International Nuclear Information System (INIS)

    Kernbichler, W.; Miley, G.H.; Heindler, M.

    1989-01-01

    The intrinsic potential of D-3He as a reactor fuel is investigated for a large range of 3He to D density ratios. A steady-state zero-dimensional reactor model is developed in which much care is attributed to a proper treatment of fast fusion products. Useful ranges of reactor parameters as well as temperature-density windows for driven and ignited operation are identified. Various figures of merit are calculated, such as power densities, net power production, neutron production, tritium load and radiative power. These results suggest several optimistic conclusions about the performance of D-3He as a reactor fuel

  2. Forsmark site investigation. Hydrochemical investigations in four calciferous lakes in the Forsmark area. Results from the second year of a complementary investigation in the Forsmark area

    International Nuclear Information System (INIS)

    Qvarfordt, Susanne; Borgiel, Micke; Berg, Cecilia

    2011-12-01

    The present report documents the results from the second year of hydrochemical investigations in four small, calciferous lakes in the Forsmark area in order to study the lake water compositions. The construction of a permanent storage facility for used nuclear fuel may result in a lowering of the ground water level and also lake surface water levels. Restoration of habitats by adding water may be an option to reduce possible negative consequences induced by a lower water level on biodiversity and valuable species. Thus, knowledge of the water composition is needed. This report presents the results from six sampling occasions during January to December 2010. The results from the sampling of the four lakes includes field measurements of redox potential (ORP), pH, dissolved oxygen, electrical conductivity, salinity, depth, atmospheric pressure, turbidity, chlorophyll and water temperature, as well as chemical analyses of major constituents and nutrient salts. The four investigated small lakes are well buffered with high alkalinity, high pH and high calcium concentrations. This is in accordance with results from the ongoing monitoring programme of lakes and streams in the area and with the results from the previous sampling period (2008-2009). The results show both seasonal and inter-annual variation in the analysed parameters. This can be explained by seasonal changes and annual differences in temperature, ice-cover, precipitation etc and lake specific parameters such as lake size and drainage area. The variation highlights the importance of both year round sampling and continued sampling for several years when discussing the water composition

  3. Forsmark site investigation. Hydrochemical investigations in four calciferous lakes in the Forsmark area. Results from the second year of a complementary investigation in the Forsmark area

    Energy Technology Data Exchange (ETDEWEB)

    Qvarfordt, Susanne; Borgiel, Micke [Sveriges Vattenekologer AB, Vingaaker (Sweden); Berg, Cecilia [Geosigma AB, Uppsala (Sweden)

    2011-12-15

    The present report documents the results from the second year of hydrochemical investigations in four small, calciferous lakes in the Forsmark area in order to study the lake water compositions. The construction of a permanent storage facility for used nuclear fuel may result in a lowering of the ground water level and also lake surface water levels. Restoration of habitats by adding water may be an option to reduce possible negative consequences induced by a lower water level on biodiversity and valuable species. Thus, knowledge of the water composition is needed. This report presents the results from six sampling occasions during January to December 2010. The results from the sampling of the four lakes includes field measurements of redox potential (ORP), pH, dissolved oxygen, electrical conductivity, salinity, depth, atmospheric pressure, turbidity, chlorophyll and water temperature, as well as chemical analyses of major constituents and nutrient salts. The four investigated small lakes are well buffered with high alkalinity, high pH and high calcium concentrations. This is in accordance with results from the ongoing monitoring programme of lakes and streams in the area and with the results from the previous sampling period (2008-2009). The results show both seasonal and inter-annual variation in the analysed parameters. This can be explained by seasonal changes and annual differences in temperature, ice-cover, precipitation etc and lake specific parameters such as lake size and drainage area. The variation highlights the importance of both year round sampling and continued sampling for several years when discussing the water composition.

  4. The undersea location of the Swedish Final Repository for reactor waste, SFR - human intrusion aspects

    International Nuclear Information System (INIS)

    Eng, T.

    1989-01-01

    The Swedish Final Repository for reactor waste, SFR, is built under the Baltic sea close to the Forsmark nuclear power plant. Sixty metres of rock cover the repository caverns under the seabed. The depth of the Baltic sea is about 5-6 m at this location. A human intrusion scenario that in normal inland locations has shown to be of great importance, is a well that is drilled through or in the close vicinity of the repository. Since the land uplift in the SFR area is about 6 mm/year the undersea location of SFR ensures that no well will be drilled at this location for a considerable time while the area is covered by the Baltic sea

  5. Conceptual design of D-3He FRC reactor 'ARTEMIS'

    International Nuclear Information System (INIS)

    Momota, H.; Ishida, A.; Kohzaki, Y.

    1991-07-01

    A comprehensive design study of the D- 3 He fueled field-reversed configuration (FRC) reactor 'ARTEMIS' is carried out for the purpose of proving its attractive characteristics and clarifying the critical issues for a commercial fusion reactor. The FRC burning plasma is stabilized and sustained in a steady equilibrium by means of a preferential trapping of D- 3 He fusion-produced energetic protons. A novel direct energy converter for 15MeV protons is also presented. On the bases of a consistent scenario of the fusion plasma production and simple engineering, a compact and simple reactor concept is presented. The design of the D- 3 He FRC power plant definitely offers the most attractive prospect for energy development. It is environmentally acceptable in view of radio-activity and fuel resources; and the estimated cost of electricity is low compared to a light water reactor. Critical issues concerning physics or engineering for the development of the D- 3 He FRC reactor are clarified. (author)

  6. Modelling transport of water and solutes in future wetlands in Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Vikstroem, Maria; Gustafsson, Lars-Goeran [DHI Water and Environment AB, Vaexjoe (Sweden)

    2006-03-15

    The Forsmark area consists of a number of natural wetlands. As a part of the evaluation of wetlands in the safety assessment for the area, possible future wetlands are being studied with respect to hydrology and transport mechanisms. A sensitivity analyses is performed to point out the governing parameters for the wetland hydraulics. The analysis of future wetlands is carried out using the hydrological model system Mike SHE. Mike SHE has been used to describe the near-surface hydrology for a regional model area in Forsmark. Three types of areas have been chosen. Today's lake Bolundfjaerden is because of its shallow depth likely to develop into a mire in the future. As it is situated in the downstream part of the regional model area, the runoff to the lake from upstream surface water system is significant. Lake Eckarfjaerden is situated in the upstream part of the catchment at a higher altitude and with a smaller inflow. Lake Puttan is situated above a planned layout of the repository and has a potential to receive discharges from a repository. It also lies in the downstream part of a large discharge area. The topography of the future mires is assumed to be flat, up to today's mean water level in each lake. To transport the surface runoff through the wetland, streams or water courses are assumed to form within the peat. The analyses of future wetlands in the Forsmark area show that the hydraulic conditions that exists today will somewhat alter as the peat is formed. For Bolundsfjaerden, where there during present conditions are weak discharge areas, a recharge area has formed during the summer. This can be explained by the amount of surface water that forms on the surface which increases the head elevation in the upper soil layers. The same holds for Eckarfjaerden, while Puttan after the peat has developed still is a discharge area due to its naturally strong discharge position close to the sea. Different vegetation and development stages for the peat have

  7. Modelling transport of water and solutes in future wetlands in Forsmark

    International Nuclear Information System (INIS)

    Vikstroem, Maria; Gustafsson, Lars-Goeran

    2006-03-01

    The Forsmark area consists of a number of natural wetlands. As a part of the evaluation of wetlands in the safety assessment for the area, possible future wetlands are being studied with respect to hydrology and transport mechanisms. A sensitivity analyses is performed to point out the governing parameters for the wetland hydraulics. The analysis of future wetlands is carried out using the hydrological model system Mike SHE. Mike SHE has been used to describe the near-surface hydrology for a regional model area in Forsmark. Three types of areas have been chosen. Today's lake Bolundfjaerden is because of its shallow depth likely to develop into a mire in the future. As it is situated in the downstream part of the regional model area, the runoff to the lake from upstream surface water system is significant. Lake Eckarfjaerden is situated in the upstream part of the catchment at a higher altitude and with a smaller inflow. Lake Puttan is situated above a planned layout of the repository and has a potential to receive discharges from a repository. It also lies in the downstream part of a large discharge area. The topography of the future mires is assumed to be flat, up to today's mean water level in each lake. To transport the surface runoff through the wetland, streams or water courses are assumed to form within the peat. The analyses of future wetlands in the Forsmark area show that the hydraulic conditions that exists today will somewhat alter as the peat is formed. For Bolundsfjaerden, where there during present conditions are weak discharge areas, a recharge area has formed during the summer. This can be explained by the amount of surface water that forms on the surface which increases the head elevation in the upper soil layers. The same holds for Eckarfjaerden, while Puttan after the peat has developed still is a discharge area due to its naturally strong discharge position close to the sea. Different vegetation and development stages for the peat have been

  8. Long-term safety for the final repository for spent nuclear fuel at Forsmark. Main report of the SR-Site project

    Energy Technology Data Exchange (ETDEWEB)

    2011-03-15

    The central conclusion of the safety assessment SR-Site is that a KBS-3 repository that fulfils long-term safety requirements can be built at the Forsmark site. This conclusion is reached because the favourable properties of the Forsmark site ensure the required long-term durability of the barriers of the KBS-3 repository. In particular, the copper canisters with their cast iron inserts have been demonstrated to provide a sufficient resistance to the mechanical and chemical loads to which they may be subjected in the repository environment. The conclusion is underpinned by: - The reliance of the KBS-3 repository on i) a geological environment that exhibits long-term stability with respect to properties of importance for long-term safety, i.e. mechanical stability, low groundwater flow rates at repository depth and the absence of high concentrations of detrimental components in the groundwater, and ii) the choice of naturally occurring materials (copper and bentonite clay) for the engineered barriers that are sufficiently durable in the repository environment to provide the barrier longevity required for safety. - The understanding, through decades of research at SKB and in international collaboration, of the phenomena that affect long-term safety, resulting in a mature knowledge base for the safety assessment. - The understanding of the characteristics of the site through several years of surface-based investigations of the conditions at depth and of scientific interpretation of the data emerging from the investigations, resulting in a mature model of the site, adequate for use in the safety assessment. - The detailed specifications of the engineered parts of the repository and the demonstration of how components fulfilling the specifications are to be produced in a quality assured manner, thereby providing a quality assured initial state for the safety assessment. The detailed analyses demonstrate that canister failures in a one million year perspective are rare

  9. Long-term safety for the final repository for spent nuclear fuel at Forsmark. Main report of the SR-Site project

    International Nuclear Information System (INIS)

    2011-03-01

    The central conclusion of the safety assessment SR-Site is that a KBS-3 repository that fulfils long-term safety requirements can be built at the Forsmark site. This conclusion is reached because the favourable properties of the Forsmark site ensure the required long-term durability of the barriers of the KBS-3 repository. In particular, the copper canisters with their cast iron inserts have been demonstrated to provide a sufficient resistance to the mechanical and chemical loads to which they may be subjected in the repository environment. The conclusion is underpinned by: - The reliance of the KBS-3 repository on i) a geological environment that exhibits long-term stability with respect to properties of importance for long-term safety, i.e. mechanical stability, low groundwater flow rates at repository depth and the absence of high concentrations of detrimental components in the groundwater, and ii) the choice of naturally occurring materials (copper and bentonite clay) for the engineered barriers that are sufficiently durable in the repository environment to provide the barrier longevity required for safety. - The understanding, through decades of research at SKB and in international collaboration, of the phenomena that affect long-term safety, resulting in a mature knowledge base for the safety assessment. - The understanding of the characteristics of the site through several years of surface-based investigations of the conditions at depth and of scientific interpretation of the data emerging from the investigations, resulting in a mature model of the site, adequate for use in the safety assessment. - The detailed specifications of the engineered parts of the repository and the demonstration of how components fulfilling the specifications are to be produced in a quality assured manner, thereby providing a quality assured initial state for the safety assessment. The detailed analyses demonstrate that canister failures in a one million year perspective are rare

  10. Long-term safety for KBS-3 repositories at Forsmark and Laxemar - a first evaluation. Main Report of the SR-Can project

    International Nuclear Information System (INIS)

    Hedin, Allan

    2006-10-01

    This document is the main report from the safety assessment project SR-Can. The SR-Can project is a preparatory stage for the SR-Site assessment, the report that will be used in support of SKB's application for a final repository. The purposes of the safety assessment SR-Can are the following: 1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant. 2. To provide feedback to design development, to SKB's RandD programme, to further site investigations and to future safety assessment projects. 3. To foster a dialogue with the authorities that oversee SKB's activities, i.e. the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI, regarding interpretation of applicable regulations, as a preparation for the SR-Site project. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark and Laxemar sites, presently being investigated by SKB as candidates for a KBS-3 repository are used in the assessment. An important aim of this report is to demonstrate the proper handling of requirements placed on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Institute are reproduced in an Appendix where references are given to sections in the main text where the handling of the different requirements is discussed. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10 -6 for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects. The risk limit corresponds to an

  11. Long-term safety for KBS-3 repositories at Forsmark and Laxemar - a first evaluation. Main Report of the SR-Can project

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, Allan (ed.)

    2006-10-15

    This document is the main report from the safety assessment project SR-Can. The SR-Can project is a preparatory stage for the SR-Site assessment, the report that will be used in support of SKB's application for a final repository. The purposes of the safety assessment SR-Can are the following: 1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant. 2. To provide feedback to design development, to SKB's RandD programme, to further site investigations and to future safety assessment projects. 3. To foster a dialogue with the authorities that oversee SKB's activities, i.e. the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI, regarding interpretation of applicable regulations, as a preparation for the SR-Site project. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark and Laxemar sites, presently being investigated by SKB as candidates for a KBS-3 repository are used in the assessment. An important aim of this report is to demonstrate the proper handling of requirements placed on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Institute are reproduced in an Appendix where references are given to sections in the main text where the handling of the different requirements is discussed. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10{sup -6} for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects

  12. Removal in a lump of JRR-3 nuclear reactor

    International Nuclear Information System (INIS)

    Ohnishi, Nobuaki; Suzuki, Masanori; Nagase, Tetsuo; Watanabe, Morinari.

    1989-01-01

    The research reactor JRR-3 in Japan Atomic Energy Research Institute is called 'Home made No.1 reactor' as all except fuel and heavy water as the moderator and coolant were manufactured in Japan. The JRR-3 attained the criticality in 1962, and the cumulative time of operation reached 47135.5 hours, and the cumulative power output reached 419073.5 MWh. It was stopped in 1983. During the period, it was utilized for beam experiment, irradiation of fuel and materials, RI production and others. In order to cope with the expansion of utilization and the advance of utilizing technology of the research reactor, the reconstruction works are in progress, and the criticality of the reconstructed reactor is expected in 1990. On the site where the old reactor is removed, the reactor of different type is installed, and the first large cold neutron source is equipped. In this report, as to the removal of the old reactor proper, the method of working and the results are described. Considering the period of working, the cost and the management of the removed reactor, in the case of the JRR-3, the method of carrying it out in a lump was adopted as the optimum removal method. The plan, procedure and results of the removal working are reported. (K.I.)

  13. Hydrogeological characterisation and modelling of deformation zones and fracture domains, Forsmark modelling stage 2.2

    Energy Technology Data Exchange (ETDEWEB)

    Follin, Sven (SF GeoLogic AB, Taeby (SE)); Leven, Jakob (Swedish Nuclear Fuel and Waste Management Co., Stockholm (SE)); Hartley, Lee; Jackson, Peter; Joyce, Steve; Roberts, David; Swift, Ben (Serco Assurance, Harwell (GB))

    2007-09-15

    The work reported here collates the structural-hydraulic information gathered in 21 cored boreholes and 32 percussion-drilled boreholes belonging to Forsmark site description, modelling stage 2.2. The analyses carried out provide the hydrogeological input descriptions of the bedrock in Forsmark needed by the end users Repository Engineering, Safety Assessment and Environmental Impact Assessment; that is, hydraulic properties of deformation zones and fracture domains. The same information is also needed for constructing 3D groundwater flow models of the Forsmark site and surrounding area. The analyses carried out render the following conceptual model regarding the observed heterogeneity in deformation zone transmissivity: We find the geological division of the deterministically modelled deformation zones into eight categories (sets) useful from a hydrogeological point of view. Seven of the eight categories are steeply dipping, WNW, NW, NNW, NNE, NE, ENE and EW, and on is gently dipping, G. All deformation zones, regardless of orientation (strike and dip), are subjected to a substantial decrease in transmissivity with depth. The data gathered suggest a contrast of c. 20,000 times for the uppermost one kilometre of bedrock, i.e. more than four orders of magnitude. The hydraulic properties below this depth are not investigated. The lateral heterogeneity is also substantial but more irregular in its appearance. For instance, for a given elevation and deformation zone category (orientation), the spatial variability in transmissivity within a particular deformation zone appears to be as large as the variability between all deformation zones. This suggests that the lateral correlation length is shorter than the shortest distance between two adjacent observation points and shorter than the category spacing. The observation that the mean transmissivity of the gently-dipping deformation zones is c. one to two orders of magnitude greater than the mean transmissivities of all

  14. The Physical Mechanism of Core-Wide and Local Instabilities at the Forsmark-1 BWR

    International Nuclear Information System (INIS)

    Analytis, G. Th.

    1998-10-01

    During the last 15 years, the problem of BWR instabilities has attracted the attention of a number of researchers. From the theoretical point of view, one would be interested in physically understanding the mechanisms responsible for the in- and out-of-phase core wide power oscillations observed at certain operating points of the power-flow map in different BWRs. From the practical point of view, one must try to avoid these 'incidents' since either locally, or globally, the power may substantially exceed the prescribed levels. In this work, we shall use RAMONA3-12 and analyse a rather unusual instability incident at Forsmark-1 in which in addition to the core-wide fundamental spatial mode oscillation, there were local large amplitude power oscillations at different radial positions in the core. We were able to reproduce these unusual experimental findings by assuming that there are large amplitude Density Wave Oscillations (DWOs) in different bundles, induced by the fact that these bundles were not seated properly into the lower fuel support plate. (author)

  15. 3D simulation of CANDU reactor regulating system

    International Nuclear Information System (INIS)

    Venescu, B.; Zevedei, D.; Jurian, M.

    2013-01-01

    Present paper shows the evaluation of the performance of the 3-D modal synthesis based reactor kinetic model in a closed-loop environment in a MATLAB/SIMULINK based Reactor Regulating System (RRS) simulation platform. A notable advantage of the 3-D model is the level of details that it can reveal as compared to the coupled point kinetic model. Using the developed RRS simulation platform, the reactor internal behaviours can be revealed during load-following tests. The test results are also benchmarked against measurements from an existing (CANDU) power plant. It can be concluded that the 3-D reactor model produces more realistic view of the core neutron flux distribution, which is closer to the real plant measurements than that from a coupled point kinetic model. It is also shown that, through a vectorization process, the computational load of the 3-D model is comparable with that of the 14-zone coupled point kinetic model. Furthermore, the developed Graphical User Interface (GUI) software package for RRS implementation represents a user friendly and independent application environment for education training and industrial utilizations. (authors)

  16. Analyses for MARIA Research Reactor with RELAP/MOD3 code

    International Nuclear Information System (INIS)

    Szczurek, J.; Czerski, P.

    2004-01-01

    This paper deals with the application of the RELAP5/MOD3 code to the transient analyses for MARIA research reactor. Poland's MARIA Research Reactor is water and beryllium moderated, water-cooled reactor of a pool type with pressurized fuel channels containing concentric multi-tube assemblies of highly enriched uranium clad in aluminium. The RELAP5/MOD3 input data model includes the whole primary cooling circuit of the MARIA reactor. The model was qualified against the reactor data at steady state conditions and additionally against the existing reliable experimental data for a transient initiated by the reactor scram. The RELAP transient simulation was performed for loss of forced flow accidents including two scenarios with protected and unprotected (no scram) reactor core. Calculations allow estimating time margin for reactor scram initiation and reactivity feedbacks contribution to the results. (author)

  17. Method for consequence calculations for severe accidents

    International Nuclear Information System (INIS)

    Nielsen, F.

    1988-07-01

    This report was commissioned by the Swedish State Power Board. The report contains a calculation of radiation doses in the surroundings caused by a theoretical core meltdown accident at Forsmark reactor No 3. The accident sequence chosen for the calculating was a release caused by total power failure. The calculations were made by means of the PLUCON4 code. Meteorological data for two years from the Forsmark meteorological tower were analysed to find representative weather situations. As typical weather, Pasquill D was chosen with a wind speed of 5 m/s, and as extreme weather, Pasquill F with a wind speed of 2 m/s. 23 tabs., 37 ills., 20 refs. (author)

  18. Site description of the SFR area at Forsmark at completion of the site investigation phase. SDM-PSU Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-05-15

    The site descriptive model (SDM) presented in this report is an integrated model for bedrock geology, rock mechanics, bedrock hydrogeology and bedrock hydrogeochemistry of the site investigated in the SFR extension project (PSU). A description of the surface system is also included in the report. However, the surface system is not integrated with the other disciplines as new data regarding the surface system will not be available until after the completion of SDM-PSU. It is noted that SDM-PSU does not include all disciplines handled in SDM-Site Forsmark (SKB 2008b), the focus is to produce a site description that meets the needs of the SFR extension project. The overall objective of the SFR extension project is to have the application for the extension ready by 2013. This report presents an integrated site model incorporating the historic data acquired from the investigations for and construction of the existing SFR facility (1980-1986), as well as from the recent investigations for the planned extension of SFR (2008-2009). It also provides a summary of the abundant underlying data and the discipline-specific models that support the integrated site model. The description relies heavily on background reports concerning detailed data analyses and modelling in the different disciplines. It is noteworthy that the investigations conducted during the SFR extension project were guided by the choice of site prior to the investigations, which was based on the experience gained during the construction of the existing SFR facility.

  19. Site description of the SFR area at Forsmark at completion of the site investigation phase. SDM-PSU Forsmark

    International Nuclear Information System (INIS)

    2013-05-01

    The site descriptive model (SDM) presented in this report is an integrated model for bedrock geology, rock mechanics, bedrock hydrogeology and bedrock hydrogeochemistry of the site investigated in the SFR extension project (PSU). A description of the surface system is also included in the report. However, the surface system is not integrated with the other disciplines as new data regarding the surface system will not be available until after the completion of SDM-PSU. It is noted that SDM-PSU does not include all disciplines handled in SDM-Site Forsmark (SKB 2008b), the focus is to produce a site description that meets the needs of the SFR extension project. The overall objective of the SFR extension project is to have the application for the extension ready by 2013. This report presents an integrated site model incorporating the historic data acquired from the investigations for and construction of the existing SFR facility (1980-1986), as well as from the recent investigations for the planned extension of SFR (2008-2009). It also provides a summary of the abundant underlying data and the discipline-specific models that support the integrated site model. The description relies heavily on background reports concerning detailed data analyses and modelling in the different disciplines. It is noteworthy that the investigations conducted during the SFR extension project were guided by the choice of site prior to the investigations, which was based on the experience gained during the construction of the existing SFR facility

  20. Completion of reconstruction for Japan Research Reactor No.3

    International Nuclear Information System (INIS)

    Kakefuda, K.; Tani, M.; Isshiki, M.

    1992-01-01

    The works of the reconstruction for the Japan Research Reactor No.3 (JRR-3) started in 1985 and initial criticality of the new reactor achieved in March, 1990. After commissioning test, the new JRR-3 has been operated some operational cycles since November, 1990. This paper presents outline of the removal work on the old JRR-3 and the new JRR-3. (author)

  1. Stress variations during a glacial cycle at 500 m depth in Forsmark and Oskarshamn: Earth model effects

    Energy Technology Data Exchange (ETDEWEB)

    Lund, Bjoern [Uppsala Univ. (Sweden). Dept. of Earth Sciences

    2006-06-15

    This study has considered the response to a glaciation of Earth models of increasingly complex structure in elastic parameters and viscosity. The models are one-dimensional in the sense that they vary only in the depth direction, i.e. there are only uniform, horizontal layers in the models. I find that as the complexity of the models increase, and the properties of the uppermost kilometer of the Earth become less affected by average properties from deeper down, the flexural stresses at 500 m depth decrease, as expected. A lower Young's modulus, lower compressibility and lower density in the uppermost layer all act to lower the stresses. However, the three properties act differently on the resulting response. Introducing layering in Young's modulus generally decreases the stresses all along a profile through the ice model. Going from incompressible to compressible models affect the stresses outside the ice edge significantly more than the stresses under the ice sheet. Introducing layering in density conversely affect the stresses under the ice sheet more than those outside the ice edge. The combined effects of the most complex models tested here show that the glacially induced horizontal stresses at 500 m depth decrease to levels very similar in magnitude to the loading stress. There are, however, temporal variations in these horizontal stresses that do not follow the loading stress and which induce tensional or compressional horizontal stresses that persist when no ice is present.As is well known, changes in viscosity structure has a very large effect on the Earth response. Viscosity affect both the magnitudes of the induced stresses and the temporal behavior of the stress evolution. This is confirmed in the current study.The glacially induced stresses for some of the models have been used in combination with the current background stress field at Forsmark and Oskarshamn, as estimated in SKB's site models, to evaluate fault stability throughout a

  2. Stress variations during a glacial cycle at 500 m depth in Forsmark and Oskarshamn: Earth model effects

    International Nuclear Information System (INIS)

    Lund, Bjoern

    2006-06-01

    This study has considered the response to a glaciation of Earth models of increasingly complex structure in elastic parameters and viscosity. The models are one-dimensional in the sense that they vary only in the depth direction, i.e. there are only uniform, horizontal layers in the models. I find that as the complexity of the models increase, and the properties of the uppermost kilometer of the Earth become less affected by average properties from deeper down, the flexural stresses at 500 m depth decrease, as expected. A lower Young's modulus, lower compressibility and lower density in the uppermost layer all act to lower the stresses. However, the three properties act differently on the resulting response. Introducing layering in Young's modulus generally decreases the stresses all along a profile through the ice model. Going from incompressible to compressible models affect the stresses outside the ice edge significantly more than the stresses under the ice sheet. Introducing layering in density conversely affect the stresses under the ice sheet more than those outside the ice edge. The combined effects of the most complex models tested here show that the glacially induced horizontal stresses at 500 m depth decrease to levels very similar in magnitude to the loading stress. There are, however, temporal variations in these horizontal stresses that do not follow the loading stress and which induce tensional or compressional horizontal stresses that persist when no ice is present.As is well known, changes in viscosity structure has a very large effect on the Earth response. Viscosity affect both the magnitudes of the induced stresses and the temporal behavior of the stress evolution. This is confirmed in the current study.The glacially induced stresses for some of the models have been used in combination with the current background stress field at Forsmark and Oskarshamn, as estimated in SKB's site models, to evaluate fault stability throughout a glacial cycle. The

  3. EL3 reactor description and safety analysis report

    International Nuclear Information System (INIS)

    1969-02-01

    The EL-3 reactor is an experimental pile. Heterogenous type reactor, water moderated and cooled it uses slightly enriched uranium oxide as fuel (4.5 percent) distributed in vertical cells that constitute the core (the maximum number of cells is 99). It is conceived to function at a maximal thermal power of 20 MW. It supplies a maximum thermal neutron flux of 10 14 neutrons/cm 2 /sec. It has several experimental devices. The EL-3 reactor is surrounded by auxiliary circuits of fluids, in a sealed containment, slightly depressed. The primary heavy water coolant circuit is completely included in this containment. Its cooling is made by the intermediary of a light water secondary circuit by atmospheric refrigerants. The ventilation circuits of the sealed containment and the reactor block do not release air outside, under nornal functioning, by a particularly studied chimney only after filtering and eventually dilution. The eventual contamination of the light water or air by active products is permanently monitored to allow the reactor shutdown and avoid the release in atmosphere of dangerous products. The EL-3 reactor, laying down in may 1955, has diverged in july 1957, made its first ascending in power in december 1957 and reached its complete power in april 1958. The positioning of actual fuel (snow crystal) was made during summer 1964. Reactor with an experimental aim, it is used for theoretical and technological studies by material irradiation in the experimental channels and the core cells, with possibilities to constitute independent loops (relative to the cooling fluids). Thirty vertical channels are devoted to the fabrication of artificial radioelements [fr

  4. Course of operators of the RA-3 reactor

    International Nuclear Information System (INIS)

    Caligiuri, G.A.

    1983-01-01

    Description of the fundamental principles of the nuclear reactors' control systems. The RA-3 reactor's control and measurement systems are principally described, without setting aside the basic criteria for the design of an appropriate instrumentation for the control of a nuclear reactor, as well as the theory on which the functioning of the several detectors and equipments used in a nuclear instrumentation are based. The main purpose of this course is that of serving, preferentially as a text, for the training of personnel which shall perform operation tasks in this reactor. The work includes three well-defined sections. The first two ones make an introduction to the subject, while the third one, extending to more than half-work, deals with the general description of the system in which the control and operation logic of RA-3 are included. (R.J.S) [es

  5. New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses

    Energy Technology Data Exchange (ETDEWEB)

    Nikitin, Evgeny [Ecole Polytechnique Federale de Lausanne (Switzerland); Helmholtz-Zentrum Dresden-Rossendorf (HZDR) e.V., Dresden (Germany); Fridman, Emil; Bilodid, Yuri; Kliem, Soeren [Helmholtz-Zentrum Dresden-Rossendorf (HZDR) e.V., Dresden (Germany)

    2017-07-15

    The reactor dynamics code DYN3D being developed at the Helmholtz-Zentrum Dresden-Rossendorf is currently under extension for Sodium cooled Fast Reactor analyses. This paper provides an overview on the new version of DYN3D to be used for SFR core calculations. The current article shortly describes the newly implemented thermal mechanical models, which can account for thermal expansion effects of the reactor core. Furthermore, the methodology used in Sodium cooled Fast Reactor analyses to generate homogenized few-group cross sections is summarized. The conducted and planned verification and validation studies are briefly presented. Related publications containing more detailed descriptions are outlined for the completeness of this overview.

  6. Calibration and analysis of soil carbon efflux estimates with closed chambers at Forsmark and Laxemar

    International Nuclear Information System (INIS)

    Tagesson, Torbern

    2006-08-01

    The Forsmark and the Laxemar investigation areas are examined by the Swedish Nuclear Fuel and Waste Management Co. for a possible construction of a deep repository for nuclear waste. In the case of a future leakage of waste, the radioactive isotopes could end up in the ecosystems above the repository. The fate of the radionuclides and their possible radiological impacts are then highly determined by ecosystem carbon cycling. An important part of the carbon cycling is the soil carbon effluxes, and in the investigation areas soil carbon effluxes have been examined with the closed chamber technique. This paper is divided into two parts. Firstly, there were problems with the equipment measuring the soil carbon dioxide efflux, and the first part is a description of the problem, how it was corrected and its possible causes. The second part is a manual in how to analyse data and calculate annual estimates of soil carbon efflux. The field measurement by the EGM-4 is just an occasional estimate of the soil carbon efflux at a certain spot and at a certain point in time. To make an interpretation of the measurements, it is essential to analyse the data and to temporally extrapolate them. It is necessary to prepare the raw data for the analysis. The problems with the EGM-4 doing the measurements at the Forsmark and the Laxemar investigation area makes it necessary to correct the data taken up by this EGM-4. The data should also be separated into soil respiration and gross primary production (GPP). Soil carbon dioxide effluxes should be changed to soil carbon effluxes. Soil carbon effluxes are strongly controlled by abiotic factors; temperature is the main factor to influence soil respiration and photosynthetically active radiation (PAR) and air temperature are the main factors to influence GPP. Regression with soil respiration against temperature and with GPP against PAR or temperature can therefore be done. These equations can then be used on datasets with temperature and PAR

  7. Calibration and analysis of soil carbon efflux estimates with closed chambers at Forsmark and Laxemar

    Energy Technology Data Exchange (ETDEWEB)

    Tagesson, Torbern (Dept. of Physical Geography and Ecosystem Analysis, Lund Univ., Lund (SE))

    2006-08-15

    The Forsmark and the Laxemar investigation areas are examined by the Swedish Nuclear Fuel and Waste Management Co. for a possible construction of a deep repository for nuclear waste. In the case of a future leakage of waste, the radioactive isotopes could end up in the ecosystems above the repository. The fate of the radionuclides and their possible radiological impacts are then highly determined by ecosystem carbon cycling. An important part of the carbon cycling is the soil carbon effluxes, and in the investigation areas soil carbon effluxes have been examined with the closed chamber technique. This paper is divided into two parts. Firstly, there were problems with the equipment measuring the soil carbon dioxide efflux, and the first part is a description of the problem, how it was corrected and its possible causes. The second part is a manual in how to analyse data and calculate annual estimates of soil carbon efflux. The field measurement by the EGM-4 is just an occasional estimate of the soil carbon efflux at a certain spot and at a certain point in time. To make an interpretation of the measurements, it is essential to analyse the data and to temporally extrapolate them. It is necessary to prepare the raw data for the analysis. The problems with the EGM-4 doing the measurements at the Forsmark and the Laxemar investigation area makes it necessary to correct the data taken up by this EGM-4. The data should also be separated into soil respiration and gross primary production (GPP). Soil carbon dioxide effluxes should be changed to soil carbon effluxes. Soil carbon effluxes are strongly controlled by abiotic factors; temperature is the main factor to influence soil respiration and photosynthetically active radiation (PAR) and air temperature are the main factors to influence GPP. Regression with soil respiration against temperature and with GPP against PAR or temperature can therefore be done. These equations can then be used on datasets with temperature and PAR

  8. Basis for applying for exemption according to species protection regulation. Final repository for spent nuclear fuel at Forsmark

    International Nuclear Information System (INIS)

    2011-02-01

    SKB will submit applications for permits and admissibility under the Environmental Act and under the Nuclear Activities Act to construct and operate a disposal facility for spent nuclear fuel at Forsmark. In the final repository the spent nuclear fuel from Swedish nuclear power plants is placed in order to protect human health and the environment against harmful effects of ionizing radiation. Construction and operation of the disposal facility in Forsmark will make an impact, give effects and consequences for the natural environment. Utilization of land for the construction of the facility and the impact on ground water as a result of groundwater drainage is expected to have negative consequences for the species included in species protection regulation. Thus, the planned activity require exemption from species protection regulation (SFS 2007:845). The purpose of this document is to provide a basis for an application for exemption under 14 paragraph species protection regulation from the prohibitions of 4, 6, 7 and 8 paragraph species protection regulation. A basis for the exemption application is that the proposed activity is considered to have an 'overriding public interest' prescribed in 14 paragraph species protection regulation. The document reports the impact, effects and consequences of the planned activities on species covered in the species protection regulation. The impact on protected species can be divided into two categories: - Direct effects on protected species and their habitats by utilization of the land. - Indirect effects on protected species and their habitats in the drainage of groundwater and the effect on groundwater levels. The document also includes a description of planned actions to prevent, restrict and compensate for the effects and consequences that the activity may cause. By applying for an exemption under 14 paragraph species protection regulation in a separate order from the application for permit according to chapters 9 and 11

  9. Method for consequence calculations for severe accidents

    International Nuclear Information System (INIS)

    Nielsen, F.; Thykier-Nielsn, S.

    1987-03-01

    This report was commissioned by the Swedish State Power Board. The report contains a calculation of radiation doses in the surroundings caused by a theoretical core meltdown accident at Forsmark reactor No 3. The assumption used for the calculations were a 0.06% release of iodine and cesium corresponding to a 0.1% release through the FILTRA plant at Barsebaeck. The calculations were made by means of the PLUCON4 code. Meteorological data for two years from the Forsmark meteorological tower were analysed to find representative weather situations. As typical weather pasquill D was chosen with wind speed 5 m/s, and as extreme weather, Pasquill F with wind speed 2 m/s. 23 tabs., 36 ills., 21 refs. (author)

  10. 3 Investment Scenarios for Fast Reactors

    International Nuclear Information System (INIS)

    Shoai Tehrani, Bianka; Da Costa, Pascal

    2013-01-01

    Results: • 4 families of scenarios: – In each of them, 3 options for national nuclear policy → 12 scenarios; – 3 favorable to FRs: - “climate constraint” with strong pro-nuclear policy - “climate constraint” with moderate pro-nuclear policy - “totally green” with strong pro-nuclear policy. • Business As Usual is not favorable to Fast Reactors; Fast reactors deployment: - Needs strong climate policy - Is viable in case of important renewable progress as long as climate policy is strong. International perspective: • Results are valid for Europe, other drivers being likely to be more important in other countries : high growth and demand (Asia); • With strong contrasts between European countries. Further research: • Finer modeling of drivers with unclear influence (clustered and excluded variables): Influence of weak signals

  11. D-3He fueled FRC reactor 'ARTEMIS-L'

    International Nuclear Information System (INIS)

    Momota, Hiromu; Tomita, Yukihiro; Ishida, Akio; Kohzaki, Yasuji; Nakao, Yasuyuki; Nishikawa, Masabumi; Ohi, Shoichi; Ohnishi, Masami.

    1992-09-01

    A neutron-lean D- 3 He fueled field reversed configuration (FRC) fusion reactor is studied on the bases of former high-efficiency ARTEMIS design. Certain improvements such as effective axial contracting plasma heating and cusp-type direct energy converters as well as an empirical scale of the energy confinement are introduced. The resultant total neutron load onto the first wall of the plasma chamber is as low as 0.1 MW/m 2 , which enable the life of the first wall or the structural materials to be longer than the whole life of the reactor. The attractive characteristics of the neutron-lean reactor follow in the ARTEMIS design: it is socially acceptable in views of radioactivity and fuel resources, and the cost of electricity appears to be cheap compared with that from a light water reactor. Critical physics and engineering issues for performing the ARTEMIS-L reactor are clarified. (author)

  12. Chemical characteristics of surface waters in the Forsmark area. Evaluation of data from lakes, streams and coastal sites

    International Nuclear Information System (INIS)

    Sonesten, Lars

    2005-06-01

    This report is an evaluation of the chemical composition of surface water in lakes, streams, and at coastal sampling sites in the Forsmark area. The aim with this study is to characterise the surface water systems in the area, and the further aim with this characterisation is to be used as input material to the safety analyses and environmental impact assessments for the potential deep repository of used nuclear fuels. The data used consist of water chemical composition of lakes, streams and coastal sites from the period March 2002 - April 2004. The sampling has been performed predominantly on a monthly basis. The emphasis of the assessment has been on surface waters (0.5 m), as the water depth at all sampling locations is limited, and thereby the water systems are rarely stratified for prolonged periods. The characterisations have been restricted to the most commonly measured chemical parameters.The assessment has been divided into three parts: Comparisons within and between the lakes, streams, and coastal sites, respectively; Temporal and spatial variation, predominantly within lakes and stream sites; and Relationships between the various chemical parameters. Beside comparisons between the sampling sites within the Forsmark area, comparisons have also been made with regional and national data from the latest Swedish National Survey (2000). The analyses of temporal and spatial variation have been concentrated on the freshwater systems in the Norra Bassaengen catchment area. This catchment area is the most comprehensively investigated, and it also includes the Bolundsfjaerden sub-catchment, which is the area where the continued site investigations will be concentrated. The relationships among the sampling sites, the catchment areas, as well as the chemical parameters investigated, were examined by applying PCA analyses on the lake and stream data. In general, the freshwater systems in the Forsmark area are characterised by small and shallow oligotrophic hardwater

  13. Chemical characteristics of surface waters in the Forsmark area. Evaluation of data from lakes, streams and coastal sites

    Energy Technology Data Exchange (ETDEWEB)

    Sonesten, Lars [Swedish Univ. of Agricultural Sciences, Uppsala (Sweden). Dept. of Environmental Assessment

    2005-06-01

    This report is an evaluation of the chemical composition of surface water in lakes, streams, and at coastal sampling sites in the Forsmark area. The aim with this study is to characterise the surface water systems in the area, and the further aim with this characterisation is to be used as input material to the safety analyses and environmental impact assessments for the potential deep repository of used nuclear fuels. The data used consist of water chemical composition of lakes, streams and coastal sites from the period March 2002 - April 2004. The sampling has been performed predominantly on a monthly basis. The emphasis of the assessment has been on surface waters (0.5 m), as the water depth at all sampling locations is limited, and thereby the water systems are rarely stratified for prolonged periods. The characterisations have been restricted to the most commonly measured chemical parameters.The assessment has been divided into three parts: Comparisons within and between the lakes, streams, and coastal sites, respectively; Temporal and spatial variation, predominantly within lakes and stream sites; and Relationships between the various chemical parameters. Beside comparisons between the sampling sites within the Forsmark area, comparisons have also been made with regional and national data from the latest Swedish National Survey (2000). The analyses of temporal and spatial variation have been concentrated on the freshwater systems in the Norra Bassaengen catchment area. This catchment area is the most comprehensively investigated, and it also includes the Bolundsfjaerden sub-catchment, which is the area where the continued site investigations will be concentrated. The relationships among the sampling sites, the catchment areas, as well as the chemical parameters investigated, were examined by applying PCA analyses on the lake and stream data. In general, the freshwater systems in the Forsmark area are characterised by small and shallow oligotrophic hardwater

  14. Description of the RA-3 research reactor as a model facility

    International Nuclear Information System (INIS)

    Vicens, Hugo E.; Quintana, Jorge A.

    2001-01-01

    The Argentine RA-3 reactor is described as a model facility for the information to be provided to the IAEA in accordance with the requirements of the Model Additional Protocol. RA-3 reactor was designed as a 5 MW swimming pool reactor, moderated and cooled with light water. Its fuel was 90% enriched uranium. The reactor started its operation in 1967, has been modified and improved in many components, including the core, that now is fueled with moderately enriched uranium

  15. Final disposal Forsmark, Simpevarp and Laxemar. Inflow of ground water and influence on hydrogeologic and hydrologic conditions; Slutfoervar Forsmark, Simpevarp och Laxemar. Inlaeckage av grundvatten samt paaverkan paa hydrogeologiska och hydrologiska foerhaallanden

    Energy Technology Data Exchange (ETDEWEB)

    Werner, Kent [Golder Associates AB, Stockholm (Sweden)

    2006-10-15

    Laxemar, the results show that also the deep parts of the repository yield an inflow and cause a lowering of the groundwater table. Hence, it is more difficult to decouple the deep and the near surface parts of the repository at these locations. A repository at Simpevarp causes a larger inflow but a smaller area of influence, compared to a repository at Laxemar. This difference is most likely due to that Simpevarp is located by the sea, whereas Laxemar is located further inland. However, there are differences in terms of how grouting is simulated in the DarcyTools modelling of the locations, which makes the comparison difficult. A simple estimate, based on the net recharge (annual mean) at each site shows that the model calculated inflow to a repository at Forsmark corresponds to an area of influence from c 1 km{sup 2} (hydraulic conductivity in the grouted zone K{sub inj} 10{sup -7} m/s) to c 0.3 km{sup 2} (K{sub inj} = 10{sup -9} m/s). For a repository at Simpevarp, the inflow corresponds an area of influence from c 36 km{sup 2} (skin factor = 0.1) to c 1.5 km{sup 2} (skin factor = 0.001); in the Simpevarp modelling, a 'skin factor' was utilized to simulate the grouting. For a repository at Laxemar, a similar comparison provides an area of influence from c 11 km{sup 2} (K{sub inj} = 10{sup -7} m/s) to c 6.5 km{sup 2} (K{sub inj} = 10{sup -9} m/s). Since the modelling results are preliminary, they principally express differences between the locations in terms of their hydrogeological and hydrological characteristics. The results are yet too preliminary to demonstrate the effects of a repository on its surroundings in absolute terms. Examples of uncertainties in the modelling include the representation of the bedrock in the 'bedrock models', providing the basis for the modelling; this particularly applies to the upper parts of the bedrock. Moreover, the interaction between Quaternary deposits and bedrock is identified as an important factor for the

  16. The simplified P3 approach on a trigonal geometry in the nodal reactor code DYN3D

    International Nuclear Information System (INIS)

    Duerigen, S.; Fridman, E.

    2011-01-01

    DYN3D is a three-dimensional nodal diffusion code for steady-state and transient analyses of Light-Water Reactors with square and hexagonal fuel assembly geometries. Currently, several versions of the DYN3D code are available including a multi-group diffusion and a simplified P 3 (SP 3 ) neutron transport option. In this work, the multi-group SP 3 method based on trigonal-z geometry was developed. The method is applicable to the analysis of reactor cores with hexagonal fuel assemblies and allows flexible mesh refinement, which is of particular importance for WWER-type Pressurized Water Reactors as well as for innovative reactor concepts including block type High-Temperature Reactors and Sodium Fast Reactors. In this paper, the theoretical background for the trigonal SP 3 methodology is outlined and the results of a preliminary verification analysis are presented by means of a simplified WWER-440 core test example. The accordant cross sections and reference solutions were produced by the Monte Carlo code SERPENT. The DYN3D results are in good agreement with the reference solutions. The average deviation in the nodal power distribution is about 1%. (Authors)

  17. 3D computer visualization and animation of CANDU reactor core

    International Nuclear Information System (INIS)

    Qian, T.; Echlin, M.; Tonner, P.; Sur, B.

    1999-01-01

    Three-dimensional (3D) computer visualization and animation models of typical CANDU reactor cores (Darlington, Point Lepreau) have been developed using world-wide-web (WWW) browser based tools: JavaScript, hyper-text-markup language (HTML) and virtual reality modeling language (VRML). The 3D models provide three-dimensional views of internal control and monitoring structures in the reactor core, such as fuel channels, flux detectors, liquid zone controllers, zone boundaries, shutoff rods, poison injection tubes, ion chambers. Animations have been developed based on real in-core flux detector responses and rod position data from reactor shutdown. The animations show flux changing inside the reactor core with the drop of shutoff rods and/or the injection of liquid poison. The 3D models also provide hypertext links to documents giving specifications and historical data for particular components. Data in HTML format (or other format such as PDF, etc.) can be shown in text, tables, plots, drawings, etc., and further links to other sources of data can also be embedded. This paper summarizes the use of these WWW browser based tools, and describes the resulting 3D reactor core static and dynamic models. Potential applications of the models are discussed. (author)

  18. Experiment for search for sterile neutrino at SM-3 reactor

    Science.gov (United States)

    Serebrov, A. P.; Ivochkin, V. G.; Samoylov, R. M.; Fomin, A. K.; Zinoviev, V. G.; Neustroev, P. V.; Golovtsov, V. L.; Gruzinsky, N. V.; Solovey, V. A.; Cherniy, A. V.; Zherebtsov, O. M.; Martemyanov, V. P.; Zinoev, V. G.; Tarasenkov, V. G.; Aleshin, V. I.; Petelin, A. L.; Pavlov, S. V.; Izhutov, A. L.; Sazontov, S. A.; Ryazanov, D. K.; Gromov, M. O.; Afanasiev, V. V.; Matrosov, L. N.; Matrosova, M. Yu.

    2016-11-01

    In connection with the question of possible existence of sterile neutrino the laboratory on the basis of SM-3 reactor was created to search for oscillations of reactor antineutrino. A prototype of a neutrino detector with scintillator volume of 400 l can be moved at the distance of 6-11 m from the reactor core. The measurements of background conditions have been made. It is shown that the main experimental problem is associated with cosmic radiation background. Test measurements of dependence of a reactor antineutrino flux on the distance from a reactor core have been made. The prospects of search for oscillations of reactor antineutrino at short distances are discussed.

  19. Integral test of JENDL-3.3 on fast reactors

    International Nuclear Information System (INIS)

    Chiba, Gou; Hazama, Taira

    2003-05-01

    An integral test has been carried out to evaluate a performance of evaluated nuclear data library JENDL-3.3, which was newly released, in a view of applying neutronics analyses of fast reactors. Japan Nuclear Cycle Development Institute has a large amount of data of critical assembly experiments (ZPPR, BFS, MOZART and FCA) and power reactor tests (JOYO). The database was utilized in this test. In plutonium loaded cores, an improvement was observed about 0.3% ε k in criticality and 5% in the non-leakage term of sodium void reactivity by a revision form JENDL-3.2 to -3.3. These results shoed that the revision is valid in plutonium loaded cores. In uranium loaded cores, dependence of C/E values on control rod position became smaller in control rod worth in ZPPR cores. On the other hand, C/E values became worse both in criticality (0.6%εk) and in sodium void reactivity (30%) in BFS cores. The main cause was a revision of uranium-235 capture cross section, and it could not be concluded whether the revision is valid or not in uranium loaded cores. It is necessary to carry out a validation test at other independent critical experiments in which uranium fuel is used. (author)

  20. Using the PCRaster-POLFLOW approach to GIS-based modelling of coupled groundwater-surface water hydrology in the Forsmark Area

    Energy Technology Data Exchange (ETDEWEB)

    Jarsjoe, Jerker; Shibuo, Yoshihiro; Destouni, Georgia [Stockholm Univ. (Sweden). Dept. of Physical Geography and Quaternary Geology

    2004-09-01

    The catchment-scale hydrologic modelling approach PCRaster-POLFLOW permits the integration of environmental process modelling functions with classical GIS functions such as database maintenance and screen display. It has previously successfully been applied at relatively large river basins and catchments, such as Rhine, Elbe and Norrstroem, for modelling stream water flow and nutrient transport. In this study, we review the PCRaster-POLFLOW modelling approach and apply it using a relatively fine spatial resolution to the smaller catchment of Forsmark. As input we use data from SKB's database, which includes detailed data from Forsmark (and Simpevarp), since these locations are being investigated as part of the process to find a suitable location for a deep repository for spent nuclear fuel. We show, by comparison with independently measured, area-averaged runoff data, that the PCRaster-POLFLOW model produces results that, without using site-specific calibration, agree well with these independent measurements. In addition, we deliver results for four planned hydrological stations within the Forsmark catchment thus allowing for future direct comparisons with streamflow monitoring. We also show that, and how, the PCRaster-POLFLOW model in its present state can be used for predicting average seasonal streamflow. The present modelling exercise provided insights into possible ways of extending and using the PCRaster-POLFLOW model for applications beyond its current main focus of surface water hydrology. In particular, regarding analysis of possible surface water-groundwater interactions, we identify the Analytic Element Method for groundwater modelling together with its GIS-based pre- and post processor ArcFlow as suitable and promising for use in combination with the PCRaster-POLFLOW modelling approach. Furthermore, for transport modelling, such as that of radionuclides entering the coupled shallow groundwater-surface water hydrological system from possible deep

  1. Using the PCRaster-POLFLOW approach to GIS-based modelling of coupled groundwater-surface water hydrology in the Forsmark Area

    International Nuclear Information System (INIS)

    Jarsjoe, Jerker; Shibuo, Yoshihiro; Destouni, Georgia

    2004-09-01

    The catchment-scale hydrologic modelling approach PCRaster-POLFLOW permits the integration of environmental process modelling functions with classical GIS functions such as database maintenance and screen display. It has previously successfully been applied at relatively large river basins and catchments, such as Rhine, Elbe and Norrstroem, for modelling stream water flow and nutrient transport. In this study, we review the PCRaster-POLFLOW modelling approach and apply it using a relatively fine spatial resolution to the smaller catchment of Forsmark. As input we use data from SKB's database, which includes detailed data from Forsmark (and Simpevarp), since these locations are being investigated as part of the process to find a suitable location for a deep repository for spent nuclear fuel. We show, by comparison with independently measured, area-averaged runoff data, that the PCRaster-POLFLOW model produces results that, without using site-specific calibration, agree well with these independent measurements. In addition, we deliver results for four planned hydrological stations within the Forsmark catchment thus allowing for future direct comparisons with streamflow monitoring. We also show that, and how, the PCRaster-POLFLOW model in its present state can be used for predicting average seasonal streamflow. The present modelling exercise provided insights into possible ways of extending and using the PCRaster-POLFLOW model for applications beyond its current main focus of surface water hydrology. In particular, regarding analysis of possible surface water-groundwater interactions, we identify the Analytic Element Method for groundwater modelling together with its GIS-based pre- and post processor ArcFlow as suitable and promising for use in combination with the PCRaster-POLFLOW modelling approach. Furthermore, for transport modelling, such as that of radionuclides entering the coupled shallow groundwater-surface water hydrological system from possible deep

  2. Forsmark site investigation. Detailed ground magnetic survey and lineament interpretation in the Forsmark area, 2006-2007

    Energy Technology Data Exchange (ETDEWEB)

    Isaksson, Hans; Thunehed, Hans; Pitkaenen, Timo; Keisu, Mikael (GeoVista AB, Luleaa (SE))

    2007-12-15

    The report presents detailed ground magnetic measurements carried out on an 11.1 km2 area in the Forsmark site investigation area. The main objective of this activity is to determine a detailed ground magnetic representation of the bedrock. The results from previous surveys were encouraging and have led to a broad geophysical programme for investigation of lineaments at Forsmark. This report comprises the results from the second and final phase of the extended survey programme and a compilation and summary of all phases in the programme. On ground and on lake ice, a grid with parallel lines was staked. Measurements of the magnetic total field were carried out along profiles, perpendicular to the staked lines, with a profile spacing of 10 m and a station spacing of 5 m. Measurements on the ice-covered sea bays were carried out by a two man crew. One crew member walked along the survey lines, carrying a RTK-GPS guiding the other crew member who measured the magnetic total field. No seaborne survey was carried out in the final phase. Previously, using a high accuracy RTK-GPS unit for boat navigation gave a seaborne survey grid of on average 10 m line spacing and 2-3 m station spacing. In total 427,238 magnetic survey stations have been measured and an area of 4.7 km2 has been surveyed from boat. The magnetic pattern in the survey area can be divided into six main areas with different magnetic character. Along the southwest margin of the survey area the magnetic pattern is intensely banded with rapidly changing low and highly magnetic bands striking southeast-northwest, which to the northeast changes to a gentler, banded pattern of low to moderate magnetic intensity. To the northeast, at the SFR office and along the coastline to the southeast, the pattern is again intensely banded with, southeast-northwest trending, rapidly changing low and highly magnetic bands. These two banded structures probably forms fold limbs of a common fold with a northwest oriented fold axis

  3. 3D CAD model of the subcritical nuclear reactor of IPN

    International Nuclear Information System (INIS)

    Pahuamba V, F. de J.; Delfin L, A.; Gomez T, A.; Ibarra R, G.; Del Valle G, E.; Sanchez R, A.

    2016-09-01

    The three-dimensional (3D) CAD model of the subcritical reactor Chicago model 9000 of Instituto Politecnico Nacional (IPN) allows obtaining a 3D view with the dimensions of each of its components, such as: natural uranium cylindrical rods, fuel elements, hexagonal reactor core arrangement, cylindrical stainless steel tank containing the core, fuel element support grids and reactor water cleaning system. As a starting point for the development of the model, the Chicago model 9000 subcritical reactor manual provided by the manufacturer was used, the measurement and verification of the components to adapt the geometric, physical and mechanical characteristics was carried out and materials standards were used to obtain a design that allows to elaborate a new manual according to the specifications. In addition, the 3D models of the building of the Advanced Physics Laboratory, neutron generator, cobalt source and the corridors connecting to the subcritical reactor facility were developed, allowing an animated ride, developed by computer-aided design software. The manual provided by the company Nuclear Chicago, dates from the year 1959 and presents diverse deviations in the design and dimensions of the reactor components. The model developed; in addition to supporting the development of the new manual represents a learning tool to visualize the reactor components. (Author)

  4. Quarterly report of the Nuclear Power Inspectorate October - December 1981

    International Nuclear Information System (INIS)

    1982-01-01

    The Inspectorate is the supervising authority of nuclear installations. The disturbances of reactor operations during the 4th quarter are described, e.g. 9 reactor trips. The operation of waste processing at Forsmark is discussed and the inspection of the facilities of ASEA-ATOM and Studsvik Energiteknik are dealt with. (G.B.)

  5. Study on the reactivity behavior partially loaded reactor cores using SIMULATE-3

    International Nuclear Information System (INIS)

    Holzer, Robert; Zeitz, Andreas; Grimminger, Werner; Lubczyk, Tobias

    2009-01-01

    The reactor core design for the NPP Gundremmingen unit B and C is performed since several years using the validated 3D reactor core calculation program SIMULATE-3. The authors describe a special application of the program to study the reactivity for different partial core loadings. Based on the comparison with results of the program CASMO-4 the program SIMULATE-3 was validated for the calculation of partially loaded reactor cores. For the planned reactor operation in NPP Gundremmingen using new MOX fuel elements the reactivity behavior was studied with respect to the KTA-Code requirements.

  6. Inventory of vegetation and benthos in newly laid and natural ponds in Forsmark 2012; Inventering av vegetation och bottenfauna i nyanlagda och naturliga goelar i Forsmark 2012

    Energy Technology Data Exchange (ETDEWEB)

    Qvarfordt, Susanne; Wallin, Anders; Borgiel, Micke [Sveriges Vattenekologer AB, Vingaaker (Sweden)

    2013-01-15

    SKB plans to build a repository for the spent nuclear fuel. The repository is planned to be built in Forsmark and constitutes installations above and below ground. The building and operation of the construction will involve activities that might affect the nature in the area. The impact means, among other things, that a small water body, which today is a reproduction site for the red listed pool frog (Rana lessonae), will disappear. The lost locality for the pool frog has been compensated by creating four new ponds in the Forsmark area. This study is part of the follow-up of these new habitats. The aim is to describe the plant and animal communities in the ponds, and follow the succession, i.e. the development of the habitats. The study also includes two natural ponds that will serve as reference objects. The survey of vegetation and invertebrate fauna in the ponds was conducted in October 2012. The results show that the new ponds had low coverage of submersed vegetation and the species composition in the plant communities differed between the ponds. The reference ponds also had different plant communities, both in terms of species composition and coverage. This indicates that the species composition of the plant communities in the new ponds will likely depend on physical factors specific to the respective pond, but that higher vegetation coverage can be expected over time in all new ponds. The reference ponds had similar animal communities that differed from the animal communities in the new ponds. The similar species composition in the reference ponds, despite the variety of plant communities, suggests that similar animal communities are likely to develop in the new ponds, even if the plant communities continues to be different. Water chemical sampling has also been conducted in the ponds during 2012. A comparison of the inorganic environment (with regard to analysed ions) showed that the reference ponds had relatively similar ion compositions with little

  7. Estimation of reactor pool water temperature after shutdown in JRR-3M

    International Nuclear Information System (INIS)

    Yagi, Masahiro; Sato, Mitsugu; Kakefuda, Kazuhiro

    1999-01-01

    The reactor pool water temperature increasing by the decay heat was estimated by calculation. The reactor pool water temperature was calculated by increased enthalpy that was estimated by the reactor decay heat, the heat released from the reactor biological shielding concrete, reactor pool water surface, the heat conduction from the canal and the core inlet piping. These results of calculation were compared with the past measured data. As the results of estimation, after the JRR-3M shutdown, the calculated reactor pool temperature first increased sharply. This is because the decay heat was the major contribution. And then, rate of increased reactor pool temperature decreased. This is because the ratio of heat released from reactor biological shielding concrete and core inlet piping to the decay heat increased. Besides, the calculated reactor pool water temperature agreed with the past measured data in consequence of correcting the decay heat and the released heat. The corrected coefficient k 1 of decay heat was 0.74 - 0.80. And the corrected coefficient k 2 of heat released from the reactor biological shielding concrete was 3.5 - 4.5. (author)

  8. RELAP5/MOD 3.3 analysis of Reactor Coolant Pump Trip event at NPP Krsko

    International Nuclear Information System (INIS)

    Bencik, V.; Debrecin, N.; Foretic, D.

    2003-01-01

    In the paper the results of the RELAP5/MOD 3.3 analysis of the Reactor Coolant Pump (RCP) Trip event at NPP Krsko are presented. The event was initiated by an operator action aimed to prevent the RCP 2 bearing damage. The action consisted of a power reduction, that lasted for 50 minutes, followed by a reactor and a subsequent RCP 2 trip when the reactor power was reduced to 28 %. Two minutes after reactor trip, the Main Steam Isolation Valves (MSIV) were isolated and the steam dump flow was closed. On the secondary side the Steam Generator (SG) pressure rose until SG 1 Safety Valve (SV) 1 opened. The realistic RELAP5/MOD 3.3 analysis has been performed in order to model the particular plant behavior caused by operator actions. The comparison of the RELAP5/MOD 3.3 results with the measurement for the power reduction transient has shown small differences for the major parameters (nuclear power, average temperature, secondary pressure). The main trends and physical phenomena following the RCP Trip event were well reproduced in the analysis. The parameters that have the major influence on transient results have been identified. In the paper the influence of SG 1 relief and SV valves on transient results was investigated more closely. (author)

  9. Modelling of MOCVD Reactor: New 3D Approach

    Science.gov (United States)

    Raj, E.; Lisik, Z.; Niedzielski, P.; Ruta, L.; Turczynski, M.; Wang, X.; Waag, A.

    2014-04-01

    The paper presents comparison of two different 3D models of vertical, rotating disc MOCVD reactor used for 3D GaN structure growth. The first one is based on the reactor symmetry, while the second, novel one incorporates only single line of showerhead nozzles. It is shown that both of them can be applied interchangeably regarding the phenomena taking place within the processing area. Moreover, the importance of boundary conditions regarding proper modelling of showerhead cooling and the significance of thermal radiation on temperature field within the modelled structure are presented and analysed. The last phenomenon is erroneously neglected in most of the hitherto studies.

  10. Modelling of MOCVD reactor: new 3D approach

    International Nuclear Information System (INIS)

    Raj, E; Lisik, Z; Niedzielski, P; Ruta, L; Turczynski, M; Wang, X; Waag, A

    2014-01-01

    The paper presents comparison of two different 3D models of vertical, rotating disc MOCVD reactor used for 3D GaN structure growth. The first one is based on the reactor symmetry, while the second, novel one incorporates only single line of showerhead nozzles. It is shown that both of them can be applied interchangeably regarding the phenomena taking place within the processing area. Moreover, the importance of boundary conditions regarding proper modelling of showerhead cooling and the significance of thermal radiation on temperature field within the modelled structure are presented and analysed. The last phenomenon is erroneously neglected in most of the hitherto studies.

  11. Characteristics of D(-3)He fueled FRC reactor: ARTEMIS-L

    Science.gov (United States)

    Momota, H.; Motojima, O.; Okamoto, M.; Sudo, S.; Tomita, Y.; Yamaguchi, S.; Iiyoshi, A.; Onozuka, M.; Ohnishi, M.; Uenosono, C.

    1993-11-01

    The characteristics of D(-3)He fueled commercial fusion reactor ARTEMIS-L are discussed. By using favorable characteristics of a field-reversed configuration, the fusion plasma of ARTEMIS-L becomes compact and its veta-value is extremely high. Consequently, it is possible to construct an economical fusion power plant based on this concept. The life of the structural materials is found during the full reactor life (30 years) and the safety of the reactor is intrinsic to D(-3)He fuels. The amount of disposed materials is rather small and the level of the intruder dose is so low that the plant appears to be acceptable in regards to the environment.

  12. PR-EDB: Power Reactor Embrittlement Database Version 3

    International Nuclear Information System (INIS)

    Wang, Jy-An John; Subramani, Ranjit

    2008-01-01

    The aging and degradation of light-water reactor pressure vessels is of particular concern because of their relevance to plant integrity and the magnitude of the expected irradiation embrittlement. The radiation embrittlement of reactor pressure vessel materials depends on many factors, such as neutron fluence, flux, and energy spectrum, irradiation temperature, and preirradiation material history and chemical compositions. These factors must be considered to reliably predict pressure vessel embrittlement and to ensure the safe operation of the reactor. Large amounts of data from surveillance capsules are needed to develop a generally applicable damage prediction model that can be used for industry standards and regulatory guides. Furthermore, the investigations of regulatory issues such as vessel integrity over plant life, vessel failure, and sufficiency of current codes, Standard Review Plans (SRPs), and Guides for license renewal can be greatly expedited by the use of a well-designed computerized database. The Power Reactor Embrittlement Database (PR-EDB) is such a comprehensive collection of data for U.S. designed commercial nuclear reactors. The current version of the PR-EDB lists the test results of 104 heat-affected-zone (HAZ) materials, 115 weld materials, and 141 base materials, including 103 plates, 35 forgings, and 3 correlation monitor materials that were irradiated in 321 capsules from 106 commercial power reactors. The data files are given in dBASE format and can be accessed with any personal computer using the Windows operating system. 'User-friendly' utility programs have been written to investigate radiation embrittlement using this database. Utility programs allow the user to retrieve, select and manipulate specific data, display data to the screen or printer, and fit and plot Charpy impact data. The PR-EDB Version 3.0 upgrades Version 2.0. The package was developed based on the Microsoft .NET framework technology and uses Microsoft Access for

  13. PR-EDB: Power Reactor Embrittlement Database - Version 3

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Jy-An John [ORNL; Subramani, Ranjit [ORNL

    2008-03-01

    The aging and degradation of light-water reactor pressure vessels is of particular concern because of their relevance to plant integrity and the magnitude of the expected irradiation embrittlement. The radiation embrittlement of reactor pressure vessel materials depends on many factors, such as neutron fluence, flux, and energy spectrum, irradiation temperature, and preirradiation material history and chemical compositions. These factors must be considered to reliably predict pressure vessel embrittlement and to ensure the safe operation of the reactor. Large amounts of data from surveillance capsules are needed to develop a generally applicable damage prediction model that can be used for industry standards and regulatory guides. Furthermore, the investigations of regulatory issues such as vessel integrity over plant life, vessel failure, and sufficiency of current codes, Standard Review Plans (SRPs), and Guides for license renewal can be greatly expedited by the use of a well-designed computerized database. The Power Reactor Embrittlement Database (PR-EDB) is such a comprehensive collection of data for U.S. designed commercial nuclear reactors. The current version of the PR-EDB lists the test results of 104 heat-affected-zone (HAZ) materials, 115 weld materials, and 141 base materials, including 103 plates, 35 forgings, and 3 correlation monitor materials that were irradiated in 321 capsules from 106 commercial power reactors. The data files are given in dBASE format and can be accessed with any personal computer using the Windows operating system. "User-friendly" utility programs have been written to investigate radiation embrittlement using this database. Utility programs allow the user to retrieve, select and manipulate specific data, display data to the screen or printer, and fit and plot Charpy impact data. The PR-EDB Version 3.0 upgrades Version 2.0. The package was developed based on the Microsoft .NET framework technology and uses Microsoft Access for

  14. Mineralogy and geochemistry of rocks and fracture fillings from Forsmark and Oskarshamn: Compilation of data for SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Drake, Henrik; Sandstroem, Bjoern [Isochron GeoConsulting HB, Goeteborg (Sweden); Tullborg, Eva-Lena [Terralogica AB, Graabo (Sweden)

    2006-11-15

    This report is a compilation of the so far available data for the safety assessment SR-Can carried out by SKB. The data consists of mineralogy, geochemistry, porosity, density and redox properties for both dominating rock types and fracture fillings at the Forsmark and Oskarshamn candidate areas. In addition to the compilation of existing information, the aim has been to identify missing data and to clarify some conception of e.g. deformation zones. The objective of the report is to present the available data requested for the modelling of the chemical stability of the two sites. The report includes no interpretation of the data.

  15. Operating reactors licensing actions summary. Vol. 3, No. 3

    International Nuclear Information System (INIS)

    1983-04-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regularory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program

  16. Report on generation IV technical working group 3 : liquid metal reactors

    International Nuclear Information System (INIS)

    Lineberry, M. J.; Rosen, S. L.; Sagayama, Y.

    2002-01-01

    This paper reports on the first round of R and D roadmap activities of the Generation IV (Gen IV) Technical Working Group (TWG) 3, on liquid metal-cooled reactors. Liquid metal coolants give rise to fast spectrum systems, and thus the reactor systems considered in this TWG are all fast reactors. Gas-cooled fast reactors are considered in the context of TWG 2. As is noted in other Gen IV papers, this first round activity is termed ''screening for potential'', and includes collecting the most complete set of liquid metal reactor/fuel cycle system concepts possible and evaluating the concepts against the Gen IV principles and goals. Those concepts or concept groups that meet the Gen IV principles and which are deemed to have reasonable potential to meet the Gen IV goals will pass to the next round of evaluation. Although we sometimes use the terms ''reactor'' or ''reactor system'' by themselves, the scope of the investigation by TWG 3 includes not only the reactor systems, but very importantly the closed fuel recycle system inevitably required by fast reactors. The response to the DOE Request for Information (RFI) on liquid metal reactor/fuel cycle systems from principal investigators, laboratories, corporations, and other institutions, was robust and gratifying. Thirty three liquid metal concept descriptions, from eight different countries, were ultimately received. The variation in the scope, depth, and completeness of the responses created a significant challenge for the group, but the TWG made a very significant effort not to screen out concepts early in the process

  17. Benchmark tests of JENDL-3.2 for thermal and fast reactors

    International Nuclear Information System (INIS)

    Takano, Hideki

    1995-01-01

    Benchmark calculations for a variety of thermal and fast reactors have been performed by using the newly evaluated JENDL-3 Version-2 (JENDL-3.2) file. In the thermal reactor calculations for the uranium and plutonium fueled cores of TRX and TCA, the k eff and lattice parameters were well predicted. The fast reactor calculations for ZPPR-9 and FCA assemblies showed that the k eff , reactivity worth of Doppler, sodium void and control rod, and reaction rate distribution were in a very good agreement with the experiments. (author)

  18. Statistics of modelled conductive fractures based on Laxemar and Forsmark. Site descriptive model data

    Energy Technology Data Exchange (ETDEWEB)

    Stigsson, Martin

    2009-12-15

    The objectives of this report is to investigate the frequency of fractures assumed to be water conductive, i.e. open or partly open and directly or indirectly connected to a source. Also the distribution of total transmissivity in 100 m and 20 m horizontal sections and 8 m vertical sections is calculated. The report is only intended to serve as input to the SER, Site Engineering Report, at Laxemar and Forsmark. The input data for the analyses is taken, as is, from the Discrete Fracture Network sections in published reports. No evaluation that the model parameters are appropriate for the task or sensitivity analysis is performed. The tunnels and deposition holes are modelled as scanlines which is a very coarse approximation, but it may give some rough estimation of the frequency of the water bearing features, especially for the larger ones, and the total transmissivity in a section

  19. Statistics of modelled conductive fractures based on Laxemar and Forsmark. Site descriptive model data

    International Nuclear Information System (INIS)

    Stigsson, Martin

    2009-12-01

    The objectives of this report is to investigate the frequency of fractures assumed to be water conductive, i.e. open or partly open and directly or indirectly connected to a source. Also the distribution of total transmissivity in 100 m and 20 m horizontal sections and 8 m vertical sections is calculated. The report is only intended to serve as input to the SER, Site Engineering Report, at Laxemar and Forsmark. The input data for the analyses is taken, as is, from the Discrete Fracture Network sections in published reports. No evaluation that the model parameters are appropriate for the task or sensitivity analysis is performed. The tunnels and deposition holes are modelled as scanlines which is a very coarse approximation, but it may give some rough estimation of the frequency of the water bearing features, especially for the larger ones, and the total transmissivity in a section

  20. Nuclear research reactor 0.5 to 3 MW

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-05-15

    This nuclear reactor has been designed for radioisotope production, basic and applied research in reactor physics and nuclear engineering, neutron-beam experimentation, irradiation of various materials and training of scientific and technical personnel. It is located in the 'Production Area' of the Nuclear Technology Center. It is equipped with the necessary facilities for large-scale production of radioisotopes to be used in medicine as well as for other scientific and industrial purposes. In addition, it has a Neutronography Facility and the required equipment to perform Neutron-Activation Analysis. It is an open pool-type reactor, moderated and cooled with light water, fuelled with 20% enriched uranium. Its reflector are graphite and water. It has plate-type fuel elements clad in aluminium. The reactor core is located near the bottom of the demineralized water pool. It includes fuel elements, reflector and sample-holding devices for materials to be irradiated. This kind of configuration, which is widely used in research reactors, provides a high degree of safety since it prevents the core from becoming exposed under any circumstance and does not require any cooling system during reactor shutdown. Power output is between 0.5 to 3 MW{sub TH}, with a minimum thermal neutron flux of approx, 10{sup 13} n/cm{sup 2}{center_dot}sec, at irradiation zone almost with no modifications. Heat extraction is achieved by means of a cooling circuit which comprises two circulation pumps and a plate-type heat exchanger. Final heat dissipation to the atmosphere is performed through another cooling circuit which includes two circulation pumps and a cooling tower. Reactor control is accomplished with five neutron-absorbing rods positioned by means of especially designed elements and governed by the reactor's instrumentation and control system. Should an abnormal situation arise, gravity causes the rods to fall automatically, thus extinguishing the nuclear reaction. The reactor

  1. Nuclear research reactor 0.5 to 3 MW

    International Nuclear Information System (INIS)

    1992-05-01

    This nuclear reactor has been designed for radioisotope production, basic and applied research in reactor physics and nuclear engineering, neutron-beam experimentation, irradiation of various materials and training of scientific and technical personnel. It is located in the 'Production Area' of the Nuclear Technology Center. It is equipped with the necessary facilities for large-scale production of radioisotopes to be used in medicine as well as for other scientific and industrial purposes. In addition, it has a Neutronography Facility and the required equipment to perform Neutron-Activation Analysis. It is an open pool-type reactor, moderated and cooled with light water, fuelled with 20% enriched uranium. Its reflector are graphite and water. It has plate-type fuel elements clad in aluminium. The reactor core is located near the bottom of the demineralized water pool. It includes fuel elements, reflector and sample-holding devices for materials to be irradiated. This kind of configuration, which is widely used in research reactors, provides a high degree of safety since it prevents the core from becoming exposed under any circumstance and does not require any cooling system during reactor shutdown. Power output is between 0.5 to 3 MW TH , with a minimum thermal neutron flux of approx, 10 13 n/cm 2 ·sec, at irradiation zone almost with no modifications. Heat extraction is achieved by means of a cooling circuit which comprises two circulation pumps and a plate-type heat exchanger. Final heat dissipation to the atmosphere is performed through another cooling circuit which includes two circulation pumps and a cooling tower. Reactor control is accomplished with five neutron-absorbing rods positioned by means of especially designed elements and governed by the reactor's instrumentation and control system. Should an abnormal situation arise, gravity causes the rods to fall automatically, thus extinguishing the nuclear reaction. The reactor building has a ventilation

  2. EL-3 dismantling of an experimental reactor

    International Nuclear Information System (INIS)

    1989-01-01

    The EL3 experimental reactor has been definitively stopped in march 1979. Its decommissioning has been pronounced in the end of 1982. This article is consecrated at decontamination and dismantling works necessited by its passage at the dismantling level 2 [fr

  3. THM-issues in repository rock. Thermal, mechanical, thermo-mechanical and hydro-mechanical evolution of the rock at the Forsmark and Laxemar sites

    Energy Technology Data Exchange (ETDEWEB)

    Hoekmark, Harald; Loennqvist, Margareta; Faelth, Billy (Clay Technology AB, Lund (Sweden))

    2010-05-15

    The present report addresses aspects of the Thermo-Hydro-Mechanical (THM) evolution of the repository host rock that are of potential importance to the SR-Site safety assessment of a KBS-3 type spent nuclear fuel repository. The report covers the evolution of rock temperatures, rock stresses, pore pressures and fracture transmissivities during the excavation and operational phase, the temperate phase and a glacial cycle on different scales. The glacial cycle is assumed to include a period of pre-glacial permafrost with lowered temperatures and with increased pore pressures in the rock beneath the impermeable permafrost layer. The report also addresses the question of the peak temperature reached during the early temperate phase in the bentonite buffer surrounding the spent fuel canisters. The main text is devoted exclusively to the projected THM evolution of the rock at the Forsmark site in central Sweden. The focus is on the potential for stress-induced failures, i.e. spalling, in the walls of the deposition holes and on changes in the transmissivity of fractures and deformation zones. All analyses are conducted by a combination of numerical tools (3DEC) and analytical solutions. All phases are treated separately and independently of each other, although in reality construction will overlap with heat generation because of the step-by-step excavation/deposition approach with some 50 years between deposition of the first and last canisters. It is demonstrated here that the thermal and thermo-mechanical evolution of the near-field will be independent of heat generated by canisters that were deposited in the past, provided that deposition is made in an orderly fashion, deposition area by deposition area. Peak temperatures and near-field stresses can, consequently, be calculated as if all canisters were deposited simultaneously. The canister and tunnel spacing is specified such that the peak buffer temperature will not exceed 100 deg C in any deposition hole, i.e. not

  4. Application of autoregressive methods and Lyapunov coefficients for instability studies of nuclear reactors

    International Nuclear Information System (INIS)

    Aruquipa Coloma, Wilmer

    2017-01-01

    Nuclear reactors are susceptible to instability, causing oscillations in reactor power in specific working regions characterized by determined values of power and coolant mass flow. During reactor startup, there is a greater probability that these regions of instability will be present; another reason may be due to transient processes in some reactor parameters. The analysis of the temporal evolution of the power reveals a stable or unstable process after the disturbance in a light water reactor of type BWR (Boiling Water Reactor). In this work, the instability problem was approached in two ways. The first form is based on the ARMA (Autoregressive Moving Average models) model. This model was used to calculate the Decay Ratio (DR) and natural frequency (NF) of the oscillations, parameters that indicate if the one power signal is stable or not. In this sense, the DRARMA code was developed. In the second form, the problems of instability were analyzed using the classical concepts of non-linear systems, such as Lyapunov exponents, phase space and attractors. The Lyapunov exponents quantify the exponential divergence of the trajectories initially close to the phase space and estimate the amount of chaos in a system; the phase space and the attractors describe the dynamic behavior of the system. The main aim of the instability phenomena studies in nuclear reactors is to try to identify points or regions of operation that can lead to power oscillations conditions. The two approaches were applied to two sets of signals. The first set comes from signals of instability events of the commercial Forsmark reactors 1 and 2 and were used to validate the DRARMA code. The second set was obtained from the simulation of transient events of the Peach Bottom reactor; for the simulation, the PARCS and RELAP5 codes were used for the neutronic/thermal hydraulic coupling calculation. For all analyzes made in this work, the Matlab software was used due to its ease of programming and

  5. Use of plate fuel elements for the RA3 reactor

    International Nuclear Information System (INIS)

    Parodi, C.; Parkanski, D.; Higa, M.; Marajofsky, A.

    1992-01-01

    The RA3 reactor is a pool reactor, redesigned for 5 MW dissipation. Nineteen plates are used in each fuel element. The utilization of 20% enriched U, gives the possibility of the development of rod type fuel with Al/U 3 O 8 cermets. The thermohydraulic and neutronic conditions are studied in this work in order to satisfy the stipulated power. In addition, the fabrication conditions of Al/U 3 O 8 and Al/U 3 O 8 /Zr H 2 cermets with densities within the limits imposed by the thermohydraulics and neutronics conditions are studied. (author)

  6. Characteristics of D-3He fueled frc reactor: ARTEMIS-L

    International Nuclear Information System (INIS)

    Momota, H.; Motojima, O.; Okamoto, M.; Sudo, S.; Tomita, Y.; Yamaguchi, S.; Iiyoshi, A.; Onozuka, M.; Ohnishi, M.; Uenosono, C.

    1993-11-01

    The paper introduces briefly the scenario and discuss the attractive characteristics of D-3He fueled commercial fusion reactor ARTEMIS-L. By using favorable characteristics of a field-reversed configuration, the fusion plasma of ARTEMIS-L is compact and its beta-value is extremely high. One find consequently a possibility of constructing an economical fusion power power plant on this prospect. The life of the structural materials is sound during the full reactor life (30 years) and the safety of the reactor is intrinsic to D-3He fuels. The amount of disposed materials is rather small and the level of these intruder dose is so low that the plant appears to be acceptable in view of the environment. (author)

  7. Summary of the 3rd workshop on the reduced-moderation water reactor

    International Nuclear Information System (INIS)

    Ishikawa, Nobuyuki; Nakatsuka, Tohru; Iwamura, Takamichi

    2000-06-01

    The research activities of a Reduced-Moderation Water Reactor (RMWR) are being performed for a development of the next generation water-cooled reactor. A workshop on the RMWR was held on March 3rd 2000 aiming to exchange information between JAERI and other organizations such as universities, laboratories, utilities and vendors. This report summarizes the contents of lectures and discussions on the workshop. The 1st workshop was held on March 1998 focusing on the review of the research activities and future research plan. The succeeding 2nd workshop was held on March 1999 focusing on the topics of the plutonium utilization in water-cooled reactors. The 3rd workshop was held on March 3rd 2000, which was attended by 77 participants. The workshop began with a lecture titled 'Recent Situation Related to Reduced-Moderation Water Reactor (RMWR)', followed by 'Program on MOX Fuel Utilization in Light Water Reactors' which is the mainstream scenario of plutonium utilization by utilities, and 'Feasibility Studies on Commercialized Fast Breeder Reactor Cycle System' mainly conducted by Japan Nuclear Cycle Development Institute (JNC). Also, following lectures were given as the recent research activities in JAERI: 'Progress in Design Study on Reduced-Moderation Water Reactors', 'Long-Term Scenarios of Power Reactors and Fuel Cycle Development and the Role of Reduced Moderation Water Reactors', 'Experimental and Analytical Study on Thermal Hydraulics' and Reactor Physics Experiment Plan using TCA'. At the end of the workshop, a general discussion was performed about the research and development of the RMWR. This report includes the original papers presented at the workshop and summaries of the questions and answers for each lecture and general discussion, as well as presentation viewgraphs, program and participant list as appendixes. The 7 of the presented papers are indexed individually. (J.P.N.)

  8. Summary of the 3rd workshop on the reduced-moderation water reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ishikawa, Nobuyuki; Nakatsuka, Tohru; Iwamura, Takamichi [eds.

    2000-06-01

    The research activities of a Reduced-Moderation Water Reactor (RMWR) are being performed for a development of the next generation water-cooled reactor. A workshop on the RMWR was held on March 3rd 2000 aiming to exchange information between JAERI and other organizations such as universities, laboratories, utilities and vendors. This report summarizes the contents of lectures and discussions on the workshop. The 1st workshop was held on March 1998 focusing on the review of the research activities and future research plan. The succeeding 2nd workshop was held on March 1999 focusing on the topics of the plutonium utilization in water-cooled reactors. The 3rd workshop was held on March 3rd 2000, which was attended by 77 participants. The workshop began with a lecture titled 'Recent Situation Related to Reduced-Moderation Water Reactor (RMWR)', followed by 'Program on MOX Fuel Utilization in Light Water Reactors' which is the mainstream scenario of plutonium utilization by utilities, and 'Feasibility Studies on Commercialized Fast Breeder Reactor Cycle System' mainly conducted by Japan Nuclear Cycle Development Institute (JNC). Also, following lectures were given as the recent research activities in JAERI: 'Progress in Design Study on Reduced-Moderation Water Reactors', 'Long-Term Scenarios of Power Reactors and Fuel Cycle Development and the Role of Reduced Moderation Water Reactors', 'Experimental and Analytical Study on Thermal Hydraulics' and Reactor Physics Experiment Plan using TCA'. At the end of the workshop, a general discussion was performed about the research and development of the RMWR. This report includes the original papers presented at the workshop and summaries of the questions and answers for each lecture and general discussion, as well as presentation viewgraphs, program and participant list as appendixes. The 7 of the presented papers are indexed individually. (J.P.N.)

  9. Geological evolution, palaeoclimate and historical development of the Forsmark and Laxemar-Simpevarp areas. Site descriptive modelling SDM-Site

    Energy Technology Data Exchange (ETDEWEB)

    Soederbaeck, Bjoern [ed.

    2008-06-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterization at two different locations, the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. The site investigations started in 2002 and were completed in 2007. The analysis and modelling of data from the site investigations, which have taken place during and after these investigations, provide a foundation for the development of an integrated, multidisciplinary site descriptive model (SDM) for each of the two sites. A site descriptive model constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere, as well as those natural processes that affect or have affected their long-term development. Hitherto, a number of reports presenting preliminary site descriptive models for Forsmark and Laxemar-Simpevarp have been published. In these reports, the evolutionary and historical aspects of the site were included in a separate chapter. The present report comprises a further elaboration of the evolutionary and historical information included in the preliminary SDM reports, but presented here in a separate, supplementary report to the final site description, SDM-Site. The report is common to the two investigated areas, and the overall objective is to describe the long-term geological evolution, the palaeoclimate, and the post-glacial development of ecosystems and of the human population at the two sites. The report largely consists of a synthesis of information derived from the scientific literature and other sources not related to the site investigations. However, considerable information from the site investigations that has contributed to our understanding of the past development at each site is also included. This unique synthesis of both published information in a regional perspective and new site-specific information breaks new ground in our understanding

  10. Geological evolution, palaeoclimate and historical development of the Forsmark and Laxemar-Simpevarp areas. Site descriptive modelling SDM-Site

    International Nuclear Information System (INIS)

    Soederbaeck, Bjoern

    2008-06-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterization at two different locations, the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. The site investigations started in 2002 and were completed in 2007. The analysis and modelling of data from the site investigations, which have taken place during and after these investigations, provide a foundation for the development of an integrated, multidisciplinary site descriptive model (SDM) for each of the two sites. A site descriptive model constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere, as well as those natural processes that affect or have affected their long-term development. Hitherto, a number of reports presenting preliminary site descriptive models for Forsmark and Laxemar-Simpevarp have been published. In these reports, the evolutionary and historical aspects of the site were included in a separate chapter. The present report comprises a further elaboration of the evolutionary and historical information included in the preliminary SDM reports, but presented here in a separate, supplementary report to the final site description, SDM-Site. The report is common to the two investigated areas, and the overall objective is to describe the long-term geological evolution, the palaeoclimate, and the post-glacial development of ecosystems and of the human population at the two sites. The report largely consists of a synthesis of information derived from the scientific literature and other sources not related to the site investigations. However, considerable information from the site investigations that has contributed to our understanding of the past development at each site is also included. This unique synthesis of both published information in a regional perspective and new site-specific information breaks new ground in our understanding

  11. Updated strategy and test of new concepts for groundwater flow modelling in Forsmark in preparation of site descriptive modelling stage 2.2

    Energy Technology Data Exchange (ETDEWEB)

    Follin, Sven [SF GeoLogic AB (Sweden); Johansson, Per-Olof [Artesia Grundvattenkonsult AB (Sweden); Leven, Jakob [Geosigma AB (Sweden); Hartley, Lee; Holton, David; McCarthy, Rachel; Roberts, David [Serco Assurance (United Kingdom)

    2007-01-15

    As part of the preliminary Site Descriptive Modelling (SDM version 1.2) for the Initial Site Investigation (ISI) stage at Forsmark, Simpevarp and Laxemar, a methodology was developed for constructing hydrogeological models of the crystalline bedrock. The methodology achieved reasonable success given the restricted amounts and types of data available at the time. Notwithstanding, several issues of concern have surfaced following the reviews of the preliminary site descriptions of the three sites. Possible solutions to parts of the problems have been discussed internally for a longer time and an integrated view and strategy forward has been formulated. The 'new strategy' is not a complete shift in methodology, however, but a refocusing on and clarification of the key aspects that the hydrogeological SDM needs to accomplish. In broad terms the basic principle of the 'new strategy' suggested is to develop an overall conceptual model that first establishes the major flowing deformation zones, and then gradually approaches determination of the hydraulic properties of the bedrock outside these zones in the potential repository volume. On each scale, the focus of the description should be on features/structures of significance on that scale. Clearly, a detailed (although statistical) description of the repository and canister deposition hole scale is the end goal, but this approach (which also is more the traditional approach in hydrogeology) is judged to provide a much better motivated overall geometrical description. Furthermore, the 'new strategy' puts more emphasis on field testing (e.g. interference tests) and data analyses and less on numerical simulation and calibration. That is, before extensive (and costly) simulations and model calibrations are made it needs to be clearly understood what could be the potential gains of carrying them out. This report presents the conceptual model development for Forsmark in preparation of the site

  12. Repository for spent nuclear fuel. Plant description layout D - Forsmark; Slutfoervarsanlaeggning foer anvaent kaernbraensle. Anlaeggningsbeskrivning layout D - Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    2010-07-15

    This document describes the final repository for spent nuclear fuel, SFK, which is located at Forsmark, in Oesthammar. The bedrock at the site is part of a so-called tectonic lens, in which the rock composition is relatively homogeneous and less deformed than outside the lens. The bedrock consists mainly of granite with high quartz content and good thermal conductivity. The central parts above ground are grouped in an operations area, located at the Soederviken on the south side of the intake duct for cooling water for nuclear power plant. Operating area is divided into an internal, secured portion, where the canisters of fuel are handled and there are links to the underground part, and a outer part, where the buffer, backfill and sealing used in the repository's barriers are produced. The above-ground part of the plant and also include storage of excavated rock, ventilation stations, and supplies of bentonite. The underground portion consists of a central area and a storage area. Caverns of the central area contain features for the underground operation. It communicates with the internal operating range above ground via a spiral ramp and several shafts. The ramp used to transport capsules of spent fuel and other heavy or bulky transport. The shafts are used to transport rock, buffer, backfill and staff, as well as for ventilation. The largest part of the space below ground is the repository where the canisters with the spent fuel are disposed. The capsules are deposited in vertical holes in the tunnels. When the deposit in a tunnel is complete, the tunnel is re-filled. The two main activities underground is rock work and disposal work, which are conducted separately from each other. Rock works covers all steps required to excavate tunnels and drill deposition holes, as well as to make temporary installations in the tunnels. To the landfill works count, besides the deposit of the capsule, the placement of the bentonite buffer in the deposition hole and

  13. Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods. Stage 8. Final report

    International Nuclear Information System (INIS)

    Pazsit, I.; Demaziere, C.; Arzhanov, V.

    2003-01-01

    This report constitutes Stage 8 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. A brief proposal for the continuation of this program in stage 9 is also given at the end of the report. The program executed in Stage 8 consists of three parts and the work performed in each part is summarized below. In Stage 7, an anomaly localisation algorithm was presented and applied to the Forsmark-1 channel instability event. This investigation was carried out with a set of static data that were typical of a generic BWR model, since no data except the Local Power Range Monitors (LPRMs) time signals recorded during the instability event were made accessible to us at that time. In the present Stage, these static data were obtained from Vattenfall Fuel AB, who used the SIMULATE-3 code. The first Section of this report is thus devoted to this anomaly localisation but this time with a relevant set of data, both regarding the static core conditions and regarding the LPRMs time signals. The noise source pointed out by the localisation algorithm was once again found to be very close to an unseated fuel assembly discovered during the fuel outage following the instability event. The localisation procedure relies in fact on the prior calculation of the reactor transfer function, carried out via the neutron noise simulator first presented in Stage 6 and later improved in Stage 7. The neutron noise simulator was also improved in this Stage. More precisely, a 2-D 2- group static core simulator was developed in order to calculate the static flux and the associated eigenvalue with a spatial discretization scheme compatible with the one in use in the neutron noise simulator, i.e. finite differences. It has generally been assumed that the Decay Ratio (DR), a parameter characterizing the stability of BWRs, is a space-independent parameter of the reactor, i.e. it is independent of which LPRM is used in the core to

  14. Integral test of JENDL-3.3 for thermal reactors

    International Nuclear Information System (INIS)

    Okumura, Keisuke; Mori, Takamasa

    2003-01-01

    Criticality benchmark testing was carried out for 59 experiments in various thermal reactors using a continues-energy Monte Carlo code MVP and its different libraries generated from JENDL-3.2, JENDL-3.3, JEF-2.2 and ENDF/B-VI (R8). From the benchmark results, we can say JENDL-3.3 generally gives better k eff values compared with other nuclear data libraries. However, further modification of JENDL-3.3 is expected to solve the following problems: 1) systematic underestimation of k eff depending on 235 U enrichment for the cores with low (less than 3wt.%) enriched uranium fueled cores, 2) dependence of C/E value of k eff on neutron spectrum and plutonium composition for MOX fueled cores. These are common problems for all of the nuclear data libraries used in this study. (author)

  15. Extension of the reactor dynamics code MGT-3D for pebblebed and blocktype high-temperature-reactors

    International Nuclear Information System (INIS)

    Shi, Dunfu

    2015-01-01

    The High Temperature Gas cooled Reactor (HTGR) is an improved, gas cooled nuclear reactor. It was chosen as one of the candidates of generation IV nuclear plants [1]. The reactor can be shut down automatically because of the negative reactivity feedback due to the temperature's increasing in designed accidents. It is graphite moderated and Helium cooled. The residual heat can be transferred out of the reactor core by inactive ways as conduction, convection, and thermal radiation during the accident. In such a way, a fuel temperature does not go beyond a limit at which major fission product release begins. In this thesis, the coupled neutronics and fluid mechanics code MGT-3D used for the steady state and time-dependent simulation of HTGRs, is enhanced and validated [2]. The fluid mechanics part is validated by SANA experiments in steady state cases as well as transient cases. The fuel temperature calculation is optimized by solving the heat conduction equation of the coated particles. It is applied in the steady state and transient simulation of PBMR, and the results are compared to the simulation with the old overheating model. New approaches to calculate the temperature profile of the fuel element of block-type HTGRs, and the calculation of the homogeneous conductivity of composite materials are introduced. With these new developments, MGT-3D is able to simulate block-type HTGRs as well. This extended MGT-3D is used to simulate a cuboid ceramic block heating experiment in the NACOK-II facility. The extended MGT-3D is also applied to LOFC and DLOFC simulation of GT-MHR. It is a fluid mechanics calculation with a given heat source. This calculation result of MGT-3D is verified with the calculation results of other codes. The design of the Japanese HTTR is introduced. The deterministic simulation of the LOFC experiment of HTTR is conducted with the Monte-Carlo code Serpent and MGT-3D, which is the LOFC Project organized by OECD/NEA [3]. With Serpent the burnup

  16. Development of the fast reactor group constant set JFS-3-J3.2R based on the JENDL-3.2

    CERN Document Server

    Chiba, G

    2002-01-01

    It is reported that the fast reactor group constant set JFS-3-J3.2 based on the newest evaluated nuclear data library JENDL3.2 has a serious error in the process of applying the weighting function. As the error affects greatly nuclear characteristics, and a corrected version of the reactor constant set, JFS-3-J3.2R, was developed, as well as lumped FP cross sections. The use of JFS-3-J3.2R improves the results of analyses especially on sample Doppler reactivity and reaction rate in the blanket region in comparison with those obtained using the JFS-3-J3.2.

  17. Development of 3D CFD simulation method in nuclear reactor safety analysis

    International Nuclear Information System (INIS)

    Rosli Darmawan; Mariah Adam

    2012-01-01

    One of the most prevailing issues in the operation of nuclear reactor is the safety of the system. Worldwide publicity on a few nuclear accidents as well as the notorious Hiroshima and Nagasaki bombing have always brought about public fear on anything related to nuclear. Most findings on the nuclear reactor accidents are closely related to the reactor cooling system. Thus, the understanding of the behaviour of reactor cooling system is very important to ensure the development and improvement on safety can be continuously done. Throughout the development of nuclear reactor technology, investigation and analysis on reactor safety have gone through several phases. In the early days, analytical and experimental methods were employed. For the last three decades 1D system level codes were widely used. The continuous development of nuclear reactor technology has brought about more complex system and processes of nuclear reactor operation. More detailed dimensional simulation codes are needed to assess these new reactors. This paper discusses the development of 3D CFD usage in nuclear reactor safety analysis worldwide. A brief review on the usage of CFD at Malaysia's Reactor TRIGA PUSPATI is also presented. (author)

  18. Large-signal, dynamic simulation of the slowpoke-3 nuclear heating reactor

    International Nuclear Information System (INIS)

    Tseng, C.M.; Lepp, R.M.

    1983-07-01

    A 2 MWt nuclear reactor, called SLOWPOKE-3, is being developed at the Chalk River Nuclear Laboratories (CRNL). This reactor, which is cooled by natural circulation, is designed to produce hot water for commercial space heating and perhaps generate some electricity in remote locations where the costs of alternate forms of energy are high. A large-signal, dynamic simulation of this reactor, without closed-loop control, was developed and implemented on a hybrid computer, using the basic equations of conservation of mass, energy and momentum. The natural circulation of downcomer flow in the pool was simulated using a special filter, capable of modelling various flow conditions. The simulation was then used to study the intermediate and long-term transient response of SLOWPOKE-3 to large disturbances, such as loss of heat sink, loss of regulation, daily load following, and overcooling of the reactor coolant. Results of the simulation show that none of these disturbances produce hazardous transients

  19. Forsmark site investigation. Detailed ground magnetic survey and lineament interpretation in the Forsmark area, 2006-2007

    International Nuclear Information System (INIS)

    Isaksson, Hans; Thunehed, Hans; Pitkaenen, Timo; Keisu, Mikael

    2007-12-01

    The report presents detailed ground magnetic measurements carried out on an 11.1 km 2 area in the Forsmark site investigation area. The main objective of this activity is to determine a detailed ground magnetic representation of the bedrock. The results from previous surveys were encouraging and have led to a broad geophysical programme for investigation of lineaments at Forsmark. This report comprises the results from the second and final phase of the extended survey programme and a compilation and summary of all phases in the programme. On ground and on lake ice, a grid with parallel lines was staked. Measurements of the magnetic total field were carried out along profiles, perpendicular to the staked lines, with a profile spacing of 10 m and a station spacing of 5 m. Measurements on the ice-covered sea bays were carried out by a two man crew. One crew member walked along the survey lines, carrying a RTK-GPS guiding the other crew member who measured the magnetic total field. No seaborne survey was carried out in the final phase. Previously, using a high accuracy RTK-GPS unit for boat navigation gave a seaborne survey grid of on average 10 m line spacing and 2-3 m station spacing. In total 427,238 magnetic survey stations have been measured and an area of 4.7 km 2 has been surveyed from boat. The magnetic pattern in the survey area can be divided into six main areas with different magnetic character. Along the southwest margin of the survey area the magnetic pattern is intensely banded with rapidly changing low and highly magnetic bands striking southeast-northwest, which to the northeast changes to a gentler, banded pattern of low to moderate magnetic intensity. To the northeast, at the SFR office and along the coastline to the southeast, the pattern is again intensely banded with, southeast-northwest trending, rapidly changing low and highly magnetic bands. These two banded structures probably forms fold limbs of a common fold with a northwest oriented fold

  20. RA reactor exploitation, task 3.08/01

    International Nuclear Information System (INIS)

    Zecevic, V.

    1963-01-01

    During 1963 the RA reactor was operated for 1852 hours at mean power of 5.7 MW (total power production was 10716 MWh). Reactor was used for irradiation according to the demand of 356 users, and 15 experiments. The reason for decreased operation in comparison with the previous year was repair of all the reactor equipment and decontamination of the heavy water system. This report contains detailed data about reactor power, reactivity changes and fuel burnup. Mean monthly usage of the reactor experimental channels as well as samples which were irradiated are part of this report

  1. Evaluating hydrochemical data from shallow groundwater in Forsmark from a microbiological perspective

    International Nuclear Information System (INIS)

    Hallbeck, Lotta

    2008-03-01

    Oxygen is one of the chemical species that can corrode a copper canister in a KBS-3 repository. It is therefore important to determine whether oxygen dissolved in precipitation or groundwater could reach repository depth by groundwater transport. This matter can be determined by gaining an understanding of the oxygen-consuming microbial processes that take place in shallow groundwater in the area of interest. This report evaluates hydrogeochemical data from shallow groundwater in the Forsmark area from a microbiological perspective. Hydrogeochemical data were gathered from soil pipes at depths from 1.6 to 9.6 m and from percussion-drilled boreholes having mid-point depths of between c. 30 and c. 180 m. Only a few of the percussion-drilled boreholes had packers installed. The sampled sections were therefore very long, allowing groundwater from many different depths to mix. Oxygen and oxidation-reduction potential (ORP) were measured in groundwater in soil pipes but not in percussion-drilled boreholes. The poor quality of the oxygen data made it difficult to identify the depth of origin of completely oxygen-free groundwater. Parameters that indicated ongoing anaerobic microbial processes, such as nitrite, ferrous iron, dissolved manganese, and sulphide, were found in many soil pipes. The soil pipes displayed individual chemical profiles in terms of chemical species related to microbial activity. The microbial activity could not be linked to the classes of soil pipe, i.e. recharge, discharge, or intermittent. Existing soil pipes and percussion-drilled boreholes could be used for additional sampling of microbial parameters. Such sampling would benefit from careful hypothesis-driven description of the sampling parameters and experience-guided choice of sampling methods

  2. Evaluating hydrochemical data from shallow groundwater in Forsmark from a microbiological perspective

    Energy Technology Data Exchange (ETDEWEB)

    Hallbeck, Lotta (Microbial Analytics Sweden AB, Goeteborg (Sweden))

    2008-03-15

    Oxygen is one of the chemical species that can corrode a copper canister in a KBS-3 repository. It is therefore important to determine whether oxygen dissolved in precipitation or groundwater could reach repository depth by groundwater transport. This matter can be determined by gaining an understanding of the oxygen-consuming microbial processes that take place in shallow groundwater in the area of interest. This report evaluates hydrogeochemical data from shallow groundwater in the Forsmark area from a microbiological perspective. Hydrogeochemical data were gathered from soil pipes at depths from 1.6 to 9.6 m and from percussion-drilled boreholes having mid-point depths of between c. 30 and c. 180 m. Only a few of the percussion-drilled boreholes had packers installed. The sampled sections were therefore very long, allowing groundwater from many different depths to mix. Oxygen and oxidation-reduction potential (ORP) were measured in groundwater in soil pipes but not in percussion-drilled boreholes. The poor quality of the oxygen data made it difficult to identify the depth of origin of completely oxygen-free groundwater. Parameters that indicated ongoing anaerobic microbial processes, such as nitrite, ferrous iron, dissolved manganese, and sulphide, were found in many soil pipes. The soil pipes displayed individual chemical profiles in terms of chemical species related to microbial activity. The microbial activity could not be linked to the classes of soil pipe, i.e. recharge, discharge, or intermittent. Existing soil pipes and percussion-drilled boreholes could be used for additional sampling of microbial parameters. Such sampling would benefit from careful hypothesis-driven description of the sampling parameters and experience-guided choice of sampling methods

  3. Site descriptive modelling Forsmark, stage 2.2. A fracture domain concept as a basis for the statistical modelling of fractures and minor deformation zones, and interdisciplinary coordination

    Energy Technology Data Exchange (ETDEWEB)

    Olofsson, Isabelle; Simeonov, Assen [Swedish Nuclear Fuel and Waste Manageme nt Co., Stockholm (Sweden); Stephens, Michael [Geological Survey of Sweden (SGU), U ppsala (Sweden); Follin, Sven [SF GeoLogic AB, Taeby (Sweden); Nilsson, Ann-Chatrin [G eosigma AB, Uppsala (Sweden); Roeshoff, Kennert; Lindberg, Ulrika; Lanaro, Flavio [Bergbygg konsult AB, Haesselby (Sweden); Fredriksson, Anders; Persson, Lars [Golder Associat es AB (Sweden)

    2007-04-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterization at two different locations, Forsmark and Simpevarp/Laxemar, with the objective of siting a final waste repository at depth for spent nuclear fuel. The programme is built upon the development of site descriptive models after each data freeze. This report describes the first attempt to define fracture domains for the Forsmark site modelling in stage 2.2. Already during model version 1.2 at Forsmark, significant spatial variability in the fracture pattern was observed. The variability appeared to be so significant that it provoked the need for a subdivision of the model volume for the treatment of geological and hydrogeological data into sub-volumes. Subsequent analyses of data collected up to data freeze 2.1 led to a better understanding of the site and a concept for the definition of fracture domains based on geological characteristics matured. The main objectives of this report are to identify and describe fracture domains at the site on the basis of geological data and to compile hydrogeological, hydrogeochemical and rock mechanics data within each fracture domain and address the implications of this integration activity. On the basis of borehole data, six fracture domains (FFM01-FFM06) have been recognized inside and immediately around the candidate volume. Three of these domains (FFM01, FFM02 and FFM06) lie inside the target volume for a potential repository in the northwestern part of the candidate area, and need to be addressed in the geological DFN modelling work. The hydrogeological data support the subdivision of the bedrock into fracture domains FFM01, FFM02 and FFM03. Few or no data are available for the other three domains. The hydrogeochemical data also support the subdivision into fracture domains FFM01 and FFM02. Since few data are available from the bedrock between deformation zones inside FFM03, there is little information on the hydrogeochemical

  4. Sediment dynamics in the coastal areas of Forsmark and Laxemar during an interglacial

    International Nuclear Information System (INIS)

    Brydsten, Lars

    2009-06-01

    been evaluated within the project. It is based on a digital elevation model (DEM) covering the Baltic Sea and its surroundings (negative values for the sea and positive values for the land) that have also been evaluated within the project. The DEM is based on elevation data from many different sources that is merged into a common coordinate system and a common height system. These irregularly spaced data have been used to interpolate a regular DEM. For each time step, this DEM has been corrected to those circumstances prevalent at that date using shore displacement equations for about 80 places around the Baltic Sea. This correction accounts for the special conditions that existed during periods when the Baltic Sea was a lake. The bathymetry of the high-resolution model domains at Forsmark and Laxemar are based on existing 20 m resolution DEMs. The change in bathymetry over time for these areas is calculated using the shore displacement equations for three sites close to each model site, a strategy that makes it possible to investigate the tilt of the landscape. This factor has some significance early and late in the modelled period. It is impossible to run the model for all combinations of wind directions and wind speeds at each time step due to time reason, so only wind directions from long fetches and two critical wind speeds are simulated. The two critical wind speeds are expected to show changes in the extensions of three sea bottom types: 1) erosion bottoms where the resuspension frequency is so high that a particle is settled for maximum of one month, 2) accumulation bottoms where resuspension is not occurring, and 3) transport bottoms where a particle can be settled for one month to 500 years. The higher wind speed is chosen so that it possibly occurs at least at one occasion each 500 years with a wind direction approximately parallel with the longest fetch and with duration enough to make the fetch the only limiting factor for the wave generation. The lower

  5. Two-phase flow in the upper plenum of a boiling water nuclear reactor

    International Nuclear Information System (INIS)

    Tinoco, Hernan

    2003-01-01

    The end part of the Emergency Core Spray System (ECSS) of the Boiling Water Reactors (BWRs) at Forsmark Nuclear Power Plant (NPP) is situated in the Upper Plenum. It consists of a pipe network equipped with water injection nozzles. In case of Lost-of-Coolant Accidents (LOCAs), the ECSS should maintain the core covered by water and, at the same time, rapidly cool and decompress the reactor by means of cold water injection. In similar reactors, some welds belonging to the ECSS support have, after a period of time, shown crack indications. Inspection, repair or replacement of these welds is time consuming and expensive. For this reason, it has now been decided to permanently remove the end part of the ECSS and to replace it by water injection in the Downcomer. However, this removal should not be accompanied by undesirable effects like an increase in the moisture of the steam used for operating the turbines. To investigate the effect of this removal on the steam moisture, a CFD analysis of the two-phase flow in the Upper Plenum of Unit 3, with and without ECSS, has been carried out by means of a two-phase Euler model in FLUENT 6.0. The inlet conditions are given by an analysis of the core kinetics and thermal hydraulics by mean of the POLCA-code. The outlet conditions, i. e. the steam separator pressure drops, are given by empirical correlations from the experiments carried out at the SNORRE facility. The predicted the mass flow-rates to each separator, together with empirical correlations for the moisture content of the steam leaving the separators and the steam dryer, indicate a slight decrease in the steam moisture when the ECSS is removed. Also, a minor decrease in pressure losses over the Upper Plenum is achieved with this removal. On the other hand, rounding the sharp edges of the inlet openings to the steam separators at the shroud cover may give a large reduction in pressure losses

  6. Characteristics of D-{sup 3}He fueled frc reactor: ARTEMIS-L

    Energy Technology Data Exchange (ETDEWEB)

    Momota, H.; Motojima, O.; Okamoto, M.; Sudo, S.; Tomita, Y.; Yamaguchi, S.; Iiyoshi, A.; Onozuka, M.; Ohnishi, M.; Uenosono, C.

    1993-11-01

    The paper introduces briefly the scenario and discuss the attractive characteristics of D-3He fueled commercial fusion reactor ARTEMIS-L. By using favorable characteristics of a field-reversed configuration, the fusion plasma of ARTEMIS-L is compact and its beta-value is extremely high. One find consequently a possibility of constructing an economical fusion power power plant on this prospect. The life of the structural materials is sound during the full reactor life (30 years) and the safety of the reactor is intrinsic to D-3He fuels. The amount of disposed materials is rather small and the level of these intruder dose is so low that the plant appears to be acceptable in view of the environment. (author).

  7. Fusion reactor control study. Volume 3. Tandem mirror reactors. Final report

    International Nuclear Information System (INIS)

    Chang, F.R.; DeCanio, F.; Fisher, J.L.; Madden, P.A.

    1982-03-01

    A study of the control requirements of the Tandem Mirror Reactor concept is reported. The study describes the development of a control simulator that is based upon a spatially averaged physics code of the reactor concept. The simulator portrays the evolution of the plasma through the complete reactor operating cycle; it includes models of the control and measurement system, thus allowing the exploration of various strategies for reactor control. Startup, shutdown, and control during the quasi-steady-state power producing phase were explored. Configurations are described which use a variety of control effectors including modulation of the refueling rate, beam current, and electron cyclotron resonance heating. Multivariable design techniques were used to design the control laws and compensators for the feedback controllers and presume the practical measurement of only a subset of the plasma and machine variables. Performance of the various controllers is explored using the nonlinear control simulator. Derivative control strategies using new or developed sensors and effectors appropriate to a power reactor environment are postulated, based upon the results of the control configurations tested. Research and development requirements for these controls are delineated

  8. Studies on the liquid fluoride thorium reactor: Comparative neutronics analysis of MCNP6 code with SRAC95 reactor analysis code based on FUJI-U3-(0)

    Energy Technology Data Exchange (ETDEWEB)

    Jaradat, S.Q., E-mail: sqjxv3@mst.edu; Alajo, A.B., E-mail: alajoa@mst.edu

    2017-04-01

    Highlights: • The verification for FUJI-U3-(0)—a molten salt reactor—was performed. • The MCNP6 was used to study the reactor physics characteristics for FUJI-U3 type. • The results from the MCNP6 were comparable with the ones obtained from literature. - Abstract: The verification for FUJI-U3-(0)—a molten salt reactor—was performed. The reactor used LiF-BeF2-ThF4-UF4 as the mixed liquid fuel salt, and the core was graphite moderated. The MCNP6 code was used to study the reactor physics characteristics for the FUJI-U3-(0) reactor. Results for reactor physics characteristic of the FUJI-U3-(0) exist in literature, which were used as reference. The reference results were obtained using SRAC95 (a reactor analysis code) coupled with ORIGEN2 (a depletion code). Some modifications were made in the reconstruction of the FUJI-U3-(0) reactor in MCNP due to unavailability of more detailed description of the reactor core. The assumptions resulted in two representative models of the reactor. The results from the MCNP6 models were compared with the reference results obtained from literature. The results were comparable with each other, but with some notable differences. The differences are because of the approximations that were done on the SRAC95 model of the FUJI-U3 to simplify the simulation. Based on the results, it is concluded that MCNP6 code predicts well the overall simulation of neutronics analysis to the previous simulation works using SRAC95 code.

  9. Systems analysis of the CANDU 3 Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Wolfgong, J.R.; Linn, M.A.; Wright, A.L.; Olszewski, M.; Fontana, M.H. [Oak Ridge National Lab., TN (United States)

    1993-07-01

    This report presents the results of a systems failure analysis study of the CANDU 3 reactor design; the study was performed for the US Nuclear Regulatory Commission. As part of the study a review of the CANDU 3 design documentation was performed, a plant assessment methodology was developed, representative plant initiating events were identified for detailed analysis, and a plant assessment was performed. The results of the plant assessment included classification of the CANDU 3 event sequences that were analyzed, determination of CANDU 3 systems that are ``significant to safety,`` and identification of key operator actions for the analyzed events.

  10. Reactor core for LMFBR type reactors

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Azekura, Kazuo; Kurihara, Kunitoshi; Bando, Masaru; Watari, Yoshio.

    1987-01-01

    Purpose: To reduce the power distribution fluctuations and obtain flat and stable power distribution throughout the operation period in an LMFBR type reactor. Constitution: In the inner reactor core region and the outer reactor core region surrounding the same, the thickness of the inner region is made smaller than the axial height of the reactor core region and the radial width thereof is made smaller than that of the reactor core region and the volume thereof is made to 30 - 50 % for the reactor core region. Further, the amount of the fuel material per unit volume in the inner region is made to 70 - 90 % of that in the outer region. The difference in the neutron infinite multiplication factor between the inner region and the outer region is substantially constant irrespective of the burnup degree and the power distribution fluctuation can be reduced to about 2/3, by which the effect of thermal striping to the reactor core upper mechanisms can be moderated. Further, the maximum linear power during operation can be reduced by 3 %, by which the thermal margin in the reactor core is increased and the reactor core fuels can be saved by 3 %. (Kamimura, M.)

  11. Forsmark site investigation. Hydrochemical monitoring of groundwaters and surface waters. Results from water sampling in the Forsmark area, January-December 2009

    Energy Technology Data Exchange (ETDEWEB)

    Nilsson, Ann-Chatrin (ed.); Berg, Cecilia; Harrstroem, Johan; Joensson, Stig; Thur, Pernilla (Geosigma AB (Sweden)); Borgiel, Micke; Qvarfordt, Susanne (Sveriges Vattenekologer AB (Sweden))

    2010-09-15

    The fifth year (2009) of hydrochemical monitoring of groundwaters, surface waters and precipitation in Forsmark is documented in the report. The hydrochemical monitoring programme 2009 included water sampling from: - percussion- and core boreholes equipped with installations for long-term pressure monitoring, tracer tests and water sampling in packed off borehole sections, sampling and analysis performed twice (spring and autumn), - near surface groundwaters (sampling four times a year), - private wells (once per year in October), - surface waters (eleven sampling occasions per year). Due to the somewhat different performance of the hydrogeochemical monitoring of the deep groundwaters during the autumn 2009 compared to previous years, some new findings and knowledge were obtained: 1) Removal of water volumes corresponding to three to five times the volume of the borehole section (the routine procedure) is seldom enough to obtain a complete exchange of the water present in the borehole section when the pumping starts. 2) It is likely that the elevated sulphide concentrations observed in the monitoring programme /1/ is due to contamination from initial water present in the borehole sections when the pumping starts. This water may have a very high sulphide concentration. Dirty water in tubes and in stand pipes may also contribute to the enhanced sulphide concentration. 3) Plug flow calculations will be introduced in the future as a new routine procedure to estimate the water volumes to be removed, in order to exchange the section water volume, prior to groundwater sampling in delimited borehole sections. During the autumn sampling, sample series of five samples per sampling location were collected during continuous pumping in thirteen selected borehole sections. Furthermore, special efforts were put on cleaning of stand pipes and exchange of water prior to sampling. The analytical protocol was rather extensive and included sulphide and uranium analyses for each sample

  12. Forsmark site investigation. Hydrochemical monitoring of groundwaters and surface waters. Results from water sampling in the Forsmark area, January-December 2009

    International Nuclear Information System (INIS)

    Nilsson, Ann-Chatrin; Borgiel, Micke; Qvarfordt, Susanne

    2010-09-01

    The fifth year (2009) of hydrochemical monitoring of groundwaters, surface waters and precipitation in Forsmark is documented in the report. The hydrochemical monitoring programme 2009 included water sampling from: - percussion- and core boreholes equipped with installations for long-term pressure monitoring, tracer tests and water sampling in packed off borehole sections, sampling and analysis performed twice (spring and autumn), - near surface groundwaters (sampling four times a year), - private wells (once per year in October), - surface waters (eleven sampling occasions per year). Due to the somewhat different performance of the hydrogeochemical monitoring of the deep groundwaters during the autumn 2009 compared to previous years, some new findings and knowledge were obtained: 1) Removal of water volumes corresponding to three to five times the volume of the borehole section (the routine procedure) is seldom enough to obtain a complete exchange of the water present in the borehole section when the pumping starts. 2) It is likely that the elevated sulphide concentrations observed in the monitoring programme /1/ is due to contamination from initial water present in the borehole sections when the pumping starts. This water may have a very high sulphide concentration. Dirty water in tubes and in stand pipes may also contribute to the enhanced sulphide concentration. 3) Plug flow calculations will be introduced in the future as a new routine procedure to estimate the water volumes to be removed, in order to exchange the section water volume, prior to groundwater sampling in delimited borehole sections. During the autumn sampling, sample series of five samples per sampling location were collected during continuous pumping in thirteen selected borehole sections. Furthermore, special efforts were put on cleaning of stand pipes and exchange of water prior to sampling. The analytical protocol was rather extensive and included sulphide and uranium analyses for each sample

  13. Numerical simulation of progressive inlet orifices in boiling water reactor fuel

    International Nuclear Information System (INIS)

    Lundgren, Sara

    2004-07-01

    This thesis was carried out at Forsmark Nuclear Power Plant. The power plant in Forsmark consists of three boiling water reactors (BWR) which produce about 17% of Swedish electricity. In a BWR the nuclear reactions are used to boil water inside the reactor vessel. The water works both as a coolant and as a moderator and the resulting steam is used directly to run the turbines. A problem when running a BWR at low flow conditions is the density wave oscillations that might occur to the water flow inside the fuel assemblies. These oscillations arise due to the connection between power and flow rate in a heated channel with two-phase flow. In order to improve the stability performance of the channel an orifice plate is placed at the inlet of each fuel assembly. Today these orifice plates have sharp edges and a constant resistance coefficient. Experimental work has been done with progressive orifices, the edge of which is half-oval in shape. The advantage of progressive orifices is the lower pressure losses with an increase of the Reynolds number, a similar phenomenon that appears in external flow around curved bodies. Since there are high costs associated with experimental generation of high- temperature and high-pressure data, it is of some interest to be able to reproduce and generate data using Computational Fluid Dynamics (CFD). This work deals with the possibility to use the CFD-code Fluent to do numerical simulations of the flow through progressive orifices. The following conclusions may be drawn from the numerical results: All simulations using Reynolds-Averaged Navier-Stokes (RANS) turbulence models, two-dimensional and three-dimensional, capture an abrupt decrease of the resistance coefficient at higher Reynolds numbers. Two-equation models seem to under-predict the critical Reynolds number. The five-equation Reynolds Stress Model (RSM) gives a critical Reynolds number of the same order of magnitude of that measured in experiments. No major differences have

  14. Ignition access in a D-3He helical reactor

    International Nuclear Information System (INIS)

    Mitarai, Osamu

    2003-01-01

    Ignition access in a D- 3 He helical reactor is studied based on 0-dimensional particle and power balance equations for deuterium, tritium, helium-3, alpha ash, proton ash, electron density and temperature. The calculations are based on the following experimental facts observed in LHD. (author)

  15. The Effect of Different Perturbations on the Stability Analysis of Light Water Reactors

    International Nuclear Information System (INIS)

    Dykin, Victor

    2010-09-01

    Neutron noise analysis techniques are studied and developed, with primary use of determining the stability of Boiling Water Reactors (BWRs). In particular, the role of a specific perturbation prevailing in Light Water Reactors, the propagating density perturbation, in the stability of BWRs and on the noise field of LWRs in general, is investigated by considering three topics. In the first topics, we investigate how the neutronic response of the reactor, usually described as a second order system driven by a white noise driving force, is affected by a non-white driving force. This latter arises from the reactivity effect of the propagating density perturbations. The investigation is performed by using spectral and correlation analysis. Propagating perturbations with different velocities are analyzed. We investigate how the accuracy of the determination of the so-called decay ratio (DR) of the system, based on the assumption of white noise driving force, deteriorates with deviations from the white noise character of the driving force. In the second topics, the space dependence of the neutron noise, induced by propagating density perturbations, represented through the perturbation of the absorption, is determined and discussed. A full analytical solution was obtained by the use of the Green's function technique. The solution was analyzed for different frequencies and different system sizes. An interesting new interference effect between the point-kinetic and space-dependent components of the induced noise was discovered and interpreted in physical terms. In the last topics, a non-linear stability analysis of a BWR is performed, using so called Reduced Order Model (ROM) techniques. A ROM is usually constructed by reducing the full set of 3D space-time dependent neutron-kinetics, thermal-hydraulics and heat transfer equations to time-dependent ones, by considering space dependence in a lumped parameter model (one or two discrete channels). The main novelty of our work

  16. Fusion blankets for catalyzed D--D and D--He3 reactors

    International Nuclear Information System (INIS)

    Fillo, J.A.; Powell, J.R.

    1977-01-01

    Blanket designs are presented for catalyzed D-D (Cat-D) and D-He 3 fusion reactors. Because of relatively low neutron wall loads and the flexibility due to non-tritium breeding, blankets potentially should operate for reactor life-times of approximately 30 years. Unscheduled replacement of failed blanket modules should be relatively rapid, due to very low residual activity, by operators working either through access ports in the shield (option 1) or directly in the plasma chamber (option 2). Cat-D blanket designs are presented for high (approximately 30%) and low (approximately 12%) β noncircular Tokamak reactors. The blankets are thick graphite screens, operating at high temperature to anneal radiation damage; the deposited neutron and gamma energy is thermally radiated along internal cavities and conducted to a bank of internal SiC coolant tubes (approximately 4 cm. ID) containing high pressure helium. In the D-He 3 Tokamak reactor design, the blanket consists of multiple layers (e.g., three) of thin (approximately 10 cm.) high strength aluminum (e.g., SAP), modular plates, cooled by organic terphynyl coolant

  17. Fusion blankets for catalyzed D--D and D--3He reactors

    International Nuclear Information System (INIS)

    Fillo, J.A.; Powell, J.R.

    1977-01-01

    Blanket designs are presented for catalyzed D-D (Cat-D) and D-He 3 fusion reactors. Because of relatively low neutron wall loads and the flexibility due to non-tritium breeding, blankets potentially should operate for reactor life-times of approximately 30 years. Unscheduled replacement of failed blanket modules should be relatively rapid, due to very low residual activity, by operators working either through access ports in the shield (option 1) or directly in the plasma chamber (option 2). Cat-D blanket designs are presented for high (approximately 30%) and low (approximately 12%) β non-circular Tokamak reactors. The blankets are thick graphite screens, operating at high temperature to anneal radiation damage; the deposited neutron and gamma energy is thermally radiated along internal cavities and conducted to a bank of internal SiC coolant tubes (approximately 4 cm. ID) containing high pressure helium. In the D-He 3 Tokamak reactor design, the blanket consists of multiple layers (e.g., three) of thin (approximately 10 cm.) high strength aluminum (e.g., SAP), modular plates, cooled by organic terphenyl coolant

  18. RELAP5-3D code validation of RBMK-1500 reactor reactivity measurement transients

    International Nuclear Information System (INIS)

    Kaliatka, Algirdas; Bubelis, Evaldas; Uspuras, Eugenijus

    2003-01-01

    This paper deals with the modeling of transients taking place during the measurements of the void and fast power reactivity coefficients performed at Ignalina NPP. The simulation of these transients was performed using RELAP5-3D code model of RBMK-1500 reactor. At the Ignalina NPP void and fast power reactivity coefficients are measured on a regular basis and, based on the total reactor power, reactivity, control and protection system control rods positions and the main circulation circuit parameter changes during the experiments, the actual values of these reactivity coefficients are determined. Following the simulation of the two above mentioned transients with RELAP5-3D code, a conclusion was made that the obtained calculation results demonstrate reasonable agreement with Ignalina NPP measured data. Behaviors of the separate MCC thermal-hydraulic parameters as well as physical processes are predicted reasonably well to the real processes, occurring in the primary circuit of RBMK-1500 reactor. The calculated reactivity and the total reactor core power behavior in time are also in reasonable agreement with the measured plant data. Despite of the small differences, RELAP5-3D code predicts reactivity and the total reactor core power behavior during the transients in a reasonable manner. Reasonable agreement of the measured and the calculated total reactor power change in time demonstrates the correct modeling of the neutronic processes taking place in RBMK-1500 reactor core

  19. The biotest basin of the Forsmark nuclear power plant, Sweden. An experiment on the ecosystem level

    International Nuclear Information System (INIS)

    Grimaas, U.

    1979-01-01

    Biotope models of various sizes and enclosed waters in connection with radionuclide release constitute important tools for radioecological experiments, representing an intermediate step between field and laboratory conditions. The biotest basin at Forsmark is especially constructed for investigations on the effects of radioactivity and heat on a brackish water ecosystem. The basin encloses a water area of 1km 2 in the outer archipelago of the region and is fed with cooling water and released radionuclides by a discharge tunnel. The quantities of the discharges into the basin are adjustable. The biotest experiment permits a quantification of the retention and transport of radionuclides at the various trophic levels. Of special value is the possibility to work with known populations of fish. The approach has the advantage of experimental ecology - the control of important parameters - under the impact of all environmental factors in a complete ecosystem. (author)

  20. Large-Scale Groundwater Flow with Free Water Surface Based on Data from SKB's Site Investigation in the Forsmark Area

    International Nuclear Information System (INIS)

    Woerman, Anders; Sjoegren, Bjoern; Marklund, Lars

    2004-12-01

    This report describes a data-base that covers entire Sweden with regard to various geographical parameters with implications to simulation of groundwater circulation on a regional and continental scale. The data-base include topography, stream network properties, and-use and water chemistry for limited areas. Furthermore, the report describes a computational (finite difference) code that solves the continuum equation for laminar, stationary and isotropic groundwater flow. The formulation accounts for a free groundwater surface except where the groundwater recharge into the stream network and lake bottoms. The theoretical background of the model is provided and the codes are described. The report also contain a simple user manual in a Matlab environment and provides and example calculation for the Forsmark area, Uppland, Sweden.

  1. GRIMH3: A new reactor calculation code at Savannah River Site

    International Nuclear Information System (INIS)

    Le, T.T.; Pevey, R.E.

    1993-01-01

    The GRIMHX reactor code currently in use at the Savannah River Site (SRS) was written at a time when computer processing speed and memory storage were very limited. Recently, a new reactor code (GRIMH3) was written to take advantage of the hardware improvements (vectorization and higher memory capacities) as well as the range of available computers at SRS (workstations and supercomputers). The GRIMH3 code computes the solution of the static multigroup neutron diffusion equation in one-, two-, and three-dimensional hexagonal geometry. Either direct or adjoint solutions can be computed for k eff searches, buckling searches, external neutron sources, power flattening searches, or power normalization factor calculations with 1, 6, 24, 54, or 96 points per hex. The GRIMHX reactor code currently in use at the Savannah River Site (SRS) was written at a time when computer processing speed and memory storage were very limited. Recently, a new reactor code (GRIMH3) was written to take advantage of the hardware improvements (vectorization and higher memory capacities) as well as the range of available computers at SRS (workstations and supercomputers). The GRIMH3 code computes the solution of the static multigroup neutron diffusion equation in one-, two-, and three-dimensional hexagonal geometry. Either direct or adjoint solutions can be computed for k eff searches, buckling searches, external neutron sources, power flattening searches, or power normalization factor calculations with 1, 6, 24, 54, or 96 points per hex

  2. Inventory of vegetation and benthos in newly laid and natural ponds in Forsmark 2012

    International Nuclear Information System (INIS)

    Qvarfordt, Susanne; Wallin, Anders; Borgiel, Micke

    2013-01-01

    SKB plans to build a repository for the spent nuclear fuel. The repository is planned to be built in Forsmark and constitutes installations above and below ground. The building and operation of the construction will involve activities that might affect the nature in the area. The impact means, among other things, that a small water body, which today is a reproduction site for the red listed pool frog (Rana lessonae), will disappear. The lost locality for the pool frog has been compensated by creating four new ponds in the Forsmark area. This study is part of the follow-up of these new habitats. The aim is to describe the plant and animal communities in the ponds, and follow the succession, i.e. the development of the habitats. The study also includes two natural ponds that will serve as reference objects. The survey of vegetation and invertebrate fauna in the ponds was conducted in October 2012. The results show that the new ponds had low coverage of submersed vegetation and the species composition in the plant communities differed between the ponds. The reference ponds also had different plant communities, both in terms of species composition and coverage. This indicates that the species composition of the plant communities in the new ponds will likely depend on physical factors specific to the respective pond, but that higher vegetation coverage can be expected over time in all new ponds. The reference ponds had similar animal communities that differed from the animal communities in the new ponds. The similar species composition in the reference ponds, despite the variety of plant communities, suggests that similar animal communities are likely to develop in the new ponds, even if the plant communities continues to be different. Water chemical sampling has also been conducted in the ponds during 2012. A comparison of the inorganic environment (with regard to analysed ions) showed that the reference ponds had relatively similar ion compositions with little

  3. Irradiated graphite studies prior to decommissioning of G1, G2 and G3 reactors

    International Nuclear Information System (INIS)

    Bonal, J.P.; Vistoli, J.Ph.; Combes, C.

    2005-01-01

    G1 (46 MW th ), G2 (250 MW th ) and G3 (250 MW th ) are the first French plutonium production reactors owned by CEA (Commissariat a l'Energie Atomique). They started to be operated in 1956 (G1), 1959 (G2) and 1960 (G3); their final shutdown occurred in 1968, 1980 and 1984 respectively. Each reactor used about 1200 tons of graphite as moderator, moreover in G2 and G3, a 95 tons graphite wall is used to shield the rear side concrete from neutron irradiation. G1 is an air cooled reactor operated at a graphite temperature ranging from 30 C to 230 C; G2 and G3 are CO 2 cooled reactors and during operation the graphite temperature is higher (140 C to 400 C). These reactors are now partly decommissioned, but the graphite stacks are still inside the reactors. The graphite core radioactivity has decreased enough so that a full decommissioning stage may be considered. Conceming this decommissioning, the studies reported here are: (i) stored energy in graphite, (ii) graphite radioactivity measurements, (iii) leaching of radionuclide ( 14 C, 36 Cl, 63 Ni, 60 Co, 3 H) from graphite, (iv) chlorine diffusion through graphite. (authors)

  4. Operational Experience from Swedish nuclear power plants 1996

    International Nuclear Information System (INIS)

    1997-01-01

    A summary of two pages is given for each Swedish reactor with data on availability, scrams, radiation doses and important events during 1996. Special reports are presented on the following issues: Reactor core spray system inoperable at OKG-2, Containment pressure relief system incorrectly closed at Forsmark-1, Isolation condenser blocked for residual heat and continued operation with defective isolation valve at OKG-1; and Degraded pressure suppression function of the containment at Barsebaeck-2

  5. The 4th surveillance testing for Kori unit 3 reactor vessel materials

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Kee Ok; Kim, Byoung Chul; Lee, Sam Lai; Choi, Kwun Jae; Gong, Un Sik; Chang, Jong Hwa; Joo, Yong Sun; Ahn, Sang Bok; Hong, Joon Hwa [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-10-01

    Surveillance testing for reactor vessel materials is performed in order to evaluate the irradiation embrittlement due to neutrons during operation and set the condition of safe operation of nuclear reactor. The 4th surveillance testing was performed completely by Korea Atomic Energy Research Institute at Taejeon after the capsule was transported from Kori site including its removal from reactor. Fast neutron fluences for capsules were calculated and various testing including mechanical and chemistry analysis were performed in order to evaluate the integrity of Kori unit 3 reactor vessel during the operation until life time. The evaluation results are as follows; Fast neutron fluences for capsules U, V, X and W are 4.983E+18, 1.641E+19, 3.158E+19, and 4.469E+19n/cm{sup 2}, respectively. The bias factor, the ratio of calculation/measurement, was 0.840 for the 1st through 4th testing and the calculational uncertainty, 12% satisfied the requirement of USNRC Reg.Guide DG-1053, 20%. The best estimated neutron fluence for reactor vessel inside surface was 1.362E+19n/cm{sup 2} based on the end of 12th fuel cycle and it was predicted that the fluences of vessel inside surface at 32, 40, 48 and 56EFPY would reach 3.481E+19, 4.209E+19, 5.144E+19 and 5.974E+19n/cm{sup 2} based on the current calculation. The result through this analysis for Kori unit 3 showed that there would be no problem for the pressurized thermal shock(PTS) during the operation until design life. 48 refs., 35 figs., 41 tabs. (Author)

  6. Comparison of 2D and 3D Neutron Transport Analyses on Yonggwang Unit 3 Reactor

    International Nuclear Information System (INIS)

    Maeng, Aoung Jae; Kim, Byoung Chul; Lim, Mi Joung; Kim, Kyung Sik; Jeon, Young Kyou; Yoo, Choon Sung

    2012-01-01

    10 CFR Part 50 Appendix H requires periodical surveillance program in the reactor vessel (RV) belt line region of light water nuclear power plant to check vessel integrity resulting from the exposure to neutron irradiation and thermal environment. Exact exposure analysis of the neutron fluence based on right modeling and simulations is the most important in the evaluation. Traditional 2 dimensional (D) and 1D synthesis methodologies have been widely applied to evaluate the fast neutron (E > 1.0 MeV) fluence exposure to RV. However, 2D and 1D methodologies have not provided accurate fast neutron fluence evaluation at elevations far above or below the active core region. RAPTOR-M3G (RApid Parallel Transport Of Radiation - Multiple 3D Geometries) program for 3D geometries calculation was therefore developed both by Westinghouse Electronic Company, USA and Korea Reactor Integrity Surveillance Technology (KRIST) for the analysis of In-Vessel Surveillance Test and Ex-Vessel Neutron Dosimetry (EVND). Especially EVND which is installed at active core height between biological shielding material and concrete also evaluates axial neutron fluence by placing three dosimetries each at Top, Middle and Bottom part of the angle representing maximum neutron fluence. The EVND programs have been applied to the Korea Nuclear Plants. The objective of this study is therefore to compare the 3D and the 2D Neutron Transport Calculations and Analyses on the Yonggwang unit 3 Reactor as an example

  7. Vegetation in the Forsmark biotest basin, 1974-1986

    International Nuclear Information System (INIS)

    Renstroem, S.; Svensson, Roger; Wigren-Svensson, M.

    1990-05-01

    Since 1980, Forsmark Power Plants has discharged large amount of cooling water into the Biotest basin. In 1974, before the dam was constructed, and 1980 to 1986, the macrophytic algae and higher vegetation inside and around the basin has been investigated. The observed changes are mainly caused by the increased water temperature causing lack of ice cover during the winter, the embankment reducing the exposition, the heavy water stream through the basin and the reduced light transmission in the water. The macroscopic vegetation in the Biotest basin was originally distributed all over the lake, but is now mainly found in more shallow water. The deepest part, a passage from the input of the cooling water to the output, totally lack vegetation. The reason for this is a combination of the heavy stream, raised temperature and reduced light transmission. The total biomass of macroscopic vegetation in the basin has been reduced from c. 70 metric ton in 1980 to c. 27 ton in 1982 and 1986. Among the most important species, the production of Chara spp. and Potamogeton pectinatus have been strongly reduced, while Cladophora glomerata and Vaucheria sp. have increased. Especially for Vaucheria, the raised temperature has been of vital importance. Among other species, Tolypella nidifica first increased, but has now totally disappeared. Zannichellia palustris was the only phanerogam which increased all the time. It is Z. palustris var. major which stands for the increase, while Z. palustris var. repens has disappeared from the basin. The shore vegetation, mainly reeds, has expanded conspicuously. From 1974 to 1980, the shore vegetation was favoured by the reduced exposition caused by the embankment. Since then, the raised temperature and absence of ice cover have resulted in an accelerating expansion of mainly Phragmites communis. Scirpus tabernaemontani and S. maritimus were first increasing, but do not seem to be able to compete with Phragmites in the long run. (au)

  8. Safety in the ARIES-III D-3He tokamak reactor design

    International Nuclear Information System (INIS)

    Herring, J.S.; Dolan, T.J.

    1992-01-01

    This paper reports on the ARIES-III reactor study, an extensive examination of the viability of a D- 3 He-fueled commercial tokamak powder reactor. Because neutrons are produced only through side reactions (D+D- 3 HE+N; and D+D-T+p followed by D+T- 4 He+n), the reactor has the significant advantages of reduced activation of the first wall and shield, low afterheat and Class A or C low level waste disposal. Since no tritium is required for operation, no lithium-containing breeding blanket is necessary. A ferritic steel shield behind the first wall protects the magnets from gamma and neutron heating and from radiation damage. The authors explored the potential for isotopically tailoring the 4 mm tungsten layer on the divertor in order to reduce the offsite doses should a tungsten aerosol be released from the reactor after an accident. The authors also modeled a loss-of-cooling accident (LOCA) in which the organic coolant was burning in order to estimate the amount of radionuclides released from the first wall. Because the maximum temperature is low, degree C, release fractions are small. The authors analyzed the disposition of the 20 g/day of tritium that is produced by D-D reactions and removed by the vacuum pumps

  9. Rock-block characterization on regional to local scales for two SKB sites in Forsmark - Uppland and Laxemar - eastern Smaaland, south-eastern Sweden

    International Nuclear Information System (INIS)

    Beckholmen, Monica; Tiren, Sven A.

    2010-11-01

    Digital elevation data in 500m, 50m and 10m grids were used for rock-block interpretations at regional, semi-regional and local scales of areas around the two SKB sites, Forsmark and Laxemar, objects for the site-investigation programme. Both areas are interpreted to be close to the surface of the sub- Cambrian peneplain and varying altitude and attitude may testify to blockfaulting in the distorted peneplain. Topographic breaks and changes in the gradient also reveal possible zones of weakness that may conduct water. Rock blocks were constructed for Uppland at 1:750 000, northern Uppland at 1:450 000 and the local Forsmark area at 1:150 000, three sets were constructed for eastern Smaaland at 1:500 000, and one for the semi-regional area at 1:250 000 and one for the local Laxemar area at 1:75 000. The orientation of rock-block boundaries and the size of the rock blocks were treated statistically. The rock blocks/polygons were analysed for their mean, minimum and maximum elevation and the range. The values were displayed by maps. The topography in especially eastern Smaaland is dominated by a clear gradient, the land rising from the sea in the east. Efforts were therefore made to remove an estimated gradient to assess the residual features and the same analyses were then made for mean, maximum, minimum and range values. In many cases the results were enhanced and the two types of presentations are complementary to each other. The rock-block interpretations were compared to bedrock and general correlation between major structures where identified. However, the distribution of rocks on a regional map often demonstrates the plastic deformation in a wider zone. Earthquake epicentres were combined with the rock-block maps and assuming that interpreted rock-block boundaries are fairly steep, there is good agreement between the location of epicentres and rock-block boundaries. In some cases it can be seen how seismic disturbance migrated along a structure. Many

  10. Rock-block characterization on regional to local scales for two SKB sites in Forsmark - Uppland and Laxemar - eastern Smaaland, south-eastern Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Beckholmen, Monica; Tiren, Sven A. (GEOSIGMA AB (Sweden))

    2010-11-15

    Digital elevation data in 500m, 50m and 10m grids were used for rock-block interpretations at regional, semi-regional and local scales of areas around the two SKB sites, Forsmark and Laxemar, objects for the site-investigation programme. Both areas are interpreted to be close to the surface of the sub- Cambrian peneplain and varying altitude and attitude may testify to blockfaulting in the distorted peneplain. Topographic breaks and changes in the gradient also reveal possible zones of weakness that may conduct water. Rock blocks were constructed for Uppland at 1:750 000, northern Uppland at 1:450 000 and the local Forsmark area at 1:150 000, three sets were constructed for eastern Smaaland at 1:500 000, and one for the semi-regional area at 1:250 000 and one for the local Laxemar area at 1:75 000. The orientation of rock-block boundaries and the size of the rock blocks were treated statistically. The rock blocks/polygons were analysed for their mean, minimum and maximum elevation and the range. The values were displayed by maps. The topography in especially eastern Smaaland is dominated by a clear gradient, the land rising from the sea in the east. Efforts were therefore made to remove an estimated gradient to assess the residual features and the same analyses were then made for mean, maximum, minimum and range values. In many cases the results were enhanced and the two types of presentations are complementary to each other. The rock-block interpretations were compared to bedrock and general correlation between major structures where identified. However, the distribution of rocks on a regional map often demonstrates the plastic deformation in a wider zone. Earthquake epicentres were combined with the rock-block maps and assuming that interpreted rock-block boundaries are fairly steep, there is good agreement between the location of epicentres and rock-block boundaries. In some cases it can be seen how seismic disturbance migrated along a structure. Many

  11. The Flamanville 3 EPR reactor; Le reacteur EPR Flamanville 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    On April 10. 2007, the french government authorized EDF to create on the site of Flamanville ( La Manche) a nuclear base installation containing a pressurized water EPR type reactor. This nuclear reactor, conceived by AREVA NP and EDF, is the first copy of a generation susceptible to replace later, at least partly, the French nuclear reactors at present in operation.Within the framework of its mission of technical support of the Authority of Nuclear Safety ( A.S.N.), the I.R.S.N. widely contributed successively: to define the general objectives of safety assigned to this new generation of pressurized water nuclear reactors; to analyze the options of safety proposed by EDF for the EPR project; To deepen, upstream to the authorization of creation, the evaluation of the step of safety and the measures of conception retained by EDF that have to allow to respect the objectives of safety which were notified to it. (N.C.)

  12. Reversed field pinch reactor study 3

    International Nuclear Information System (INIS)

    Hollis, A.A.; Mitchell, J.T.D.

    1977-12-01

    This report, the third of a series on the Reversed Field Pinch Reactor, describes a preliminary concept of the engineering design and layout of this pulsed toroidal reactor, which uses the stable plasma behaviour first observed in ZETA. The basic parameters of the 600 MW(e) reactor are taken from a companion study by Hancox and Spears. The plasma volume is 1.75m minor radius and 16m major radius surrounded by a 1.8m blanket-shield region - with the blanket divided into 14 removable segments for servicing. The magnetic confinement system consists of 28 toroidal field coils situated just outside the blanket and inside the poloidal and vertical field coils and all coils have normal copper conductors. The requirement to incorporate a conducting shell at the front of the blanket to provide a short-time plasma stability has a marked effect on the design. It sets the size of the blanket segment and the scale of the servicing operations, limits the breeding gain and complicates the blanket cooling and its integration with the heat engine. An extensive study will be required to confirm the overall reactor potential of the concept. (author)

  13. Permanent scatterer InSAR processing: Forsmark

    International Nuclear Information System (INIS)

    Dehls, John F.

    2006-04-01

    It has been speculated that slow, aseismic movement may be occurring along some of the fracture zones crosscutting the Forsmark area. The purpose of this study is to determine if it is possible to measure such movement using dInSAR. Differential SAR Interferometry (DInSAR) is a technique that compares the phases of multiple radar images of an area to measure surface change. The method has the potential to detect millimetric surface deformation along the sensor - target line-of-sight. Differences in phase between two images are easily viewed by combining, or interfering, the two phase-images. In the resulting image, the waves will either reinforce or cancel one another, depending upon the relative phases. The resulting image is called an interferogram and contains concentric bands of colour, or fringes, that are related to topography and/or surface deformation. New algorithms use many images acquired over a long time period to determine the movement history of individual objects, referred to as permanent scatterers. In the current project, standard PSInSAR processing was performed on 40 ERS-1 and ERS-2 scenes. The total area processed is approximately 1,500 km 2 . Slightly less than 20,000 permanent scatterers were identified.The highest densities were obtained along the coast and on the islands, where natural outcrops are more abundant. Two main classes of objects act as permanent scatterers in this area. The first are natural reflectors, such as rocks. The second are man-made reflectors, such as parts of buildings. Numerous local movements were found in the study area, relating to building subsidence, or compaction of anthropogenic fill. The dataset was divided into three groups for analysis, based upon the location of regional lineaments provided by SKB. Both statistical and geostatistical techniques were used. The median velocity of the three blocks did not differ by more than 0.2 mm/yr. This is not considered significant, given the possible magnitude of errors

  14. Permanent scatterer InSAR processing: Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Dehls, John F [Geological Survey of Norway, Trondheim (Norway)

    2006-04-15

    It has been speculated that slow, aseismic movement may be occurring along some of the fracture zones crosscutting the Forsmark area. The purpose of this study is to determine if it is possible to measure such movement using dInSAR. Differential SAR Interferometry (DInSAR) is a technique that compares the phases of multiple radar images of an area to measure surface change. The method has the potential to detect millimetric surface deformation along the sensor - target line-of-sight. Differences in phase between two images are easily viewed by combining, or interfering, the two phase-images. In the resulting image, the waves will either reinforce or cancel one another, depending upon the relative phases. The resulting image is called an interferogram and contains concentric bands of colour, or fringes, that are related to topography and/or surface deformation. New algorithms use many images acquired over a long time period to determine the movement history of individual objects, referred to as permanent scatterers. In the current project, standard PSInSAR processing was performed on 40 ERS-1 and ERS-2 scenes. The total area processed is approximately 1,500 km{sup 2}. Slightly less than 20,000 permanent scatterers were identified.The highest densities were obtained along the coast and on the islands, where natural outcrops are more abundant. Two main classes of objects act as permanent scatterers in this area. The first are natural reflectors, such as rocks. The second are man-made reflectors, such as parts of buildings. Numerous local movements were found in the study area, relating to building subsidence, or compaction of anthropogenic fill. The dataset was divided into three groups for analysis, based upon the location of regional lineaments provided by SKB. Both statistical and geostatistical techniques were used. The median velocity of the three blocks did not differ by more than 0.2 mm/yr. This is not considered significant, given the possible magnitude of

  15. Conceptual and numerical modelling of radionuclide transport in near-surface systems at Forsmark. SR-Site Biosphere

    International Nuclear Information System (INIS)

    Pique, Angels; Grandia, Fidel; Sena, Clara; Arcos, David; Molinero, Jorge; Duro, Lara; Bruno, Jordi

    2010-11-01

    In the framework of the SR-Site safety assessment, a conceptual and numerical modelling of radionuclide reactive transport in near-surface systems (including till and clay systems) at Forsmark has been carried out. The objective was to evaluate the retention capacity of the near-surface systems, composed of Quaternary deposits, which would be the last natural barrier for an eventual radionuclide release from the deep repository prior to reaching the biosphere. The studied radionuclides are 14 C, 129 I, 36 Cl, 94 Nb, 59 Ni, 93 Mo, 79 Se, 99 Tc, 230 Th, 90 Sr, 226 Ra, 135 Cs and U. Conceptual description and numerical simulations of radionuclide reactive transport show that cation exchange and surface complexation on illite are active processes for the retention of several radionuclides (U, Th, Ni, Cs, Sr, Ra). Surface complexation on iron hydroxide is an active process in the till system, able to effectively retain U and Ni. Another retention process of importance is the incorporation of the radionuclides into mineral phases, either by the precipitation of pure phases or solid solutions. Quantitative modelling has been useful to illustrate the incorporation of C and Sr in the carbonate solid solution in the considered model domains (till and clay), as well as the precipitation of uraninite in the clay sediments and the precipitation of native selenium and radiobarite in the till. Other mineral phases that could, a priori, retain U, Se, Nb and Tc do not precipitate in the simulations, either due to the pH-Eh conditions and/or because the dissolved concentration of the element is not high enough under the considered simulation conditions. It is important to keep in mind that changes in these parameters and in the boundary conditions could modify the predicted behaviour of these elements. The radionuclides that are most significantly retarded are Th, Ni and Cs, mainly through sorption onto illite. Therefore, if the amount of illite (or available sorption sites

  16. Conceptual and numerical modelling of radionuclide transport in near-surface systems at Forsmark. SR-Site Biosphere

    Energy Technology Data Exchange (ETDEWEB)

    Pique, Angels; Grandia, Fidel; Sena, Clara; Arcos, David; Molinero, Jorge; Duro, Lara; Bruno, Jordi (Amphos21 Consulting S.L., Barcelona (Spain))

    2010-11-15

    In the framework of the SR-Site safety assessment, a conceptual and numerical modelling of radionuclide reactive transport in near-surface systems (including till and clay systems) at Forsmark has been carried out. The objective was to evaluate the retention capacity of the near-surface systems, composed of Quaternary deposits, which would be the last natural barrier for an eventual radionuclide release from the deep repository prior to reaching the biosphere. The studied radionuclides are 14C, 129I, 36Cl, 94Nb, 59Ni, 93Mo, 79Se, 99Tc, 230Th, 90Sr, 226Ra, 135Cs and U. Conceptual description and numerical simulations of radionuclide reactive transport show that cation exchange and surface complexation on illite are active processes for the retention of several radionuclides (U, Th, Ni, Cs, Sr, Ra). Surface complexation on iron hydroxide is an active process in the till system, able to effectively retain U and Ni. Another retention process of importance is the incorporation of the radionuclides into mineral phases, either by the precipitation of pure phases or solid solutions. Quantitative modelling has been useful to illustrate the incorporation of C and Sr in the carbonate solid solution in the considered model domains (till and clay), as well as the precipitation of uraninite in the clay sediments and the precipitation of native selenium and radiobarite in the till. Other mineral phases that could, a priori, retain U, Se, Nb and Tc do not precipitate in the simulations, either due to the pH-Eh conditions and/or because the dissolved concentration of the element is not high enough under the considered simulation conditions. It is important to keep in mind that changes in these parameters and in the boundary conditions could modify the predicted behaviour of these elements. The radionuclides that are most significantly retarded are Th, Ni and Cs, mainly through sorption onto illite. Therefore, if the amount of illite (or available sorption sites) decreases, the

  17. Safety analysis of loss of flow transients in a typical research reactor by RELAP5/MOD3.3

    International Nuclear Information System (INIS)

    Di Maro, B.; Pierro, F.; Adorni, M.; Bousbia Salah, A.; D'Auria, F.

    2003-01-01

    The main aim of the following study is to assess the RELAP5/MOD3.3 code capability in simulating transient dynamic behaviour in nuclear research reactors. For this purpose typical loss of flow transient in a representative MTR (Metal Test Reactor) fuel type Research Reactor is considered. The transient herein considered is a sudden pump trip followed by the opening of a safety valve in order to allow passive decay heat removal by natural convection. During such transient the coolant flow decay, originally downward, leads to a flow reversal and the cooling process of the core passes from forced, mixed and finally to natural circulation. This fact makes it suitable for evaluating the new features of RELAP5 to simulate such specific operating conditions. The instantaneous reactor power is derived through the point kinetic calculation, both protected and unprotected cases are considered (with and without Scram). The results obtained from this analysis were also compared with previous results obtained by old version RELAP5/MOD2 code. (author)

  18. Greenland Analogue Project - Hydraulic properties of deformation zones and fracture domains at Forsmark, Laxemar and Olkiluoto for usage together with Geomodel version 1

    International Nuclear Information System (INIS)

    Follin, Sven; Stigsson, Martin; Rhen, Ingvar; Engstroem, Jon; Klint, Knut Erik

    2011-05-01

    The database of the GAP site is under development. In order to meet the data needs of the different modelling teams working with groundwater flow modelling it has been decided to compile trial data sets comprising structural-hydraulic properties suitable for flow modelling on different scales. The properties provided in this report are based on data and groundwater flow modelling studies conducted for three sites located in the Fennoscandian Shield, two of which are studied by SKB, Forsmark and Laxemar, and one by Posiva, Olkiluoto. The provided hydraulic properties provided here are simplified to facilitate a readily usage together with the GAP Geomodel version 1

  19. Greenland Analogue Project - Hydraulic properties of deformation zones and fracture domains at Forsmark, Laxemar and Olkiluoto for usage together with Geomodel version 1

    Energy Technology Data Exchange (ETDEWEB)

    Follin, Sven (SF GeoLogic AB (Sweden)); Stigsson, Martin (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)); Rhen, Ingvar (Sweco Environment AB (Sweden)); Engstroem, Jon (Geologian tutkimuskeskus (Finland)); Klint, Knut Erik (De Nationale Geologiske Undersoegelser for Danmark og Groenland (Denmark))

    2011-05-15

    The database of the GAP site is under development. In order to meet the data needs of the different modelling teams working with groundwater flow modelling it has been decided to compile trial data sets comprising structural-hydraulic properties suitable for flow modelling on different scales. The properties provided in this report are based on data and groundwater flow modelling studies conducted for three sites located in the Fennoscandian Shield, two of which are studied by SKB, Forsmark and Laxemar, and one by Posiva, Olkiluoto. The provided hydraulic properties provided here are simplified to facilitate a readily usage together with the GAP Geomodel version 1.

  20. Three-Dimensional Modeling of a Steam-Line Break in a Boiling Water Reactor

    International Nuclear Information System (INIS)

    Tinoco, Hernan

    2002-01-01

    Because of weld problems, the core grids of Units 1 and 2 at the Forsmark nuclear power plant have been replaced by grids of a new design, consisting of a single machined piece without welds. The qualifying structural analysis has been carried out considering dynamic loads, which implies that even loss-of-coolant accidents have to be included. Therefore, a detailed time description of the loads acting on the different internal parts of the reactor is needed. To achieve sufficient space and time resolution, a computational fluid dynamics (CFD) analysis was considered to be a viable alternative.A CFD analysis of a steam-line break in the boiling water reactor of Unit 2 is the subject of this work. The study is based on the assumption that the timescale of the transient analysis is smaller than the relaxation time of the water-steam system. Therefore, a simulation of only the upper, steam part of the reactor with no two-phase effects (flashing) is feasible.The results obtained display a rather complex behavior of the decompression process, forcing the analysis of the pressure field to be accomplished through animation. In contrast, the computed instantaneous forces over different internal parts oscillate regularly and are approximately twice the forces estimated in the past by simpler methods, with frequencies of 30 to 40 Hz; top amplitudes of ∼1.64 MN; and relatively low damping, ∼25% after 0.5 s.According to the present results, this type of modeling is physically meaningful for simulation timescales smaller than the water-steam relaxation time, i.e., ∼0.5 s at reactor conditions. At larger times, a two-phase model is necessary to describe the decompression process since two-phase effects are dominant. The results have not yet been validated with experiments, but validation computations will be run in the future for comparison with results of the Marviken tests

  1. Gas Reactor International Cooperative program. Pebble bed reactor plant: screening evaluation. Volume 3. Appendix A. Equipment list

    International Nuclear Information System (INIS)

    1979-11-01

    This report consists of three volumes which describe the design concepts and screening evaluation for a 3000 MW(t) Pebble Bed Reactor Multiplex Plant (PBR-MX). The Multiplex plant produces both electricity and transportable chemical energy via the thermochemical pipeline (TCP). The evaluation was limited to a direct cycle plant which has the steam generators and steam reformers in the primary circuit. Volume 1 reports the overall plant and reactor system and was prepared by the General Electric Company. Core scoping studies were performed which evaluated the effects of annular and cylindrical core configurations, radial blanket zones, burnup, and ball heavy metal loadings. The reactor system, including the PCRV, was investigated for both the annular and cylindrical core configurations. Volume 3 is an Appendix containing the equipment list for the plant and was also prepared by United Engineers and Constructors, Inc. It tabulates the major components of the plant and describes each in terms of quantity, type, orientation, etc., to provide a basis for cost estimation

  2. SR-Site: Oxygen ingress in the rock at Forsmark during a glacial cycle

    Energy Technology Data Exchange (ETDEWEB)

    Sidborn, Magnus (Kemakta Konsult AB (Sweden)); Sandstroem, Bjoern (WSP Sverige AB (Sweden)); Tullborg, Eva-Lena (Terralogica AB (Sweden)); Salas, Joaquin; Maia, Flavia; Delos, Anne; Molinero, Jorge (Amphos21 (Spain)); Hallbeck, Lotta; Pedersen, Karsten (Microbial Analytics Sweden AB (Sweden))

    2010-11-15

    The aim of this report is to assess the possibility for oxygen to be transported by glacial melt-water to canister positions in a final repository for spent nuclear fuel at the proposed location in Forsmark. The approach for this assessment is to combine reactive transport modelling with geological observations of present and historical indications of oxygen ingress. For safety assessment purposes a cautious approach in the modelling is required when estimating the extent of oxygen ingress. In this report, a cautious approach has been applied both in the conceptualisation of the problem and in the choice of input parameters used in the models. Oxygen consuming processes are only neglected in the modelling if they are expected to further decrease the extent of oxygen ingress. Several oxygen consuming processes have been identified, each of which may play an important role in the scavenging of oxygen along recharge flow paths in the rock. These processes include biological pathways with degradation of organic material of ground surface origin, and biotically mediated reactions with reduced rock minerals and with various materials expected to be present in the backfilled repository volume. In the absence of microbes most of these reactions may also follow abiotic pathways. Present day observations show that degradation of organic material is the most powerful oxygen scavenging process. At Forsmark, oxygen is generally depleted within a few metres under present day temperate conditions. Although biological activity is likely to exist also during different phases of a glaciation, large uncertainties exist regarding e.g. the population growth dynamics, the biotic reaction rates and the availability of organic material under the highly varying conditions expected. Microbial activity and degradation of organic material is therefore pessimistically neglected in the calculations in this report. In the absence of organic material, ferrous iron present in minerals in the rock

  3. SR-Site: Oxygen ingress in the rock at Forsmark during a glacial cycle

    International Nuclear Information System (INIS)

    Sidborn, Magnus; Sandstroem, Bjoern; Tullborg, Eva-Lena; Salas, Joaquin; Maia, Flavia; Delos, Anne; Molinero, Jorge; Hallbeck, Lotta; Pedersen, Karsten

    2010-11-01

    The aim of this report is to assess the possibility for oxygen to be transported by glacial melt-water to canister positions in a final repository for spent nuclear fuel at the proposed location in Forsmark. The approach for this assessment is to combine reactive transport modelling with geological observations of present and historical indications of oxygen ingress. For safety assessment purposes a cautious approach in the modelling is required when estimating the extent of oxygen ingress. In this report, a cautious approach has been applied both in the conceptualisation of the problem and in the choice of input parameters used in the models. Oxygen consuming processes are only neglected in the modelling if they are expected to further decrease the extent of oxygen ingress. Several oxygen consuming processes have been identified, each of which may play an important role in the scavenging of oxygen along recharge flow paths in the rock. These processes include biological pathways with degradation of organic material of ground surface origin, and biotically mediated reactions with reduced rock minerals and with various materials expected to be present in the backfilled repository volume. In the absence of microbes most of these reactions may also follow abiotic pathways. Present day observations show that degradation of organic material is the most powerful oxygen scavenging process. At Forsmark, oxygen is generally depleted within a few metres under present day temperate conditions. Although biological activity is likely to exist also during different phases of a glaciation, large uncertainties exist regarding e.g. the population growth dynamics, the biotic reaction rates and the availability of organic material under the highly varying conditions expected. Microbial activity and degradation of organic material is therefore pessimistically neglected in the calculations in this report. In the absence of organic material, ferrous iron present in minerals in the rock

  4. RADDA - Comparison of results of three ATWS/ATWC scenarios simulated with the help of POLCA-T and S3K/RELAP5

    International Nuclear Information System (INIS)

    Peltonen, J.

    2008-03-01

    The effects of ATWS and ATWC-events with control rods failing to enter the core has been evaluated in this project. To understand the uncertainties in using modern 3D-calculation methods two different codes were used in the project. The outputs from the two code packages were compared. Within the project the used code were first evaluated against a real event, pancake core at Forsmark 3. The results give important knowledge of the core responses for such events and on how to use different code to perform such calculations. The NKS report is only one minor part of the total project. The project was sponsored by TVO, Forsmark, OKG, Ringhals, SKI besides the NKS-funding. The results could be used for PSA-studies and for deterministically safety analysis. (au)

  5. Development of telerobotic systems for reactor decommissioning, (3)

    International Nuclear Information System (INIS)

    Usui, Hozumi; Fujii, Yoshio; Shinohara, Yoshikuni

    1991-01-01

    This paper describes the telerobotic system for reactor decommissioning in the scope of engineering demonstration of dismantling radioactive reactor internals of an experimental boiling water power reactor JPDR. The total system consists of a telerobotic manipulator system equipped with a multi-functional amphibious slave manipulator with a load capacity of 25 daN, a chain-driven transport system, and a computer-assisted monitoring and control system. Preceding to the application of the telerobotic system to actual dismantling operation, a mockup test was performed of dismantling the simulated reactor internals of actual-size by the method of underwater plasma arc cutting in order to study the performance of the telerobotic system in a realistic environment. The system was then successfully applied to dismantling the actual reactor internals according to the JPDR decommissioning program. (author)

  6. A Small-Animal Irradiation Facility for Neutron Capture Therapy Research at the RA-3 Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Emiliano Pozzi; David W. Nigg; Marcelo Miller; Silvia I. Thorp; Amanda E. Schwint; Elisa M. Heber; Veronica A. Trivillin; Leandro Zarza; Guillermo Estryk

    2007-11-01

    The National Atomic Energy Commission of Argentina (CNEA) has constructed a thermal neutron source for use in Boron Neutron Capture Therapy (BNCT) applications at the RA-3 research reactor facility located in Buenos Aires. The Idaho National Laboratory (INL) and CNEA have jointly conducted some initial neutronic characterization measurements for one particular configuration of this source. The RA-3 reactor (Figure 1) is an open pool type reactor, with 20% enriched uranium plate-type fuel and light water coolant. A graphite thermal column is situated on one side of the reactor as shown. A tunnel penetrating the graphite structure enables the insertion of samples while the reactor is in normal operation. Samples up to 14 cm height and 15 cm width are accommodated.

  7. Station Blackout Analysis for a 3-Loop Westinghouse PWR Reactor Using Trace

    International Nuclear Information System (INIS)

    El-Sahlamy, N.M.

    2017-01-01

    One of the main concerns in the area of severe accidents in nuclear reactors is that of station blackout (SBO). The loss of offsite electrical power concurrent with the unavailability of the onsite emergency alternating current (AC) power system can result in loss of decay heat removal capability, leading to a potential core damage which may lead to undesirable consequences to the public and the environment. To cope with an SBO, nuclear reactors are provided with protection systems that automatically shut down the reactor, and with safety systems to remove the core residual heat. This paper provides a best estimate assessment of the SBO scenario in a 3-loop Westinghouse PWR reactor. The evaluation is performed using TRACE, a best estimate computer code for thermal-hydraulic calculations. Two sets of scenarios for SBO analyses are discussed in the current work. The first scenario is the short term SBO where it is assumed that in addition to the loss of AC power, there is no DC power; i.e., no batteries are available. In the second scenario, a long term SBO is considered. For this scenario, DC batteries are available for four hours. The aim of the current SBO analyses for the 3-loop pressurized water reactor presented in this paper is to focus on the effect of the availability of a DC power source to delay the time to core uncovers and heatup

  8. The qualification of U3O8 as research reactor fuel

    International Nuclear Information System (INIS)

    Krull, W.

    1983-01-01

    This report summarizes the today knowledge of the qualification status of U 3 O 8 as low enriched ( 3 O 8 is so far qualified to start testing of ten (10) fuel elements with an U-density of 3.1 g U/cc in the FRG-2 research reactor. (orig.) [de

  9. Operation experience with the 3 MW TRIGA Mark-II research reactor of Bangladesh

    International Nuclear Information System (INIS)

    Islam, M.S.; Haque, M.M.; Salam, M.A.; Rahman, M.M.; Khandokar, M.R.I.; Sardar, M.A.; Saha, P.K.; Haque, A.; Malek Sonar, M.A.; Uddin, M.M.; Hossain, S.M.S.; Zulquarnain, M.A.

    2004-01-01

    The 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC) has been operating since September 14, 1986. The reactor is used for radioisotope production ( 131 I, 99m Tc, 46 Sc), various R and D activities and manpower training. The reactor has been operated successfully since it's commissioning with the exception of a few reportable incidents. Of these, the decay tank leakage incident of 1997 is considered to be the most significant one. As a result of this incident, reactor operation at full power under forced-convection mode remained suspended for about 4 years. During that time, the reactor was operated at a power level of 250 kW so as to carry out experiments that require lower neutron flux. This was made possible by establishing a temporary by pass connection across the decay tank using local technology. The other incident was the contamination of the Dry Central Thimble (DCT) that took place in March 2002 when a pyrex vial containing 50 g of TeO 2 powder got melted inside the DCT. The vial was melted due to high heat generation on its surface while the reactor was operated for 8 hours at 3 MW for trial production of Iodine-131 ( 131 I). A Wet Central Thimble (WCT) was used to replace the damaged DCT in June 2002 such that the reactor operation could be resumed. The WCT was again replaced by a new DCT in June 2003 such that radioisotope production could be continued. A total of 873 irradiation requests (IRs) have been catered for different reactor uses. Out of these, 114 IRs were for radioisotope (RI) production and 759 IRs for different experiments. The total amount of RI produced stands at about 2100 GBq. The total amount of burn-up-fuel is about 6158 MWh. Efforts are on to undertake an ADP project so as to convert the analog console and I and C system of the reactor into digital one. The paper summarizes the reactor operation experiences focusing on troubleshooting, rectification, modification, RI production, various R and D

  10. Computational Analysis of Nuclear Safety Parameters of 3 MW TRIGA Mark-II Research Reactor Based on Evaluated Nuclear Data Libraries JENDL-3.3 and ENDF/B-VII.0

    International Nuclear Information System (INIS)

    Khan, Jahirul Haque

    2013-01-01

    The objective of this study is to explain the main nuclear safety parameters of 3 MW TRIGA Mark-II Research Reactor at AERE, Savar, Dhaka, Bangladesh from the viewpoint of reactor safety and also reactor operator. The most important nuclear reactor physics safety parameters are power distribution, power peaking factors, shutdown margin, control rod worth, excess reactivity and fuel temperature reactivity coefficient. These parameters are calculated using the chain of the computer codes the SRAC-PIJ for cell calculation based on neutron transport theory and the SRAC-CITATION for core calculation based on neutron diffusion equation. To achieve this objective the TRIGA model is developed by the 3-D diffusion code SRAC-CITATION based on the group constants that come from the collision probability transport code SRAC-PIJ. In this study the evaluated nuclear data libraries JENDL-3.3 and ENDF/B-VII.0 are used. The calculated most important reactor physics parameters are compared to the safety analysis report (SAR) values as well as earlier published MCNP results (numerically benchmark). It was found that the calculated results show a good agreement between the said libraries. Besides, in most cases the calculated results reveal a reasonable agreement with the SAR values (by General Atomic) as well as the MCNP results. In addition, this analysis can be used as the inputs for thermal-hydraulic calculations of the TRIGA fresh core in the steady state and pulse mode operation. Because of power peaking factors, power distributions and temperature reactivity coefficients are the most important reactor safety parameters for normal operation and transient safety analysis in research as well as in power reactors. They form the basis for technical specifications and limitations for reactor operation such as loading pattern limitations for pulse operation (in TRIGA). Therefore, this analysis will be very important to develop the nuclear safety parameters data of 3 MW TRIGA Mark

  11. Gas-cooled reactor thermal-hydraulics using CAST3M and CRONOS2 codes

    International Nuclear Information System (INIS)

    Studer, E.; Coulon, N.; Stietel, A.; Damian, F.; Golfier, H.; Raepsaet, X.

    2003-01-01

    The CEA R and D program on advanced Gas Cooled Reactors (GCR) relies on different concepts: modular High Temperature Reactor (HTR), its evolution dedicated to hydrogen production (Very High Temperature Reactor) and Gas Cooled Fast Reactors (GCFR). Some key safety questions are related to decay heat removal during potential accident. This is strongly connected to passive natural convection (including gas injection of Helium, CO 2 , Nitrogen or Argon) or forced convection using active safety systems (gas blowers, heat exchangers). To support this effort, thermal-hydraulics computer codes will be necessary tools to design, enhance the performance and ensure a high safety level of the different reactors. Accurate and efficient modeling of heat transfer by conduction, convection or thermal radiation as well as energy storage are necessary requirements to obtain a high level of confidence in the thermal-hydraulic simulations. To achieve that goal a thorough validation process has to ve conducted. CEA's CAST3M code dedicated to GCR thermal-hydraulics has been validated against different test cases: academic interaction between natural convection and thermal radiation, small scale in-house THERCE experiments and large scale High Temperature Test Reactor benchmarks such as HTTR-VC benchmark. Coupling with neutronics is also an important modeling aspect for the determination of neutronic parameters such as neutronic coefficient (Doppler, moderator,...), critical position of control rods...CEA's CAST3M and CRONOS2 computer codes allow this coupling and a first example of coupled thermal-hydraulics/neutronics calculations has been performed. Comparison with experimental data will be the next step with High Temperature Test Reactor experimental results at nominal power

  12. 3-DB, 3-D Multigroup Diffusion, X-Y-Z, R-Theta-Z, Triangular-Z Geometry, Fast Reactor Burnup

    International Nuclear Information System (INIS)

    Hardie, R.W.; Little, W.W. Jr.; Mroz, W.

    1974-01-01

    1 - Description of problem or function: 3DB is a three-dimensional (x-y-z, r-theta-z, triangular-z) multigroup diffusion code for use in detailed fast-reactor criticality and burnup analysis. The code can be used to - (a) compute k eff and perform criticality searches on time absorption, reactor composition, and reactor dimensions by means of either a flux or an adjoint model, (b) compute material burnup using a flexible material shuffling scheme, and (c) compute flux distributions for an arbitrary extraneous source. 2 - Method of solution: Eigenvalues are computed by standard source- iteration techniques. Group re-balancing and successive over-relaxation with line inversion are used to accelerate convergence. Adjoint solutions are obtained by inverting the input data and redefining the source terms. Material burnup is by reactor zone. The burnup rate is determined by the zone and energy-averaged cross sections which are recomputed after each time-step. The isotopic chains, which can contain any number of isotopes are formed by the user. The code does not contain built- in or internal chains. 3 - Restrictions on the complexity of the problem: Since variable dimensioning is employed, no simple bounds can be stated

  13. A robot-automated work site for repair of the Chinon A3 reactor

    International Nuclear Information System (INIS)

    Raynal, A.

    1987-01-01

    In 1982, following degradation due to corrosion of low-carbon steel by carbon dioxide gas, the utility undertook to repair some of the support structures at Chinon A3. This involved consolidation and reinforcing thermocouples and gas monitor pipeworks supports. A welding process was selected and the use of robots became indispensable because of the large number of components to be replaced (200 per outage). Two robots, supplied with tool heads and replacement components from outside the reactor were used. The robots and their servers were coordinated by a central computer and monitored by a closed circuit television system. Each repair operation was performed after ''training'' on a full-scale mockup of the top of the reactor reconstructed from telemetry of the real reactor dimensions. Since becoming operational in June 1986, the robots have accumulated over 20 000 hours of operation and seventy parts have been welded to the reactor. A 3D CAD system has been adapted to simulate the robots and analyse long trajectories in order to reduce robot learning time [fr

  14. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part I; Redovisning av saekerhet efter foerslutning av slutfoervaret foer anvaent kaernbraensle. Huvudrapport fraan projekt SR-Site. Del I

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  15. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part II; Redovisning av saekerhet efter foerslutning av slutfoervaret foer anvaent kaernbraensle. Huvudrapport fraan projekt SR-Site. Del II

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  16. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part III; Redovisning av saekerhet efter foerslutning av slutfoervaret foer anvaent kaernbraensle. Huvudrapport fraan projekt SR-Site. Del III

    Energy Technology Data Exchange (ETDEWEB)

    2011-07-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  17. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part III

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  18. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part I

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  19. EL3 reactor description and safety analysis report; Pile EL3, rapport descriptif et de surete

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1969-02-01

    The EL-3 reactor is an experimental pile. Heterogenous type reactor, water moderated and cooled it uses slightly enriched uranium oxide as fuel (4.5 percent) distributed in vertical cells that constitute the core (the maximum number of cells is 99). It is conceived to function at a maximal thermal power of 20 MW. It supplies a maximum thermal neutron flux of 10{sup 14} neutrons/cm{sup 2}/sec. It has several experimental devices. The EL-3 reactor is surrounded by auxiliary circuits of fluids, in a sealed containment, slightly depressed. The primary heavy water coolant circuit is completely included in this containment. Its cooling is made by the intermediary of a light water secondary circuit by atmospheric refrigerants. The ventilation circuits of the sealed containment and the reactor block do not release air outside, under nornal functioning, by a particularly studied chimney only after filtering and eventually dilution. The eventual contamination of the light water or air by active products is permanently monitored to allow the reactor shutdown and avoid the release in atmosphere of dangerous products. The EL-3 reactor, laying down in may 1955, has diverged in july 1957, made its first ascending in power in december 1957 and reached its complete power in april 1958. The positioning of actual fuel (snow crystal) was made during summer 1964. Reactor with an experimental aim, it is used for theoretical and technological studies by material irradiation in the experimental channels and the core cells, with possibilities to constitute independent loops (relative to the cooling fluids). Thirty vertical channels are devoted to the fabrication of artificial radioelements. [French] La pile EL-3 est une pile experimentale. Du type heterogene, moderee et refroidie a l'eau lourde elle utilise comme combustible de l'oxygene d'uranium faiblement enrichi (4,5 p.cent) reparti en cellules verticales qui constituent le coeur (le nombre maximal de cellules est de, 99). Elle est

  20. EL3 reactor description and safety analysis report; Pile EL3, rapport descriptif et de surete

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1969-02-01

    The EL-3 reactor is an experimental pile. Heterogenous type reactor, water moderated and cooled it uses slightly enriched uranium oxide as fuel (4.5 percent) distributed in vertical cells that constitute the core (the maximum number of cells is 99). It is conceived to function at a maximal thermal power of 20 MW. It supplies a maximum thermal neutron flux of 10{sup 14} neutrons/cm{sup 2}/sec. It has several experimental devices. The EL-3 reactor is surrounded by auxiliary circuits of fluids, in a sealed containment, slightly depressed. The primary heavy water coolant circuit is completely included in this containment. Its cooling is made by the intermediary of a light water secondary circuit by atmospheric refrigerants. The ventilation circuits of the sealed containment and the reactor block do not release air outside, under nornal functioning, by a particularly studied chimney only after filtering and eventually dilution. The eventual contamination of the light water or air by active products is permanently monitored to allow the reactor shutdown and avoid the release in atmosphere of dangerous products. The EL-3 reactor, laying down in may 1955, has diverged in july 1957, made its first ascending in power in december 1957 and reached its complete power in april 1958. The positioning of actual fuel (snow crystal) was made during summer 1964. Reactor with an experimental aim, it is used for theoretical and technological studies by material irradiation in the experimental channels and the core cells, with possibilities to constitute independent loops (relative to the cooling fluids). Thirty vertical channels are devoted to the fabrication of artificial radioelements. [French] La pile EL-3 est une pile experimentale. Du type heterogene, moderee et refroidie a l'eau lourde elle utilise comme combustible de l'oxygene d'uranium faiblement enrichi (4,5 p.cent) reparti en cellules verticales qui constituent le coeur (le nombre maximal de cellules est de, 99

  1. Uranium-fuel thermal reactor benchmark testing of CENDL-3

    International Nuclear Information System (INIS)

    Liu Ping

    2001-01-01

    CENDL-3, the new version of China Evaluated Nuclear Data Library are being processed, and distributed for thermal reactor benchmark analysis recently. The processing was carried out using the NJOY nuclear data processing system. The calculations and analyses of uranium-fuel thermal assemblies TRX-1,2, BAPL-1,2,3, ZEEP-1,2,3 were done with lattice code WIMSD5A. The results were compared with the experimental results, the results of the '1986'WIMS library and the results based on ENDF/B-VI. (author)

  2. Quality control of GPS deformation data from Forsmark and analysis of crustal deformation in the local scale

    International Nuclear Information System (INIS)

    Ekman, Lennart; Ekman, Mats

    2013-03-01

    A network comprising seven GPS stations was established at Forsmark, Sweden, within about 10 km radius from the centre of the investigation area for a final repository for spent nuclear fuel with the purpose of monitoring slow rock motion. During the period November 2005 to December 2009, GPS data were collected in eighteen intermittent measurement campaigns, each with a duration of between three and seven days. As shown in Gustafson and Ljungberg (2010), the data expose a considerable scatter, indicating a non-linear variability of the GPS baseline velocities. However, the commission narrated in Gustafson and Ljungberg (2010) was restricted to account only for the field performance of the GPS measurement campaign and to present the resulting measurement data per se, merely supplemented with a linear regression solution for the baseline motions. The preliminary interpretation of GPS data in Gustafson and Ljungberg (2010) was in the present report followed by a closer examination where the non-linear variability is modelled as sinusoidal. Evidence for sinusoidal variations were also found in resulting data from GPS measurements at the Aespoe/Laxemar area at Oskarshamn (Sjoeberg et al. 2004), as well as in GPS data from several sites in western, middle and north-eastern Finland (Ollikainen et al. 2004, Ahola et al. 2008, Poutanen et al. 2010). We here postulate that the baseline velocities are characterized by a long-term linear drift superposed by a non-linear sinusoidal motion. This was modelled in two steps. Initially an Auto Regressive (AR) model was applied and the linear trends between the GPS stations were estimated. In a second step, an Auto Regressive Moving Average (ARMA) model was estimated for (almost) all baselines. The residuals between the original data and the one-step predictor for the ARMA model were then used to estimate new linear trends for the baselines. Our analysis of the Forsmark GPS data indicates relative motions more than 10 times slower

  3. Quality control of GPS deformation data from Forsmark and analysis of crustal deformation in the local scale

    Energy Technology Data Exchange (ETDEWEB)

    Ekman, Lennart; Ekman, Mats [LE Geokonsult AB, Baelinge (Sweden)

    2013-03-15

    A network comprising seven GPS stations was established at Forsmark, Sweden, within about 10 km radius from the centre of the investigation area for a final repository for spent nuclear fuel with the purpose of monitoring slow rock motion. During the period November 2005 to December 2009, GPS data were collected in eighteen intermittent measurement campaigns, each with a duration of between three and seven days. As shown in Gustafson and Ljungberg (2010), the data expose a considerable scatter, indicating a non-linear variability of the GPS baseline velocities. However, the commission narrated in Gustafson and Ljungberg (2010) was restricted to account only for the field performance of the GPS measurement campaign and to present the resulting measurement data per se, merely supplemented with a linear regression solution for the baseline motions. The preliminary interpretation of GPS data in Gustafson and Ljungberg (2010) was in the present report followed by a closer examination where the non-linear variability is modelled as sinusoidal. Evidence for sinusoidal variations were also found in resulting data from GPS measurements at the Aespoe/Laxemar area at Oskarshamn (Sjoeberg et al. 2004), as well as in GPS data from several sites in western, middle and north-eastern Finland (Ollikainen et al. 2004, Ahola et al. 2008, Poutanen et al. 2010). We here postulate that the baseline velocities are characterized by a long-term linear drift superposed by a non-linear sinusoidal motion. This was modelled in two steps. Initially an Auto Regressive (AR) model was applied and the linear trends between the GPS stations were estimated. In a second step, an Auto Regressive Moving Average (ARMA) model was estimated for (almost) all baselines. The residuals between the original data and the one-step predictor for the ARMA model were then used to estimate new linear trends for the baselines. Our analysis of the Forsmark GPS data indicates relative motions more than 10 times slower

  4. Investigations related to a one-piece removal of the reactor block in the frame of the JRR-3 reconstruction program

    International Nuclear Information System (INIS)

    Onishi, N.; Kanenari, A.; Futamura, Y.; Sakurai, H.; Suzuki, S.; Nagase, T.; Iwatani, A.; Otsubo, F.

    1987-01-01

    In the Japan Atomic Energy Research Institute (JAERI), an outdated research reactor (Japan Research Reactor No.3; JRR-3) was removed to a storage facility between October 14th and November 7th, 1986. The removal of the 2250-ton reactor block (10 x 10 x 10 m) was performed as a part of a program to replace the JRR-3's core (10-MW thermal) with an upgraded research reactor core. The heavy water and fuel elements were taken out from the JRR-3 before removal work began. The reactor block was raised about 3.7 meters, using a 12-cubic meter steel frame and a center-hole jack system. The reactor block was then transported horizontally about 34 meters on steel rails, using four 100-ton jacks, to a storage facility. Finally, the reactor block was lowered 14 meters into the storage facility. After the reactor block was stored, a new 20-MW thermal, light-water moderated and cooled JRR-3 core will be built, with criticality targeted for 1989

  5. Decommissioning of the BR3 pressurized-water reactor

    International Nuclear Information System (INIS)

    Massaut, V.

    1996-01-01

    The dismantling and the decommissioning of nuclear installations at the end of their life-cycle is a new challenge to the nuclear industry. Different techniques and procedures for the dismantling of a nuclear power plant on an existing installation, the BR-3 pressurized-water reactor, are described. The scientific programme, objectives, achievements in this research area at the Belgian Nuclear Research Centre SCK-CEN for 1995 are summarized

  6. Application of RELAP5-3D code for thermal analysis of the ADS reactor core

    International Nuclear Information System (INIS)

    Fernandes, Gustavo Henrique Nazareno

    2018-01-01

    Nuclear power is essential to supply global energy demand. Therefore, in order to use nuclear fuel more efficiently, more efficient nuclear reactors technologies researches have been intensified, such as hybrid systems, composed of particle accelerators coupled into nuclear reactors. In order to add knowledge to such studies, an innovative reactor design was considered where the RELAP5-3D thermal-hydraulic analysis code was used to perform a thermal analysis of the core, either in stationary operation or in situations transitory. The addition of new kind of coolants, such as, liquid salts, among them Flibe, lead, lead-bismuth, sodium, lithium-bismuth and lithium-lead was an important advance in this version of the code, making possible to do the thermal simulation of reactors that use these types of coolants. The reactor, object of study in this work, is an innovative reactor, due to its ability to operate in association with an Accelerator Driven System (ADS), considered a predecessor system of the next generation of nuclear reactors (GEN IV). The reactor selected was the MYRRHA (Multi-purpose Hybrid Research Reactor for High tech Applications) due to the availability of data to perform the simulation. In the modeling of the reactor with the code RELAP5-3D, the core was simulated using nodules with 1, 7, 15 and 51 thermohydraulic channels and eutectic lead-bismuth (LBE) as coolant. The parameters, such as, pressure, mass flow and coolant and heat structure temperature were analyzed. In addition, the thermal behavior of the core was evaluated by varying the type of coolant (sodium) in substitution for the LBE of the original design using the model with 7 thermohydraulic channels. The results of the steady-state calculations were compared with data from the literature and the proposed models were verified certifying the ability of the RELAP5-3D code to simulate this innovative reactor. After this step, it was analysed cases of transients with loss of coolant flow

  7. Proceedings of 2. Yugoslav symposium on reactor physics, Part 3, Herceg Novi (Yugoslavia), 27-29 Sep 1966

    International Nuclear Information System (INIS)

    1966-01-01

    This Volume 3 of the Proceedings of 2. Yugoslav symposium on reactor physics includes three papers describing the following: model for spatial synthesis of automated control system of the GCR type reactor; model for analysis of hydrodynamic processes at the BHWR type reactors; mathematical model for safety analysis of heavy water power reactor

  8. Filtered atmospheric venting of light water reactor containments

    International Nuclear Information System (INIS)

    Hedgran, A.; Ahlstroem, P.E.; Nilsson, L.; Persson, Aa.

    1982-11-01

    The aim of filtered venting is to improve the function of the reactor containment in connection with very severe accidents. By equipping the containment with a safety valve for pressure relief and allowing the released gases to pass through an effective filter, it should be possible to achieve a considerable protective effect. The work has involved detailed studies of the core meltdown sequence, how the molten core material runs out of the reactor vessel, what effect it has on concrete and other structures and how final cooling of the molten core material takes place. On the basis of previous Swedish studies, the project has chosen to study a filter concept that consists of a gravel bed of large volume. This filter plant shall not only retain the radioactive particles that escape from the containment through the vent line, but shall also condense the accompanying steam. After the government decided in 1981 that Barsebaeck was to be equipped with filtered venting and issued specifications regarding its performance, the project aimed at obtaining results that could be used to design and verify a plant for filtered venting at the Barsebaeck nuclear power station. As far as the other Swedish nuclear power plants at Oskarshamn, Ringhals and Forsmark are concerned, the results are only applicable to a limited extent. Additional studies are required for these nuclear power plants before the value of filtered venting can be assessed. Based on the results of experiments and analyses, the project has made a safety analysis with Barsebaeck as a reference plant in order to study how the introduction of filtered venting affects the safety level at a station. In summary, the venting function appears to entail a not insignificant reduction of risks for boiling water reactors of the Barsebaeck type. For a number of types of such very severe core accident cases, the filter design studied ensures a substantial reduction of the releases. However it has not been possible within the

  9. Reactor core of FBR type reactor

    International Nuclear Information System (INIS)

    Hayashi, Hideyuki; Ichimiya, Masakazu.

    1994-01-01

    A reactor core is a homogeneous reactor core divided into two regions of an inner reactor core region at the center and an outer reactor core region surrounding the outside of the inner reactor core region. In this case, the inner reactor core region has a lower plutonium enrichment degree and less amount of neutron leakage in the radial direction, and the outer reactor core region has higher plutonium enrichment degree and greater amount of neutron leakage in the radial direction. Moderator materials containing hydrogen are added only to the inner reactor core fuels in the inner reactor core region. Pins loaded with the fuels with addition of the moderator materials are inserted at a ratio of from 3 to 10% of the total number of the fuel pins. The moderator materials containing hydrogen comprise zirconium hydride, titanium hydride, or calcium hydride. With such a constitution, fluctuation of the power distribution in the radial direction along with burning is suppressed. In addition, an absolute value of the Doppler coefficient can be increased, and a temperature coefficient of coolants can be reduced. (I.N.)

  10. Chemical characteristics of surface systems in the Forsmark area. Visualisation and statistical evaluation of data from shallow groundwater, precipitation, and regolith

    International Nuclear Information System (INIS)

    Troejbom, Mats; Soederbaeck, Bjoern

    2006-02-01

    The Swedish Nuclear Fuel and Waste management Co (SKB) initiated site investigations for a deep repository for spent nuclear fuel at two different sites in Sweden, Forsmark and Oskarshamn, in 2002. This report evaluates the results from chemical investigations of the surface system in the Forsmark area during the period November 2002 - March 2005. The evaluation includes data from surface waters (lakes, streams and the sea), precipitation, shallow groundwater and regolith (till, soil, peat, sediments and biota) in the area. Results from surface waters are not presented in this report since these were treated in a recently published report. The main focus of the study is to visualize the vast amount of data collected hitherto in the site investigations, and to give a chemical characterisation of the investigated media at the site. The results will be used to support the site descriptive models, which in turn are used for safety assessment studies and for the environmental impact assessment. The data used consist of water chemical composition in lakes, streams, coastal sites, and in precipitation, predominantly sampled on a monthly basis, and in groundwater from soil tubes and wells, sampled up to four times per year. Moreover, regolith data includes information on the chemical composition of till, soil, sediment and vegetation samples from the area. The characterisations include all measured chemical parameters, i.e. major and minor constituents, trace elements, nutrients, isotopes and radio nuclides, as well as field measured parameters. The evaluation of data from each medium has been divided into the following parts: Characterisation of individual sampling sites, and comparisons within and among sampling sites as well as comparisons with local, regional and national reference data; Analysis of time trends and seasonal variation (for shallow groundwater); Exploration of relationships among the various chemical parameters. For all investigated parameters, the

  11. Hybrid Reactor Simulation and 3-D Information Display of BWR Out-of-Phase Oscillation

    International Nuclear Information System (INIS)

    Edwards, Robert; Huang, Zhengyu

    2001-01-01

    The real-time hybrid reactor simulation (HRS) capability of the Penn State TRIGA reactor has been expanded for boiling water reactor (BWR) out-of-phase behavior. During BWR out-of-phase oscillation half of the core can significantly oscillate out of phase with the other half, while the average power reported by the neutronic instrumentation may show a much lower amplitude for the oscillations. A description of the new HRS is given; three computers are employed to handle all the computations required, including real-time data processing and graph generation. BWR out-of-phase oscillation was successfully simulated. By adjusting the reactivity feedback gains from boiling channels to the TRIGA reactor and to the first harmonic mode power simulation, limit cycle can be generated with both reactor power and the simulated first harmonic power. A 3-D display of spatial power distributions of fundamental mode, first harmonic, and total powers over the reactor cross section is shown

  12. Simulation of channel blockage for the IEA-R1 research reactor using RELAP/MOD 3

    International Nuclear Information System (INIS)

    Oliveira, Eduardo C.F. de; Castrillo, Lazara Silveira

    2015-01-01

    Research reactors have great importance in the area of nuclear technology, such as radioisotope production, research in nuclear physics, development of new technologies and staff training for reactor operation. The IEA-R1 is a Brazilian research reactor type pool, located at the IPEN (Instituto de Pesquisas Energeticas e Nucleares). In this work is simulated with computer code RELAP5 / MOD 3.3.2 gamma, the effect caused by partial and complete blockage of a channel in MTR fuel element of the IEA-R1 core, in order to analyzed the thermal hydraulic parameters on adjacent channels. (author)

  13. Simulation of channel blockage for the IEA-R1 research reactor using RELAP/MOD 3

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Eduardo C.F. de; Castrillo, Lazara Silveira, E-mail: ecfoliveira@hotmail.com, E-mail: lazara.castrillo@upe.br [Universidade de Pernambuco (UPE), Recife, PE (Brazil). Escola Politecnica de Pernambuco

    2015-07-01

    Research reactors have great importance in the area of nuclear technology, such as radioisotope production, research in nuclear physics, development of new technologies and staff training for reactor operation. The IEA-R1 is a Brazilian research reactor type pool, located at the IPEN (Instituto de Pesquisas Energeticas e Nucleares). In this work is simulated with computer code RELAP5 / MOD 3.3.2 gamma, the effect caused by partial and complete blockage of a channel in MTR fuel element of the IEA-R1 core, in order to analyzed the thermal hydraulic parameters on adjacent channels. (author)

  14. Advances in Reactor physics, mathematics and computation. Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    These proceedings of the international topical meeting on advances in reactor physics, mathematics and computation, volume 3, are divided into sessions bearing on: - poster sessions on benchmark and codes: 35 conferences - review of status of assembly spectrum codes: 9 conferences - Numerical methods in fluid mechanics and thermal hydraulics: 16 conferences - stochastic transport and methods: 7 conferences.

  15. Simulation of a reactor FBR with hexagonal-Z geometry using the code PARCS 3.1; Simulacion de un reactor FBR con geometria hexagonal-Z usando el codigo PARCS 3.1

    Energy Technology Data Exchange (ETDEWEB)

    Reyes F, M. C.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. Instituto Politecnico Nacional s/n, U.P. Adolfo Lopez Mateos, Edificio 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Filio L, C., E-mail: rf.melisa@gmail.com [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    The nuclear reactor core type FBR (Fast Breeder Reactor) was modeled in three dimensions of hexagonal-Z geometry using the code PARCS (Purdue Advanced Reactor Core Simulator) version 3.1 developed by Purdue University researchers. To carry out the modeling of the mentioned reactor was taken the corresponding information to one of the described benchmarks in the document NEACRP-L-330 (3-D Neutron Transport Benchmarks, 1991); fundamentally the corresponding to the geometric data and the cross sections. Being a quick reactor of breeding, known as the Knk-II, for which are considered 4 energy groups without dispersions up. The reactor core is formed by prismatic elements of hexagonal transversal cut where part of them only corresponds to nuclear fuel assemblies. This has four reflector rings and 6 identical control elements that together with the active part of the core is configured with 8 different types of elements.With the extracted information of the mentioned document the entrance file was prepared for PARCS 3.1 only considering a sixth part of the core due to the symmetry that presents their configuration. The NEACRP-L-330 shows a wide range of results reported by those who collaborated in its elaboration using different solution techniques that go from the Monte Carlo method to the approaches S{sub 2} and P{sub 1}. Of all the results were selected those obtained with the code HEXNOD, to which were carried out a comparison of the effective multiplication factor, being smaller differences to the 300 pcm, for three different scenarios: a) with the control bars extracted totally, b) with the semi-inserted control bars and c) with the control bars inserted completely and two different axial meshes, a thick mesh with 14 slices and another fine with 38, that which implies that the results can be considered very similar among if same. Radial maps and axial profiles are included, as much of the power as of the neutrons flow. (Author)

  16. State of the art of second international exercise on benchmarks in BWR reactors

    International Nuclear Information System (INIS)

    Verdu, G.; Munoz-Cobo, J. L.; Palomo, M. J.; Escriva, A.; Ginestar, D.

    1998-01-01

    This is a second in series of Benchmarks based on data from operating Swedish BWRs. The first one concerned measurements made in cycles 14,15 16 and 17 at Ringhals 1 Nuclear Power Plant and addressed predictive power of analytical tools used in BWR stability analysis. Part of the data was disclosed only after participants had provided their results. This work has been published in the report: NEA/NSC/DOC(96)22, November 1996. In this report it was recognised that there is a need for better qualification of the applied noise analysis methods. A follow up Benchmark was thus proposed dedicated to the analysis of time series data and including the evaluation of both global and regional stability of Forsmarks 1 and 2 Nuclear Power Plant. In this second Benchmark have participated Forsmarks Kraftgrupp AB,NEA Nuclear Science Committee, CSN Consejo de Seguridad Nuclear and Department of Chemical and Nuclear Engineering of Polytechnic University of Valencia. (Author)

  17. Preparations for the shipment of RA-3 reactor irradiated fuel

    International Nuclear Information System (INIS)

    Goldschmidt, Adrian; Novara, Oscar; Lafuente, Jose

    2002-01-01

    During the last quarter of 2000, in the Radioactive Waste Management Area of the Argentine National Commission of Atomic Energy (CNEA), located at Ezeiza Atomic Center (CAE), activities associated to the shipment of 207 MTR spent fuels containing high enrichment uranium were carried out within the Foreign Research Reactor/Domestic Research Reactor Receipt Program launched by the US Department of Energy (DOE). The MTR spent fuel shipped to Savannah River Site (SRS) was fabricated in Argentina with 90% enriched uranium of US origin and it was utilized in the operation of the research and radioisotope production reactor RA-3 from 1968 until 1987. After a cooling period at the reactor, the spent fuel was transferred to the Central Storage Facility (CSF) located in the waste management area of CAE for interim storage. The spent fuel (SF) inventory consisted of 166 standard assemblies (SA) and 41 control assemblies (CA). Basically, the activities performed were the fuel conditioning operations inside the storage facility (remote transference of the assemblies to the operation pool, fuel cropping, fuel re-identification, loading in transport baskets, etc.) conducted by CNEA. The loading of the filled baskets in the transport casks (NAC-LWT) by means of intermediate transfer systems and loaded casks final preparations were conducted by NAC personnel (DOE's contractor) with the support of CNEA personnel. (author)

  18. Preliminary safety evaluation for the Forsmark area. Based on data and site descriptions after the initial site investigation stage

    International Nuclear Information System (INIS)

    Andersson, Johan

    2005-08-01

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Forsmark area have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that, even considering remaining uncertainties, the Forsmark area meets all stated safety requirements and preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Forsmark area. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Nevertheless, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry inside the target area would be needed to more firmly define locations of the suitable deposition volumes. There is substantial uncertainty in the Discrete Fracture Network model. Further reduction of the uncertainties, if needed, would probably only be possible from the underground, detailed investigation phase. Efforts need also be spent on improving the DFN-modelling. There are assumptions made in current models that could be challenged and there seems to be room for better use of the borehole information. It is particularly important to provide

  19. Preliminary safety evaluation for the Forsmark area. Based on data and site descriptions after the initial site investigation stage

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan [JA Streamflow AB, Aelvsjoe (Sweden)

    2005-08-01

    The main objectives of this Preliminary Safety Evaluation (PSE) of the Forsmark area have been to determine, with limited efforts, whether the feasibility study's judgement of the suitability of the candidate area with respect to long-term safety holds up in the light of the actual site investigation data; to provide feedback to continued site investigations and site-specific repository design and to identify site-specific scenarios and geoscientific issues for further analyses. The PSE focuses on comparing the attained knowledge of the sites with the suitability criteria as set out by SKB. The PSE does not aim at comparing sites and does not assess compliance with safety and radiation protection criteria. The evaluation shows that, even considering remaining uncertainties, the Forsmark area meets all stated safety requirements and preferences. Consequently, from a safety point of view, there is no reason not to continue the Site Investigations of the Forsmark area. There are still uncertainties to resolve and the safety would eventually need to be verified through a full safety assessment. Nevertheless, this Preliminary Safety Evaluation demonstrates that it is likely that a safe repository for spent nuclear fuel of the KBS-3 type could be constructed at the site. The following feedback is provided to the site investigations and the associated site modelling: Reducing the uncertainty on the deformation zone geometry inside the target area would be needed to more firmly define locations of the suitable deposition volumes. There is substantial uncertainty in the Discrete Fracture Network model. Further reduction of the uncertainties, if needed, would probably only be possible from the underground, detailed investigation phase. Efforts need also be spent on improving the DFN-modelling. There are assumptions made in current models that could be challenged and there seems to be room for better use of the borehole information. It is particularly important to

  20. Sensitivity analysis and development of calibration methodology for near-surface hydrogeology model of Forsmark

    International Nuclear Information System (INIS)

    Aneljung, Maria; Gustafsson, Lars-Goeran

    2007-04-01

    The hydrological modelling system MIKE SHE has been used to describe near-surface groundwater flow, transport mechanisms and the contact between ground- and surface water at the Forsmark site. The surface water system at Forsmark is described with the 1D modelling tool MIKE 11, which is fully and dynamically integrated with MIKE SHE. In spring 2007, a new data freeze will be available and a process of updating, rebuilding and calibrating the MIKE SHE model will start, based on the latest data set. Prior to this, it is important to gather as much knowledge as possible on calibration methods and to define critical calibration parameters and areas within the model. In this project, an optimization of the numerical description and an initial calibration of the MIKE SHE model has been made, and an updated base case has been defined. Data from 5 surface water level monitoring stations, 4 surface water discharge monitoring stations and 32 groundwater level monitoring stations (SFM soil boreholes) has been used for model calibration and evaluation. The base case simulations generally show a good agreement between calculated and measured water levels and discharges, indicating that the total runoff from the area is well described by the model. Moreover, with two exceptions (SFM0012 and SFM0022) the base case results show very good agreement between calculated and measured groundwater head elevations for boreholes installed below lakes. The model also shows a reasonably good agreement between calculated and measured groundwater head elevations or depths to phreatic surfaces in many other points. The following major types of calculation-measurement differences can be noted: Differences in groundwater level amplitudes due to transpiration processes. Differences in absolute mean groundwater head, due to differences between borehole casing levels and the interpolated DEM. Differences in absolute mean head elevations, due to local errors in hydraulic conductivity values

  1. Sensitivity analysis and development of calibration methodology for near-surface hydrogeology model of Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Aneljung, Maria; Gustafsson, Lars-Goeran [DHI Water and Environment AB, Goeteborg (Sweden)

    2007-04-15

    The hydrological modelling system MIKE SHE has been used to describe near-surface groundwater flow, transport mechanisms and the contact between ground- and surface water at the Forsmark site. The surface water system at Forsmark is described with the 1D modelling tool MIKE 11, which is fully and dynamically integrated with MIKE SHE. In spring 2007, a new data freeze will be available and a process of updating, rebuilding and calibrating the MIKE SHE model will start, based on the latest data set. Prior to this, it is important to gather as much knowledge as possible on calibration methods and to define critical calibration parameters and areas within the model. In this project, an optimization of the numerical description and an initial calibration of the MIKE SHE model has been made, and an updated base case has been defined. Data from 5 surface water level monitoring stations, 4 surface water discharge monitoring stations and 32 groundwater level monitoring stations (SFM soil boreholes) has been used for model calibration and evaluation. The base case simulations generally show a good agreement between calculated and measured water levels and discharges, indicating that the total runoff from the area is well described by the model. Moreover, with two exceptions (SFM0012 and SFM0022) the base case results show very good agreement between calculated and measured groundwater head elevations for boreholes installed below lakes. The model also shows a reasonably good agreement between calculated and measured groundwater head elevations or depths to phreatic surfaces in many other points. The following major types of calculation-measurement differences can be noted: Differences in groundwater level amplitudes due to transpiration processes. Differences in absolute mean groundwater head, due to differences between borehole casing levels and the interpolated DEM. Differences in absolute mean head elevations, due to local errors in hydraulic conductivity values

  2. Design and implementation of the control system for the new console of TRIGA-3-Salazar Reactor

    International Nuclear Information System (INIS)

    Gonzalez M, J.L.

    1994-01-01

    TRIGA-3-Salazar Reactor was set in operation in 1968 and the aging of its components has cause the increasing in the maintenance. In the presence of this, it becomes necessary to replace the reactor console using new technologies, considering the incorporation of a personal computer. The aim of this work is the design and construction of the equipment interfaces as well as the digital computer program for the automation and control of the TRIGA-3-Salazar Reactor by means of a personal computer. (Author)

  3. On the major DYN3D developments for fast reactor design and transient analysis

    International Nuclear Information System (INIS)

    Merk, B.; Kliem, S.

    2013-01-01

    Due to the French project ASTRID, the European CP-ESFR project, and the MYRRHA/FASTEF project, the research work on fast reactors has got a new push in Europe. Additionally to this European projects a strong project is growing in Russia based on the lead cooled fast reactor design BREST. Following this trend, the Institute of Resource Ecology at the Helmholtz-Zentrum Dresden-Rossendorf has decided to start several projects dedicated to fast reactor technology, among them the extension of the well validated LWR core simulator DYN3D. The new developments, first validation results, and the next strategic steps for the adaption of the code for the improved simulation of fast reactor cores are presented. (orig.)

  4. On the major DYN3D developments for fast reactor design and transient analysis

    Energy Technology Data Exchange (ETDEWEB)

    Merk, B.; Kliem, S. [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Reactor Safety Div.

    2013-07-01

    Due to the French project ASTRID, the European CP-ESFR project, and the MYRRHA/FASTEF project, the research work on fast reactors has got a new push in Europe. Additionally to this European projects a strong project is growing in Russia based on the lead cooled fast reactor design BREST. Following this trend, the Institute of Resource Ecology at the Helmholtz-Zentrum Dresden-Rossendorf has decided to start several projects dedicated to fast reactor technology, among them the extension of the well validated LWR core simulator DYN3D. The new developments, first validation results, and the next strategic steps for the adaption of the code for the improved simulation of fast reactor cores are presented. (orig.)

  5. Calculation of low-energy reactor neutrino spectra reactor for reactor neutrino experiments

    Energy Technology Data Exchange (ETDEWEB)

    Riyana, Eka Sapta; Suda, Shoya; Ishibashi, Kenji; Matsuura, Hideaki [Dept. of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Kyushu (Japan); Katakura, Junichi [Dept. of Nuclear System Safety Engineering, Nagaoka University of Technology, Nagaoka (Japan)

    2016-06-15

    Nuclear reactors produce a great number of antielectron neutrinos mainly from beta-decay chains of fission products. Such neutrinos have energies mostly in MeV range. We are interested in neutrinos in a region of keV, since they may take part in special weak interactions. We calculate reactor antineutrino spectra especially in the low energy region. In this work we present neutrino spectrum from a typical pressurized water reactor (PWR) reactor core. To calculate neutrino spectra, we need information about all generated nuclides that emit neutrinos. They are mainly fission fragments, reaction products and trans-uranium nuclides that undergo negative beta decay. Information in relation to trans-uranium nuclide compositions and its evolution in time (burn-up process) were provided by a reactor code MVP-BURN. We used typical PWR parameter input for MVP-BURN code and assumed the reactor to be operated continuously for 1 year (12 months) in a steady thermal power (3.4 GWth). The PWR has three fuel compositions of 2.0, 3.5 and 4.1 wt% {sup 235}U contents. For preliminary calculation we adopted a standard burn-up chain model provided by MVP-BURN. The chain model treated 21 heavy nuclides and 50 fission products. The MVB-BURN code utilized JENDL 3.3 as nuclear data library. We confirm that the antielectron neutrino flux in the low energy region increases with burn-up of nuclear fuel. The antielectron-neutrino spectrum in low energy region is influenced by beta emitter nuclides with low Q value in beta decay (e.g. {sup 241}Pu) which is influenced by burp-up level: Low energy antielectron-neutrino spectra or emission rates increase when beta emitters with low Q value in beta decay accumulate. Our result shows the flux of low energy reactor neutrinos increases with burn-up of nuclear fuel.

  6. RA reactor exploitation, task 3.08/01; Zadatak 3.08/01 - Eksploatacija reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    During 1963 the RA reactor was operated for 1852 hours at mean power of 5.7 MW (total power production was 10716 MWh). Reactor was used for irradiation according to the demand of 356 users, and 15 experiments. The reason for decreased operation in comparison with the previous year was repair of all the reactor equipment and decontamination of the heavy water system. This report contains detailed data about reactor power, reactivity changes and fuel burnup. Mean monthly usage of the reactor experimental channels as well as samples which were irradiated are part of this report.

  7. Operating reactors licensing actions summary. Vol. 3, No. 6

    International Nuclear Information System (INIS)

    1983-07-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  8. Study of seismic responses of Candu-3 reactor building using isolator bearings

    International Nuclear Information System (INIS)

    Biswas, J.K.

    1992-01-01

    Seismic isolator bearings are known to increase reliability, reduce cost and increase the potential sitings for nuclear power plants located in regions of high seismicity. High seismic activities in Canada occur mainly in the western coast, the Grand Banks and regions of Quebec along the St. Lawrence river. In Canada, nuclear power plants are located in Ontario, Quebec and New Brunswick where the seismicity levels are low to moderate. Consequently, seismic isolator bearings have not been used in the existing nuclear power plants in Canada. The present paper examines the effect of using seismic isolator bearings in the design for the new CANDU3 which would be suitable for regions having high seismicity. The CANDU3 Nuclear Power Plant is rated at 450 MW of net output power and is a smaller version of its predecessor CANDU6 successfully operating in Canada and abroad. The design of CANDU3 is being developed by AECL CANDU. Advanced technologies for design, construction and plant operation have been utilized. During the conceptual development of the CANDU3 design, various design options including the use of isolator bearings were considered. The present paper presents an overview of seismic isolation technology and summarizes the analytical work for predicting the seismic behavior of the CANDU3 reactor building. A lumped-parameter dynamic model for the reactor building is used for the analysis. The characteristics of the bearings are utilized in the analysis work. The time-history modal analysis has been used to compute the seismic responses. Seismic responses of the reactor building with and without isolator bearings are compared. The isolator bearings are found to reduce the accelerations of the reactor building. As a result, a lower level of seismic qualification for components and systems would be required. The use of these bearings however increases rigid body seismic displacements of the structure requiring special considerations in the layout and interfaces for

  9. Applications for fueling of Forsmark-3 and Oskarshamn III

    International Nuclear Information System (INIS)

    1984-01-01

    The method for handling and final disposal of spent nuclear fuel outlined in the report KBS-3 has been found acceptable in relation to conventional and radiation safety. The main institutions agree on this, IAEA and other international institutions deem the method over-safe. The KBS-3 study has left some problems unsolved. Further research projects have been identified. (Aa)

  10. TU Electric reactor physics model verification: Power reactor benchmark

    International Nuclear Information System (INIS)

    Willingham, C.E.; Killgore, M.R.

    1988-01-01

    Power reactor benchmark calculations using the advanced code package CASMO-3/SIMULATE-3 have been performed for six cycles of Prairie Island Unit 1. The reload fuel designs for the selected cycles included gadolinia as a burnable absorber, natural uranium axial blankets and increased water-to-fuel ratio. The calculated results for both startup reactor physics tests (boron endpoints, control rod worths, and isothermal temperature coefficients) and full power depletion results were compared to measured plant data. These comparisons show that the TU Electric reactor physics models accurately predict important measured parameters for power reactors

  11. Reactor Dosimetry Applications Using RAPTOR-M3G:. a New Parallel 3-D Radiation Transport Code

    Science.gov (United States)

    Longoni, Gianluca; Anderson, Stanwood L.

    2009-08-01

    The numerical solution of the Linearized Boltzmann Equation (LBE) via the Discrete Ordinates method (SN) requires extensive computational resources for large 3-D neutron and gamma transport applications due to the concurrent discretization of the angular, spatial, and energy domains. This paper will discuss the development RAPTOR-M3G (RApid Parallel Transport Of Radiation - Multiple 3D Geometries), a new 3-D parallel radiation transport code, and its application to the calculation of ex-vessel neutron dosimetry responses in the cavity of a commercial 2-loop Pressurized Water Reactor (PWR). RAPTOR-M3G is based domain decomposition algorithms, where the spatial and angular domains are allocated and processed on multi-processor computer architectures. As compared to traditional single-processor applications, this approach reduces the computational load as well as the memory requirement per processor, yielding an efficient solution methodology for large 3-D problems. Measured neutron dosimetry responses in the reactor cavity air gap will be compared to the RAPTOR-M3G predictions. This paper is organized as follows: Section 1 discusses the RAPTOR-M3G methodology; Section 2 describes the 2-loop PWR model and the numerical results obtained. Section 3 addresses the parallel performance of the code, and Section 4 concludes this paper with final remarks and future work.

  12. Research on intelligent monitor for 3D power distribution of reactor core

    International Nuclear Information System (INIS)

    Xia, Hong; Li, Bin; Liu, Jianxin

    2014-01-01

    Highlights: • Core power distribution of ex-core measurement system has been reconstructed. • Building up an artificial intelligence model for 3-D core power distribution. • Error of the experiments has been reduced to 0.76%. • Methods for improving the accuracy of the model have been obtained. - Abstract: A real-time monitor for 3D reactor power distribution is critical for nuclear safety and high efficiency of NPP’s operation as well as for optimizing the control system, especially when the nuclear power plant (NPP) works at a certain power level or it works in load following operation. This paper was based on analyzing the monitor for 3D reactor power distribution technologies used in modern NPPs. Furthermore, considering the latest research outcomes, the paper proposed a method based on using an ex-core neutron detector system and a neural network to set up a real time monitor system for reactor’s 3D power distribution supervision. The results of the experiments performed on a reactor simulation machine illustrated that the new monitor system worked very well for a certain burn-up range during the fuel cycle. In addition, this new model could reduce the errors associated with the fitting of the distribution effectively, and several optimization methods were also obtained to improve the accuracy of the simulation model

  13. Effect of 3-D moderator flow configurations on the reactivity of CANDU nuclear reactors

    International Nuclear Information System (INIS)

    Zadeh, Foad Mehdi; Etienne, Stephane; Chambon, Richard; Marleau, Guy; Teyssedou, Alberto

    2017-01-01

    Highlights: • 3-D CFD simulations of CANDU-6 moderator flows are presented. • A thermal-hydraulic code using thermal physical fluid properties is used. • The numerical approach and convergence is validated against available data. • Flow configurations are correlated using Richardson’s number. • The interaction between moderator temperatures with reactivity is determined. - Abstract: The reactivity of nuclear reactors can be affected by thermal conditions prevailing within the moderator. In CANDU reactors, the moderator and the coolant are mechanically separated but not necessarily thermally isolated. Hence, any variation of moderator flow properties may change the reactivity. Until now, nuclear reactor calculations have been performed by assuming uniform moderator flow temperature distribution. However, CFD simulations have predicted large time dependent flow fluctuations taking place inside the calandria, which can bring about local temperature variations that can exceed 50 °C. This paper presents robust CANDU 3-D CFD moderator simulations coupled to neutronic calculations. The proposed methodology makes it possible to study not only different moderator flow configurations but also their effects on the reactor reactivity coefficient.

  14. G2 and G3 reactors design; Description des reacteurs G2 et G3

    Energy Technology Data Exchange (ETDEWEB)

    Herreng,; Ertaud,; Pasquet, [Societe Alsacienne de Constructions Mecaniques (France)

    1958-07-01

    'FRANCE ATOME' Manufacturers Party has been entrusted with the G2 and G3 reactors engineering by the french A.E.C., for the first-five-year french project. Although these reactors are essentially plutonium generators, everyone has been linked with a power station which is supposed to supply with 40 MW, 'Electricite de France' has taken the liability upon itself. The reactor core includes most of G1 reactor parts (central gap excluded): horizontal channels, graphite parallelepipedic bricks stacking, steel thermal shield. The cooling is provided with CO{sub 2} under a 15 atmospheres pressure. This pressure is kept steady in a press-stressed concrete packing-case which is a cylinder horizontally shaped. Steel strips tightened encircle the concrete cylinder; itself protected by sole-plates. The cylinder bottom has brought about unusual problems which have been solved by the choice of an hemispheric shape. Packing-case tightness is provided by a 30 mm iron-plate connected with the inner wall of concrete. One of the reactor's special characteristics is the possibility of loading and unloading while operating. On loading side, barrel locks, each weighting 50 tons, allow new cans, at a pressure of 15 atmospheres, to pass. The cans process almost in a steady way through the channel, and finally drop down through bent spouts, then through spiral toboggans into a new lock. The cooling CO{sub 2} flow is provided with 3 turbo-bellows, these are actuated by average pressure-steam, obtained from exchangers. Every reactor supplies 4 exchangers which have been very difficult to build and to set up. The secondary cycle is standard and contains 3 stages (pressure 10,3: 2 and 0,5 kg/cm{sup 2}). Steam can be condensed in the event of a group turbo-generator stopping, with no modifion for the normal operating conditions of the reactor. Auxiliary circuits have to assure the continuous purifying of cooling CO{sub 2}, its storage and drain. 49 boron carbide rods are used to control the

  15. Groundwater flow modelling of periods with periglacial and glacial climate conditions - Forsmark

    International Nuclear Information System (INIS)

    Vidstrand, Patrik; Follin, Sven; Zugec, Nada

    2010-12-01

    As a part of the license application for a final repository for spent nuclear fuel at Forsmark, the Swedish Nuclear Fuel and Waste Management Company (SKB) has undertaken a series of groundwater flow modelling studies. These represent time periods with different hydraulic conditions and the simulations carried out contribute to the overall evaluation of the repository design and long-term radiological safety. The groundwater flow modelling study reported here comprises a coupled thermal-hydraulic-chemical (T-H-C) analysis of periods with periglacial and glacial climate conditions. Hydraulic-mechanical (H-M) issues are also handled but no coupled flow modelling is done. The objective of the report is to provide bounding hydrogeological estimates at different stages during glaciation and deglaciation of a glacial cycle for subsequent use in safety assessment applications within SKB's project SR-Site. Three cases with different climate conditions are analysed here: (i) Temperate case, (ii) Glacial case without permafrost, and (iii) Glacial case with permafrost. The glacial periods are transient and encompass approximately 19,000 years. The simulation results comprise residual fluid pressures, Darcy fluxes, and water salinities, as well as advective transport performance measures obtained by particle tracking such as flow path lengths, travel times and flow-related transport resistances. The modelling is accompanied by a sensitivity study that addresses the impact of the following matters: the direction of the ice sheet advance, the speed of the ice sheet margin, the bedrock hydraulic and transport properties, the temperature at the ice-subsurface interface close to the ice sheet margin, and the initial hydrochemical conditions

  16. Groundwater flow modelling of periods with periglacial and glacial climate conditions - Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Vidstrand, Patrik (TerraSolve AB, Floda (Sweden)); Follin, Sven (SF GeoLogic AB, Taeby (Sweden)); Zugec, Nada (Bergab, Stockholm (Sweden))

    2010-12-15

    As a part of the license application for a final repository for spent nuclear fuel at Forsmark, the Swedish Nuclear Fuel and Waste Management Company (SKB) has undertaken a series of groundwater flow modelling studies. These represent time periods with different hydraulic conditions and the simulations carried out contribute to the overall evaluation of the repository design and long-term radiological safety. The groundwater flow modelling study reported here comprises a coupled thermal-hydraulic-chemical (T-H-C) analysis of periods with periglacial and glacial climate conditions. Hydraulic-mechanical (H-M) issues are also handled but no coupled flow modelling is done. The objective of the report is to provide bounding hydrogeological estimates at different stages during glaciation and deglaciation of a glacial cycle for subsequent use in safety assessment applications within SKB's project SR-Site. Three cases with different climate conditions are analysed here: (i) Temperate case, (ii) Glacial case without permafrost, and (iii) Glacial case with permafrost. The glacial periods are transient and encompass approximately 19,000 years. The simulation results comprise residual fluid pressures, Darcy fluxes, and water salinities, as well as advective transport performance measures obtained by particle tracking such as flow path lengths, travel times and flow-related transport resistances. The modelling is accompanied by a sensitivity study that addresses the impact of the following matters: the direction of the ice sheet advance, the speed of the ice sheet margin, the bedrock hydraulic and transport properties, the temperature at the ice-subsurface interface close to the ice sheet margin, and the initial hydrochemical conditions.

  17. 3. International conference on catalysis in membrane reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    The 3. International Conference on Catalysis in Membrane Reactors, Copenhagen, Denmark, is a continuation of the previous conferences held in Villeurbanne 1994 and Moscow 1996 and will deal with the rapid developments taking place within membranes with emphasis on membrane catalysis. The approx. 80 contributions in form of plenary lectures and posters discuss hydrogen production, methane reforming into syngas, selectivity and specificity of various membranes etc. The conference is organised by the Danish Catalytic Society under the Danish Society for Chemical Engineering. (EG)

  18. Thermal-hydraulic modelling of the SAFARI-1 research reactor using RELAP/SCDAPSIM/MOD3.4

    International Nuclear Information System (INIS)

    Sekhri, Abdelkrim; Graham, Andy; D'Arcy, Alan; Oliver, Melissa

    2008-01-01

    The SAFARI-1 reactor is a tank-in-pool MTR type research reactor operated at a nominal core power of 20 MW. It operates exclusively in the single phase liquid water regime with nominal water and fuel temperatures not exceeding 100 deg. C. RELAP/SCDAPSIM/MOD3.4 is a Best Estimate Code for light water reactors as well as for low pressure transients, as part of the code validation was done against low pressure facilities and research reactor experimental data. The code was used to simulate SAFARI-1 in normal and abnormal operation and validated against the experimental data in the plant and was used extensively in the upgrading of the Safety Analysis Report (SAR) of the reactor. The focus of the following study is the safety analysis of the SAFARI-1 research reactor and describes the thermal hydraulic modelling and analysis approach. Particular emphasis is placed on the modelling detail, the application of the no-boiling rule and predicting the Onset of Nucleate Boiling and Departure from Nucleate Boiling under Loss of Flow conditions. Such an event leads the reactor to switch to a natural convection regime which is an adequate mode to maintain the clad and fuel temperature within the safety margin. It is shown that the RELAP/SCDAPSIM/MOD3.4 model can provide accurate predictions as long as the clad temperature remains below the onset of nucleate boiling temperature and the DNB ratio is greater than 2. The results are very encouraging and the model is shown to be appropriate for the analysis of SAFARI-1 research reactor. (authors)

  19. Dealing with the current permissibility application for constructing a spent fuel DGR in Sweden. SKB's license applications for a spent fuel repository

    International Nuclear Information System (INIS)

    Olsson, Olle

    2014-01-01

    The nuclear power utilities in Sweden were in 1976 obliged to demonstrate a safe method for final disposal of spent fuel in order to start operation of new reactors. This initiated a comprehensive research, development and demonstration programme and the development of the KBS-method for final disposal. A new Nuclear Activities Act in 1984 gave the reactor owners full technical and financial responsibility for the waste. They gave in turn SKB the responsibility for all nuclear waste management. Reprocessing was no longer required and direct disposal of the spent fuel has, since then, been the main alternative. Alternative methods for final disposal have been evaluated and compared to the KBS-3-method but it has remained the preferred alternative. A comprehensive research, development and demonstration programme to strengthen the scientific basis and to refine the KBS-3-method has been operated by SKB since then. The site selection process for the final repository for spent nuclear fuel was initiated in 1992. The work included general siting studies at the national and the municipal level and in 2002, SKB initiated site investigations for siting of a final repository on two sites: the Simpevarp and Laxemar areas and the Forsmark area. At the same time, the work on preparing license applications to construct and operate an encapsulation plant and a final repository for spent fuel was started. In June 2009, SKB announced Forsmark as the selected site for the final repository. This paper reviews the applicable legislation and describes the license application, the licensing review and the preparations for implementation

  20. Application of Raptor-M3G to reactor dosimetry problems on massively parallel architectures - 026

    International Nuclear Information System (INIS)

    Longoni, G.

    2010-01-01

    The solution of complex 3-D radiation transport problems requires significant resources both in terms of computation time and memory availability. Therefore, parallel algorithms and multi-processor architectures are required to solve efficiently large 3-D radiation transport problems. This paper presents the application of RAPTOR-M3G (Rapid Parallel Transport Of Radiation - Multiple 3D Geometries) to reactor dosimetry problems. RAPTOR-M3G is a newly developed parallel computer code designed to solve the discrete ordinates (SN) equations on multi-processor computer architectures. This paper presents the results for a reactor dosimetry problem using a 3-D model of a commercial 2-loop pressurized water reactor (PWR). The accuracy and performance of RAPTOR-M3G will be analyzed and the numerical results obtained from the calculation will be compared directly to measurements of the neutron field in the reactor cavity air gap. The parallel performance of RAPTOR-M3G on massively parallel architectures, where the number of computing nodes is in the order of hundreds, will be analyzed up to four hundred processors. The performance results will be presented based on two supercomputing architectures: the POPLE supercomputer operated by the Pittsburgh Supercomputing Center and the Westinghouse computer cluster. The Westinghouse computer cluster is equipped with a standard Ethernet network connection and an InfiniBand R interconnects capable of a bandwidth in excess of 20 GBit/sec. Therefore, the impact of the network architecture on RAPTOR-M3G performance will be analyzed as well. (authors)

  1. Site investigation SFR. Reprocessing of reflection seismic profiles 5b and 8, Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Juhlin, Christopher; Zhang, Fengjiao (Uppsala Univ., Dept. of Earth Sciences (Sweden))

    2010-12-15

    Reflection seismic profiles 5b and 8 in the northern Forsmark area have been reprocessed with the aim of improving the images in the uppermost 500 metres in the SFR area. The main conclusion is that a new reflection (B10) has been identified that may extend below the SFR site. This reflection was not clearly observed in the previous processing. The reflection strikes approximately N25E and dips at about 35 degrees to the southeast. This orientation is similar to the set B group identified earlier /Juhlin and Palm 2005/. Note that the dip of the reflection is uncertain. On shot gathers it appears to dip at a slightly shallower angle while on the stacked sections it appears to dip at a greater angle. This discrepancy is probably due to the crooked nature of the profiles. However, reflections are clearly observed in shot gathers and its presence below SFR is highly probable. Two new reflections were also identified further north along profile 5b (A11 and A12). These dip to the south-southeast, but would be found at a depth of 1-2 km below SFR if they extend to below the site. There are also signs of a 3rd reflection with similar orientation to the set A group identified earlier, A13, but its existence is very speculative. This reflector would intersect the surface within the SFR area. South of the Singoe deformation zone on profile 5b, another new reflection has been found, N1. The orientation of this reflection is speculative since it is not clearly seen on profile 8. It has been modelled as dipping to the north at about 35 degrees and projects to the surface south of the main SFR area. In addition, the orientation of reflection B7 has been revised as has the lateral extent of A1. Most importantly, A1 is now interpreted not to extend to the surface and not cross the Singoe deformation zone

  2. The design of a fuel element for the RA-3 reactor (Ezeiza Atomic Center)

    International Nuclear Information System (INIS)

    Agueda, Horacio C.; Estevez, Esteban; Gerding, Jose R.; Markiewicz, Mario E.

    2003-01-01

    Some features of the mechanical design of the low enrichment fuel element for the RA-3 reactor are described, with emphasis in those aspects of the original design that have been modified considering the experience acquired in the design of other fuel elements. The proposed modification is based fundamentally on the replacement of all welded joints by screwed joints, which facilitates the manufacture of the fuel element, avoiding the distortions produced by the welds used at present and contributing to the fulfillment of the foreseen tolerances. A basic characteristic of this design is a careful manufacture of the fuel element's structural components in order to assure an assembling of the fuel element that fulfills the tolerances intrinsically required. The fuel is designed for the RA-3 reactor and uses U 3 O 8 or U 3 Si 2 as carrying phase of the fissile material with an enrichment of 19.70% of 235 U. The design verification was performed by analytical and numerical methods, and is supported by testing of materials in laboratory, hydrodynamics tests and performance evaluations of the fuel elements in the RA-3 reactor. (author)

  3. Technical report on implementation of reactor internal 3D modeling and visual database system

    International Nuclear Information System (INIS)

    Kim, Yeun Seung; Eom, Young Sam; Lee, Suk Hee; Ryu, Seung Hyun

    1996-06-01

    In this report was described a prototype of reactor internal 3D modeling and VDB system for NSSS design quality improvement. For improving NSSS design quality several cases of the nuclear developed nation's integrated computer aided engineering system, such as Mitsubishi's NUWINGS (Japan), AECL's CANDID (Canada) and Duke Power's PASCE (USA) were studied. On the basis of these studies the strategy for NSSS design improvement system was extracted and detail work scope was implemented as follows : 3D modelling of the reactor internals were implemented by using the parametric solid modeler, a prototype system of design document computerization and database was suggested, and walk-through simulation integrated with 3D modeling and VDB was accomplished. Major effects of NSSS design quality improvement system by using 3D modeling and VDB are the plant design optimization by simulation, improving the reliability through the single design database system and engineering cost reduction by improving productivity and efficiency. For applying the VDB to full scope of NSSS system design, 3D modelings of reactor coolant system and nuclear fuel assembly and fuel rod were attached as appendix. 2 tabs., 31 figs., 7 refs. (Author) .new

  4. Technical report on implementation of reactor internal 3D modeling and visual database system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yeun Seung; Eom, Young Sam; Lee, Suk Hee; Ryu, Seung Hyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-06-01

    In this report was described a prototype of reactor internal 3D modeling and VDB system for NSSS design quality improvement. For improving NSSS design quality several cases of the nuclear developed nation`s integrated computer aided engineering system, such as Mitsubishi`s NUWINGS (Japan), AECL`s CANDID (Canada) and Duke Power`s PASCE (USA) were studied. On the basis of these studies the strategy for NSSS design improvement system was extracted and detail work scope was implemented as follows : 3D modelling of the reactor internals were implemented by using the parametric solid modeler, a prototype system of design document computerization and database was suggested, and walk-through simulation integrated with 3D modeling and VDB was accomplished. Major effects of NSSS design quality improvement system by using 3D modeling and VDB are the plant design optimization by simulation, improving the reliability through the single design database system and engineering cost reduction by improving productivity and efficiency. For applying the VDB to full scope of NSSS system design, 3D modelings of reactor coolant system and nuclear fuel assembly and fuel rod were attached as appendix. 2 tabs., 31 figs., 7 refs. (Author) .new.

  5. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

  6. RELAP5-3D Code for Supercritical-Pressure Light-Water-Cooled Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Riemke, Richard Allan; Davis, Cliff Bybee; Schultz, Richard Raphael

    2003-04-01

    The RELAP5-3D computer program has been improved for analysis of supercritical-pressure, light-water-cooled reactors. Several code modifications were implemented to correct code execution failures. Changes were made to the steam table generation, steam table interpolation, metastable states, interfacial heat transfer coefficients, and transport properties (viscosity and thermal conductivity). The code modifications now allow the code to run slow transients above the critical pressure as well as blowdown transients (modified Edwards pipe and modified existing pressurized water reactor model) that pass near the critical point.

  7. Development of a 3-D flow analysis computer program for integral reactor

    International Nuclear Information System (INIS)

    Youn, H. Y.; Lee, K. H.; Kim, H. K.; Whang, Y. D.; Kim, H. C.

    2003-01-01

    A 3-D computational fluid dynamics program TASS-3D is being developed for the flow analysis of primary coolant system consists of complex geometries such as SMART. A pre/post processor also is being developed to reduce the pre/post processing works such as a computational grid generation, set-up the analysis conditions and analysis of the calculated results. TASS-3D solver employs a non-orthogonal coordinate system and FVM based on the non-staggered grid system. The program includes the various models to simulate the physical phenomena expected to be occurred in the integral reactor and will be coupled with core dynamics code, core T/H code and the secondary system code modules. Currently, the application of TASS-3D is limited to the single phase of liquid, but the code will be further developed including 2-phase phenomena expected for the normal operation and the various transients of the integrator reactor in the next stage

  8. Research reactors in Argentina

    International Nuclear Information System (INIS)

    Carlos Ruben Calabrese

    1999-01-01

    Argentine Nuclear Development started in early fifties. In 1957, it was decided to built the first a research reactor. RA-1 reactor (120 kw, today licensed to work at 40 kW) started operation in January 1958. Originally RA-1 was an Argonaut (American design) reactor. In early sixties, the RA-1 core was changed. Fuel rods (20% enrichment) was introduced instead the old Argonaut core design. For that reason, a critical facility named RA-0 was built. After that, the RA-3 project started, to build a multipurpose 5 MW nuclear reactor MTR pool type, to produce radioisotopes and research. For that reason and to define the characteristics of the RA-3 core, another critical facility was built, RA-2. Initially RA-3 was a 90 % enriched fuel reactor, and started operation in 1967. When Atucha I NPP project started, a German design Power Reactor, a small homogeneous reactor was donated by the German Government to Argentina (1969). This was RA-4 reactor (20% enrichment, 1W). In 1982, RA-6 pool reactor achieved criticality. This is a 500 kW reactor with 90% enriched MTR fuel elements. In 1990, RA-3 started to operate fueled by 20% enriched fuel. In 1997, the RA-8 (multipurpose critical facility located at Pilcaniyeu) started to operate. RA-3 reactor is the most important CNEA reactor for Argentine Research Reactors development. It is the first in a succession of Argentine MTR reactors built by CNEA (and INVAP SE ) in Argentina and other countries: RA-6 (500 kW, Bariloche-Argentina), RP-10 (10MW, Peru), NUR (500 kW, Algeria), MPR (22 MW, Egypt). The experience of Argentinian industry permits to compete with foreign developed countries as supplier of research reactors. Today, CNEA has six research reactors whose activities have a range from education and promotion of nuclear activity, to radioisotope production. For more than forty years, Argentine Research Reactors are working. The experience of Argentine is important, and argentine firms are able to compete in the design and

  9. Hydrogen production using Rhodopseudomonas palustris WP 3-5 with hydrogen fermentation reactor effluent

    International Nuclear Information System (INIS)

    Chi-Mei Lee; Kuo-Tsang Hung

    2006-01-01

    The possibility of utilizing the dark hydrogen fermentation stage effluents for photo hydrogen production using purple non-sulfur bacteria should be elucidated. In the previous experiments, Rhodopseudomonas palustris WP3-5 was proven to efficiently produce hydrogen from the effluent of hydrogen fermentation reactors. The highest hydrogen production rate was obtained at a HRT value of 48 h when feeding a 5 fold effluent dilution from anaerobic hydrogen fermentation. Besides, hydrogen production occurred only when the NH 4 + concentration was below 17 mg-NH 4 + /l. Therefore, for successful fermentation effluent utilization, the most important things were to decrease the optimal HRT, increase the optimal substrate concentration and increase the tolerable ammonia concentration. In this study, a lab-scale serial photo-bioreactor was constructed. The reactor overall hydrogen production efficiency with synthetic wastewater exhibiting an organic acid profile identical to that of anaerobic hydrogen fermentation reactor effluent and with effluent from two anaerobic hydrogen fermentation reactors was evaluated. (authors)

  10. Research reactor core conversion guidebook. V. 3: Analytical verification (Appendices G and H)

    International Nuclear Information System (INIS)

    1992-04-01

    Volume 3 consists of Appendix G which contains detailed results of a safety-related benchmark problem for an idealized reactor and Appendix H which contains detailed comparisons of calculated and measured data for actual cores with moderately enriched uranium and low enriched uranium fuels. The results of the benchmark calculations in Appendix G are summarized in Chapter 7 of Volume 1 and the results of the comparisons between calculations and measurements are summarized in Chapter 8 of Volume 1. Both the approaches described in these appendices are very useful in ensuring that the calculational methods employed in the preparation of a Safety Report are accurate. As a first step, it is recommended that reactor operators/physicists use their own methods and codes to first calculate the benchmark problem, and then compare the results of calculations with measurements in their own reactor or in one of the reactors for which measured data is available in Appendix H. (author). Refs, figs and tabs

  11. The ARIES-III D-3He tokamak reactor

    International Nuclear Information System (INIS)

    Bathke, C.G.; Werley, K.A.; Miller, R.L.; Krakowski, R.A.; Santarius, J.F.

    1992-01-01

    The multi-institutional ARIES study has generated a conceptual design of another tokamak fusion reactor in a series that varies the assumed advances in technology and physics. The ARIES-III design uses a D- 3 He fuel cycle and requires advances in technology and physics for economical attractiveness. The optimal design was characterized through systems analyses for eventual conceptual engineering design. In this paper, results from the systems analysis are summarized, and a comparison with the high-field, D-T fueled ARIES-I is included

  12. Annealing of the BR3 reactor pressure vessel

    International Nuclear Information System (INIS)

    Fabry, A.; Motte, F.; Stiennon, G.; Debrue, J.; Gubel, P.; Van de Velde, J.; Minsart, G.; Van Asbroeck, P.

    1985-01-01

    The pressure vessel of the Belgian BR-3 plant, a small (11 MWe) PWR presently used for fuel testing programs and operated since 1962, was annealed during March, 1984. The anneal was performed under wet conditions for 168 hours at 650 0 F with core removal and within plant design margins justification for the anneal, summary of plant characteristics, description of materials sampling, summary of reactor physics and dosimetry, development of embrittlement trend curves, hypothesized pressurized and overcooling thermal shock accidents, and conclusions are provided in detail

  13. RB Research nuclear reactor RB reactor, Annual report for 2000

    International Nuclear Information System (INIS)

    Milosevic, M.

    2000-12-01

    Report on RB reactor operation during 2000 contains 3 parts. Part one contains a brief description of reactor operation and reactor components, relevant dosimetry data and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level-meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization with a comprehensive list of publications resulting from experiments done at the RB reactor. It contains data about reactor operation during previous 14 years, i.e. from 1986 - 2000

  14. Gas turbine installations in nuclear power plants in Sweden

    International Nuclear Information System (INIS)

    Sevestedt, Lars

    1986-01-01

    At each of the four nuclear power stations in Sweden (Ringhals, Forsmark, Oskarshamn, Barsebaeck) gas turbine generating sets have been installed. These units are normally used for peak load operation dictated of grid and System requirements but they are also connected to supply the electrical auxiliary load of the nuclear plant as reserve power sources. The gas turbines have automatic start capability under certain abnormal conditions (such as reactor trips, low frequency grid etc) but they can also be started manually from several different locations. Starting time is approximately 2- 3 minutes from start up to full load. (author)

  15. Gas turbine installations in nuclear power plants in Sweden

    Energy Technology Data Exchange (ETDEWEB)

    Sevestedt, Lars [Electrical Equipment and Gas Turbines, Swedish State Power Board, Ringhals Nuclear Power Plant, S-430 22 Vaeroebacka (Sweden)

    1986-02-15

    At each of the four nuclear power stations in Sweden (Ringhals, Forsmark, Oskarshamn, Barsebaeck) gas turbine generating sets have been installed. These units are normally used for peak load operation dictated of grid and System requirements but they are also connected to supply the electrical auxiliary load of the nuclear plant as reserve power sources. The gas turbines have automatic start capability under certain abnormal conditions (such as reactor trips, low frequency grid etc) but they can also be started manually from several different locations. Starting time is approximately 2- 3 minutes from start up to full load. (author)

  16. Reactor science and technology: operation and control of reactors

    International Nuclear Information System (INIS)

    Qiu Junlong

    1994-01-01

    This article is a collection of short reports on reactor operation and research in China in 1991. The operation of and research activities linked with the Heavy Water Research Reactor, Swimming Pool Reactor and Miniature Neutron Source Reactor are briefly surveyed. A number of papers then follow on the developing strategies in Chinese fast breeder reactor technology including the conceptual design of an experimental fast reactor (FFR), theoretical studies of FFR thermo-hydraulics and a design for an immersed sodium flowmeter. Reactor physics studies cover a range of topics including several related to work on zero power reactors. The section on reactor safety analysis is concerned largely with the assessment of established, and the presentation of new, computer codes for use in PWR safety calculations. Experimental and theoretical studies of fuels and reactor materials for FBRs, PWRs, BWRs and fusion reactors are described. A final miscellaneous section covers Mo-Tc isotope production in the swimming pool reactor, convective heat transfer in tubes and diffusion of tritium through plastic/aluminium composite films and Li 2 SiO 3 . (UK)

  17. KBS-3H Complementary studies, 2008-2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-10-15

    KBS-3H is a joint project between Svensk Kaernbraenslehantering AB (SKB) in Sweden and Posiva Oy in Finland. The main goal during the project phase Complementary studies of horizontal emplacement KBS-3H 2008-2010 was to develop KBS-3H to such a state that a decision to go ahead with full-scale testing and demonstration could be made. The KBS-3H design is a variant of the KBS-3 method and an alternative to the KBS-3V design. In KBS-3H multiple canisters containing spent nuclear fuel are emplaced in parallel, 100-300 m long, horizontal deposition drifts at a depth of about 400-500 m in the bedrock whereas the KBS-3V design calls for vertical emplacement of the canisters in individual deposition holes. Further development and evaluation of the main KBS-3H design alternatives developed in earlier work, DAWE (Drainage, Artificial Watering and air Evacuation) and STC (Semi Tight Compartments) (Autio el al. 2007) has now enabled a well-founded KBS-3H reference design selection, DAWE has been selected. Regarding long-term safety; bentonite-metal interactions have been in focus and studies have given a good basis for material selection for the Supercontainer, plugs and other supporting structures and titanium is selected. The selections and evaluations made during this project phase will be used in the safety evaluations planned for Forsmark and Olkiluoto in the upcoming project phase. KBS-3H specific production lines have been outlined and layout adaptations for both Forsmark and Olkiluoto have been developed. Full-scale tests of system components have also been carried out with good results; the full-scale compartment plug test shows the ability to install a plug that separates drift compartments hydraulically.

  18. KBS-3H complementary studies, 2008-2010

    International Nuclear Information System (INIS)

    2013-07-01

    KBS-3H is a joint project between Svensk Kaernbraenslehantering AB (SKB) in Sweden and Posiva Oy in Finland. The main goal during the project phase Complementary studies of horizontal emplacement KBS-3H 2008-2010 was to develop KBS-3H to such a state that a decision to go ahead with full-scale testing and demonstration could be made. The KBS-3H design is a variant of the KBS-3 method and an alternative to the KBS-3V design. In KBS-3H multiple canisters containing spent nuclear fuel are emplaced in parallel, 100-300 m long, horizontal deposition drifts at a depth of about 400-500 m in the bedrock whereas the KBS- 3V design calls for vertical emplacement of the canisters in individual deposition holes. Further development and evaluation of the main KBS-3H design alternatives developed in earlier work, DAWE (Drainage, Artificial Watering and air Evacuation) and STC (Semi Tight Compartments) (Autio el al. 2007) has now enabled a well-founded KBS-3H reference design selection, DAWE has been selected. Regarding long-term safety; bentonite-metal interactions have been in focus and studies have given a good basis for material selection for the Supercontainer, plugs and other supporting structures and titanium is selected. The selections and evaluations made during this project phase will be used in the safety evaluations planned for Forsmark and Olkiluoto in the upcoming project phase. KBS-3H specific production lines have been outlined and layout adaptations for both Forsmark and Olkiluoto have been developed. Full-scale tests of system components have also been carried out with good results; the full-scale compartment plug test shows the ability to install a plug that separates drift compartments hydraulically. (orig.)

  19. KBS-3H Complementary studies, 2008-2010

    International Nuclear Information System (INIS)

    2012-10-01

    KBS-3H is a joint project between Svensk Kaernbraenslehantering AB (SKB) in Sweden and Posiva Oy in Finland. The main goal during the project phase Complementary studies of horizontal emplacement KBS-3H 2008-2010 was to develop KBS-3H to such a state that a decision to go ahead with full-scale testing and demonstration could be made. The KBS-3H design is a variant of the KBS-3 method and an alternative to the KBS-3V design. In KBS-3H multiple canisters containing spent nuclear fuel are emplaced in parallel, 100-300 m long, horizontal deposition drifts at a depth of about 400-500 m in the bedrock whereas the KBS-3V design calls for vertical emplacement of the canisters in individual deposition holes. Further development and evaluation of the main KBS-3H design alternatives developed in earlier work, DAWE (Drainage, Artificial Watering and air Evacuation) and STC (Semi Tight Compartments) (Autio el al. 2007) has now enabled a well-founded KBS-3H reference design selection, DAWE has been selected. Regarding long-term safety; bentonite-metal interactions have been in focus and studies have given a good basis for material selection for the Supercontainer, plugs and other supporting structures and titanium is selected. The selections and evaluations made during this project phase will be used in the safety evaluations planned for Forsmark and Olkiluoto in the upcoming project phase. KBS-3H specific production lines have been outlined and layout adaptations for both Forsmark and Olkiluoto have been developed. Full-scale tests of system components have also been carried out with good results; the full-scale compartment plug test shows the ability to install a plug that separates drift compartments hydraulically

  20. Master-3.0: multi-purpose analyzer for static and transient effects of reactors

    International Nuclear Information System (INIS)

    Cho, Byung Oh; Joo, Han Gyu; Cho, Jin Young; Song, Jae Seung; Zee, Sung Quun

    2002-03-01

    MASTER-3.0 (Multi-purpose Analyzer for Static and Transient Effects of Reactors) is a nuclear design code based on the multi-group diffusion theory to calculate the steady-state and transient pressurized water reactor core in a 3-dimensional Cartesian or hexagonal geometry. Its neutronics model solves the space-time dependent neutron diffusion equations with NIM (Nodal Integration Method), NEM (Nodal Expansion Method), AFEN (Analytic Function Expansion Nodal Method)/NEM Hybrid Method, NNEM (Non-linear Nodal Expansion Method) or NANM (Non-linear Analytic Nodal Method) for a Cartesian geometry and with NTPEN (Non-linear Triangle-based Polynomial Expansion Nodal Method), AFEN (Analytic Function Expansion Nodal)/NEM Hybrid Method or NLFM (Non-linear Local Fine-Mesh Method) for a hexagonal one. Coarse mesh rebalancing, Krylov Subspace method, energy group restriction/prolongation method and asymptotic extrapolation method are implemented to accelerate the convergence of iteration process. MASTER-3.0 performs microscopic depletion calculations using microscopic cross sections provided by CASMO-3 or HELIOS and also has the reconstruction capability of pin information by use of MSS-IAS (Method of Successive Smoothing with Improved Analytic Solution). For the thermal-hydraulic calculation, fuel temperature table or COBRA3-C/P or MATRA model can be used selectively. In addition, MASTER-3.0 is designed to cover various PWRs including SMART as well as WH- and CE-type reactors, providing all data required in their design procedures

  1. 3 D flow computations under a reactor vessel closure head

    International Nuclear Information System (INIS)

    Daubert, O.; Bonnin, O.; Hofmann, F.; Hecker, M.

    1995-12-01

    The flow under a vessel cover of a pressurised water reactor is investigated by using several computations and a physical model. The case presented here is turbulent, isothermal and incompressible. Computations are made with N3S code using a k-epsilon model. Comparisons between numerical and experimental results are on the whole satisfying. Some local improvements are expected either with more sophisticated turbulence models or with mesh refinements automatically computed by using the adaptive meshing technique which has been just implemented in N3S for 3D cases. (authors). 6 refs., 7 figs

  2. Review on the seismic safety of JRR-3 according to the revised regulatory code on seismic design for nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, Tetsuya; Araki, Masaaki; Ohba, Toshinobu; Torii, Yoshiya [Japan Atomic Energy Agency, Tokai, Ibaraki (Japan); Takeuchi, Masaki [Nuclear Safety Commission (Japan)

    2012-03-15

    JRR-3(Japan Research Reactor No.3) with the thermal power of 20MW is a light water moderated and cooled, swimming pool type research reactor. JRR-3 has been operated without major troubles. This paper presents about review on the seismic safety of JRR-3 according to the revised regulatory code on seismic design for nuclear reactors. In addition, some topics concerning damages in JRR-3 due to the Great East Japan Earthquake are presented. (author)

  3. Chemical characteristics of surface systems in the Forsmark area. Visualisation and statistical evaluation of data from surface water, precipitation, shallow groundwater, and regolith

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-02-15

    The Swedish Nuclear Fuel and Waste management Co (SKB) initiated site investigations for a deep repository for spent nuclear fuel at two different sites in Sweden, Forsmark and Oskarshamn, in 2002. This report evaluates the results from chemical investigations of the surface system in the Forsmark area during the period November 2002 - March 2005. The evaluation includes data from surface waters (lakes, streams and the sea), precipitation, shallow groundwater and regolith (till, soil, peat, sediments and biota) in the area. Results from surface waters are not presented in this report since these were treated in a recently published report. The main focus of the study is to visualize the vast amount of data collected hitherto in the site investigations, and to give a chemical characterisation of the investigated media at the site. The results will be used to support the site descriptive models, which in turn are used for safety assessment studies and for the environmental impact assessment. The data used consist of water chemical composition in lakes, streams, coastal sites, and in precipitation, predominantly sampled on a monthly basis, and in groundwater from soil tubes and wells, sampled up to four times per year. Moreover, regolith data includes information on the chemical composition of till, soil, sediment and vegetation samples from the area. The characterisations include all measured chemical parameters, i.e. major and minor constituents, trace elements, nutrients, isotopes and radio nuclides, as well as field measured parameters. The evaluation of data from each medium has been divided into the following parts: Characterisation of individual sampling sites, and comparisons within and among sampling sites as well as comparisons with local, regional and national reference data; Analysis of time trends and seasonal variation (for shallow groundwater); Exploration of relationships among the various chemical parameters. For all investigated parameters, the

  4. Repository for spent nuclear fuel. Plant description layout D - Forsmark

    International Nuclear Information System (INIS)

    2010-07-01

    This document describes the final repository for spent nuclear fuel, SFK, which is located at Forsmark, in Oesthammar. The bedrock at the site is part of a so-called tectonic lens, in which the rock composition is relatively homogeneous and less deformed than outside the lens. The bedrock consists mainly of granite with high quartz content and good thermal conductivity. The central parts above ground are grouped in an operations area, located at the Soederviken on the south side of the intake duct for cooling water for nuclear power plant. Operating area is divided into an internal, secured portion, where the canisters of fuel are handled and there are links to the underground part, and a outer part, where the buffer, backfill and sealing used in the repository's barriers are produced. The above-ground part of the plant and also include storage of excavated rock, ventilation stations, and supplies of bentonite. The underground portion consists of a central area and a storage area. Caverns of the central area contain features for the underground operation. It communicates with the internal operating range above ground via a spiral ramp and several shafts. The ramp used to transport capsules of spent fuel and other heavy or bulky transport. The shafts are used to transport rock, buffer, backfill and staff, as well as for ventilation. The largest part of the space below ground is the repository where the canisters with the spent fuel are disposed. The capsules are deposited in vertical holes in the tunnels. When the deposit in a tunnel is complete, the tunnel is re-filled. The two main activities underground is rock work and disposal work, which are conducted separately from each other. Rock works covers all steps required to excavate tunnels and drill deposition holes, as well as to make temporary installations in the tunnels. To the landfill works count, besides the deposit of the capsule, the placement of the bentonite buffer in the deposition hole and backfilling

  5. Neutron flux calculations for the Rossendorf research reactor in (hex)- and (hex,z)-geometry using SNAP-3D

    International Nuclear Information System (INIS)

    Koch, R.; Findeisen, A.

    1986-04-01

    The multigroup neutron diffusion theory code SNAP-3D has been used to perform time independent neutron flux and power calculations of the 10 MW Rossendorf research reactor of the type WWR-SM. The report describes these calculations, as well as the actual reactor configuration, some details of the code SNAP-3D, and two- and three-dimensional reactor models. For evaluating the calculations some flux values and control rod worths have been compared with those of measurements. (author)

  6. Thermal fluid dynamics study of nuclear advanced reactors of high temperature using RELAP5-3D

    International Nuclear Information System (INIS)

    Scari, Maria Elizabeth

    2017-01-01

    Fourth Generation nuclear reactors (GEN-IV) are being designed with special features such as intrinsic safety, reduction of isotopic inventory and use of fuel in proliferation-resistant cycles. Therefore, the investigation and evaluation of operational and safety aspects of the GEN-IV reactors have been the subject of numerous studies by the international community and also in Brazil. In 2008, in Brazil, was created the National Institute of Science and Technology of Innovative Nuclear Reactors, focusing on studies of projects and systems of new generation reactors, which included GEN-IV reactors as well as advanced PWR (Pressurized Water Reactor) concepts. The Department of Nuclear Engineering of the Federal University of Minas Gerais (DEN-UFMG) is a partner of this Institute, having started studies on the GEN-IV reactors in the year 2007. Therefore, in order to add knowledge to these studies, in this work, three projects of advanced reactors were considered to verify the simulation capability of the thermo-hydraulic RELAP5-3D code for these systems, either in stationary operation or in transient situations. The addition of new working fluids such as ammonia, carbon dioxide, helium, hydrogen, various types of liquid salts, among them Flibe, lead, lithium-bismuth, lithium-lead, was a major breakthrough in this version of the code, allowing also the simulation of GEN-IV reactors. The modeling of the respective core of an HTTR (High Temperature Engineering Test Reactor), HTR-10 (High Temperature Test Module Reactor) and LS-VHTR (Liquid-Salt-Cooled Very-High-Temperature Reactor) were developed and verified in steady state comparing the values found through the calculations with reference data from other simulations, when it is possible. The first two reactors use helium gas as coolant and the LS-VHTR uses a mixture of 66% LiF and 34% of BeF 2 , the LiF-BeF 2 , also know as Flibe. All the studied reactors use enriched uranium as fuel, in form of TRISO (Tristructural

  7. 3D CFD for chemical transport profiles in a rotating disk CVD reactor

    Science.gov (United States)

    Han, Jong-Hyun; Yoon, Do-Young

    2010-06-01

    The RDCVD (Rotating Disk Chemical Vapor Deposition) technique is an appropriate method for uniform deposition of grains, such as compound semiconductior materials. The substrate temperature and rotation speed are the major factors, which determine the thickness uniformity of the deposited films. This paper investigates 3D CFD (3 Dimensional Computational Fluid Dynamics) simulation results of flow and heat transfer in a reactor of RDCVD using Fluent. In order to establish the reducibility of buoyancy effect on deposition quality, the chemical transport profile upon the disk heated is examined successfully in 3D domain for different rotating speeds. The resulting vortex flows due the simultaneous buoyance and centrifuge are discussed qualitatively in the 3D virtual system of a RDCVD reactor. 3D CFD is even more effective to describe the internal vortex flows due to the competitive inlet, buoyancy and centrifuge flows, which cannot be realized in the general 2D (2 Dimensional) CFD.[Figure not available: see fulltext.

  8. Development of a version of the reactor dynamics code DYN3D applicable for High Temperature Reactors; Entwicklung einer Version des Reaktordynamikcodes DYN3D fuer Hochtemperaturreaktoren. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Rohde, Ulrich; Apanasevich, Pavel; Baier, Silvio; Duerigen, Susan; Fridman, Emil; Grahn, Alexander; Kliem, Soeren; Merk, Bruno

    2012-07-15

    Based on the reactor dynamics code DYN3D for the simulation of transient processes in Light Water Reactors, a code version DYN3D-HTR for application to graphitemoderated, gas-cooled block-type high temperature reactors has been developed. This development comprises: - the methodical improvement of the 3D steady-state neutron flux calculation for the hexagonal geometry of the HTR fuel element blocks - the development of methods for the generation of homogenised cross section data taking into account the double heterogeneity of the fuel element block structure - the implementation of a 3D model for heat conduction and heat transport in the graphite matrix. The nodal method for neutron flux calculation based on SP3 transport approximation was extended to hexagonal fuel element geometry, where the hexagons are subdivided into triangles, thus the method had finally to be derived for triangular geometry. In triangular geometry, a subsequent subdivision of the hexagonal elements can be considered, and therefore, the effect of systematic mesh refinement can be studied. The algorithm was verified by comparison with Monte Carlo reference solutions, on the node-wise level, as well as also on the pin-wise level. New procedures were developed for the homogenization of the double-heterogeneous fuel element structures. One the one hand, the so-called Reactivity equivalent Physical Transformation (RPT), the two-step homogenization method based on 2D deterministic lattice calculations, was extended to cells with different temperatures of the materials. On the other hand, the progress in development of Monte Carlo methods for spectral calculations, in particular the development of the code SERPENT, opened a new, fully consistent 3D approach, where all details of the structures on fuel particle, fuel compact and fuel block level can be taken into account within one step. Moreover, a 3D heat conduction and heat transport model was integrated into DYN3D to be able to simulate radial

  9. Experimental and kinetic modeling study of 3-methylheptane in a jet-stirred reactor

    KAUST Repository

    Karsenty, Florent

    2012-08-16

    Improving the combustion of conventional and alternative fuels in practical applications requires the fundamental understanding of large hydrocarbon combustion chemistry. The focus of the present study is on a high-molecular-weight branched alkane, namely, 3-methylheptane, oxidized in a jet-stirred reactor. This fuel, along with 2-methylheptane, 2,5-dimethylhexane, and n-octane, are candidate surrogate components for conventional diesel fuels derived from petroleum, synthetic Fischer-Tropsch diesel and jet fuels derived from coal, natural gas, and/or biomass, and renewable diesel and jet fuels derived from the thermochemical treatment of bioderived fats and oils. This study presents new experimental results along with a low- and high-temperature chemical kinetic model for the oxidation of 3-methylheptane. The proposed model is validated against these new experimental data from a jet-stirred reactor operated at 10 atm, over the temperature range of 530-1220 K, and for equivalence ratios of 0.5, 1, and 2. Significant effort is placed on the understanding of the effects of methyl substitution on important combustion properties, such as fuel reactivity and species formation. It was found that 3-methylheptane reacts more slowly than 2-methylheptane at both low and high temperatures in the jet-stirred reactor. © 2012 American Chemical Society.

  10. Development of a 3D-Multigroup program to simulate anomalous diffusion phenomena in the nuclear reactors

    International Nuclear Information System (INIS)

    Maleki Moghaddam, Nader; Afarideh, Hossein; Espinosa-Paredes, Gilberto

    2015-01-01

    Highlights: • The new version of neutron diffusion equation for simulating anomalous diffusion is presented. • Application of fractional calculus in the nuclear reactor is revealed. • A 3D-Multigroup program is developed based on the fractional operators. • The super-diffusion and sub-diffusion phenomena are modeled in the nuclear reactors core. - Abstract: The diffusion process is categorized in three parts, normal diffusion, super-diffusion and sub-diffusion. The classical neutron diffusion equation is used to model normal diffusion. A new scheme of derivatives is required to model anomalous diffusion phenomena. The fractional space derivatives are employed to model anomalous diffusion processes where a plume of particles spreads at an inconsistent rate with the classical Brownian motion model. In the fractional diffusion equation, the fractional Laplacians are used; therefore the statistical jump length of neutrons is unrestricted. It is clear that the fractional Laplacians are capable to model the anomalous phenomena in nuclear reactors. We have developed a NFDE-3D (neutron fractional diffusion equation) as a core calculation code to model normal and anomalous diffusion phenomena. The NFDE-3D is validated against the LMW-LWR reactor. The results demonstrate that reactors exhibit complex behavior versus order of the fractional derivatives which depends on the competition between neutron absorption and super-diffusion phenomenon

  11. Study on effects of development of reactor constant in fast reactor analysis

    International Nuclear Information System (INIS)

    Chiba, Gou

    2002-12-01

    Evaluation was carried out about an effect of development of the new generation reactor constant system that substitutes for the JFS library in fast reactor analysis. Analyzed cores were ZPPR in JUPITER critical experiment and several power reactor cores that were designed in the feasibility study. In the JUPITER analysis, large effects, over 10%, were observed in sodium void reactivity and sample Doppler reactivity. The former resulted from several factors, while the latter was due to an accurate of a resonance interaction effect between Doppler sample and core fuel. In the previous study, the effect had been evaluated in power reactor cores. The effect included an effect of corrosion of weighting spectrum because JFS-3-J3.2, which had been made with the incorrect weighting spectrum, was used in the evaluation. In the present study, JFS-3-J3.2R, which had been made with the correct weighting spectrum, was used. It was confirmed that the effect of development of reactor constant in power reactor was not as large as that in critical assembly. (author)

  12. Simulation in 3 dimensions of a cycle 18 months for an BWR type reactor using the Nod3D program; Simulacion en 3 dimensiones de un ciclo de 18 meses para un reactor BWR usando el programa Nod3D

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez, N.; Alonso, G. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)]. E-mail: nhm@nuclear.inin.mx; Valle, E. del [IPN, ESFM, 07738 Mexico D.F. (Mexico)

    2004-07-01

    The development of own codes that you/they allow the simulation in 3 dimensions of the nucleus of a reactor and be of easy maintenance, without the consequent payment of expensive use licenses, it can be a factor that propitiates the technological independence. In the Department of Nuclear Engineering (DIN) of the Superior School of Physics and Mathematics (ESFM) of the National Polytechnic Institute (IPN) a denominated program Nod3D has been developed with the one that one can simulate the operation of a reactor BWR in 3 dimensions calculating the effective multiplication factor (kJJ3, as well as the distribution of the flow neutronic and of the axial and radial profiles of the power, inside a means of well-known characteristics solving the equations of diffusion of neutrons numerically in stationary state and geometry XYZ using the mathematical nodal method RTN0 (Raviart-Thomas-Nedelec of index zero). One of the limitations of the program Nod3D is that it doesn't allow to consider the burnt of the fuel in an independent way considering feedback, this makes it in an implicit way considering the effective sections in each step of burnt and these sections are obtained of the code Core Master LEND. However even given this limitation, the results obtained in the simulation of a cycle of typical operation of a reactor of the type BWR are similar to those reported by the code Core Master LENDS. The results of the keJ - that were obtained with the program Nod3D they were compared with the results of the code Core Master LEND, presenting a difference smaller than 0.2% (200 pcm), and in the case of the axial profile of power, the maxim differs it was of 2.5%. (Author)

  13. Synthesis of the IRSN report related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor. Referral of the Permanent Group of Experts for nuclear reactors (GPR), examination of probabilistic level-2 safety studies (EPS 2) and severe accidents (AG) of the Flamanville reactor nr 3. Opinion related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor (FA3). Electronuclear reactors - EDF - Flamanville 3 EPR reactor. Severe accidents and probabilistic level 2 studies

    International Nuclear Information System (INIS)

    2015-01-01

    This document gathers several documents. The first one recalls the main arrangements implemented on the FA3 EPR reactor regarding accidents with core fusion, reports the analysis made by the IRSN about the sizing of these arrangements to reach a controlled status of the installation after a severe accident, regarding the probabilistic level-2 safety assessment, regarding the radiological impact of a severe accident on the population and on the environment, regarding those aimed at facing a total and long duration loss of electric power sources and cold sources, and about the situation of the reactor with respect to WENRA positions on severe accidents for new reactors. The second document is a letter sent by the ASN to the Permanent Group of Experts for nuclear reactors (GPR) to address probabilistic level-2 safety studies (EPS2) and severe accidents for the Flamanville 3 reactor. The third one reports the opinion of the GPR on these both issues and proposes a set of recommendations. The next document is a letter sent by the ASN to the Flamanville 3 project manager at EDF which recalls the related objectives, the ASN opinion on the implemented arrangements for severe accidents (de-pressurization of the primary circuit, management of hydrogen-related risks, corium recovery and cooling outside the vessel, limitation of vapour explosion risks outside the vessel, heat evacuation system, containment enclosure, management of the risk of a return to criticality), to face a total and long duration loss of electricity sources and cold sources, and other aspects addressed in the IRSN analysis. Requests and remarks formulated by the ASN are provided in an appendix to this last document

  14. Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor

    International Nuclear Information System (INIS)

    Fiorina, Carlo; Hursin, Mathieu; Pautz, Andreas

    2017-01-01

    Highlights: • Development and verification of an SP 3 solver based on OpenFOAM. • Integration into the GeN-Foam multi-physics platform. • Application of the new GeN-Foam SP 3 solver to the CROCUS reactor. - Abstract: The Laboratory for Reactor Physics and Systems Behaviour at the PSI and at the EPFL has been developing since 2013 a multi-physics platform for coupled reactor analysis named GeN-Foam. The developed tool includes a solver for the eigenvalue and transient solution of multi-group neutron diffusion equations. Although frequently used in reactor analysis, the diffusion theory shows some limitations for core configurations involving strong anisotropies, which is the case for the CROCUS research reactor at the EPFL. The use of an SP 3 approximation to neutron transport can often lead to visible improvements in a code predictive capabilities, especially for one-directional anisotropies, with acceptable added computational cost vs diffusion. Following some modelling issues for the CROCUS reactor, and in order to improve the GeN-Foam modelling capabilities, the GeN-Foam diffusion solver has been extended to allow for SP 3 analyses. The present paper describes such extension and a preliminary verification using a mini-core PWR benchmark. The newly developed solver is then applied to the analysis of the CROCUS experimental reactor and results are compared to Monte Carlo calculations, as well as to the results of the diffusion solver.

  15. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  16. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.

    1992-07-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  17. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing

  18. Tritium production, management and its impact on safety for a D-3He fusion reactor

    International Nuclear Information System (INIS)

    Sze, D.K.; Herring, S.; Sawan, M.

    1991-11-01

    About three percent of the fusion energy produced by a D- 3 He reactor is in the form of neutrons. Those neutrons are generated by D-D and D-T reactions, with the tritium produced by the D-D fusion. The neutrons will react with structural steel, deuterium, 3 He and shielding material to produce tritium. About half of the tritium generated by the D-D reaction will not burn in the plasma and will exit as a part of the plasma exhaust. Thus, there is enough tritium produced in a D- 3 He reactor and careful management will be required. The tritium produced in the shield and plasma can be managed with an acceptable effect on cost and safety. 3 refs., 2 figs., 3 tabs

  19. Forsmark site investigation. Investigation of marine and lacustrine sediment in lakes. Field data 2003

    Energy Technology Data Exchange (ETDEWEB)

    Hedenstroem, Anna [SGU, Uppsala (Sweden)

    2003-04-01

    The aim of this activity is to describe the aerial and stratigraphical distribution of marine and lacustrine sediment i.e. sediment overlaying the glacial till and/or bedrock surface, in lakes in the Forsmark area. The investigation is carried out within areas where mapping of unconsolidated Quaternary deposits is presently carried out. Since small and shallow lakes cover a large part of the region, this work will give important information on the distribution and stratigraphy of sedimentary deposits not included in the regular mapping of unconsolidated Quaternary deposits within the site investigation programme. Samples were also collected for laboratory analyses of grain size distribution, mineralogical composition as well as the total content of C, N and S and calcium carbonate. The analyses will be carried out on selected samples of representative sedimentary units in order to characterise the chemical and physical properties of the unconsolidated deposits. The analytical data will be useful for the hydrogeological modelling and for models of the Quaternary evolution of the area. The mineralogical analyses of clay may provide information on the origin of the clay particles. One stratigraphic sequence from Lake Eckarfjaerden will be stored for later analyses, e.g. pollen analysis. This report includes field data from spring 2003. Together, the field data and the forthcoming results from the laboratory analyses will form the basis for construction of stratigraphical profiles to be presented in a following report in the fall 2003.

  20. Forsmark site investigation. Investigation of marine and lacustrine sediment in lakes. Field data 2003

    International Nuclear Information System (INIS)

    Hedenstroem, Anna

    2003-04-01

    The aim of this activity is to describe the aerial and stratigraphical distribution of marine and lacustrine sediment i.e. sediment overlaying the glacial till and/or bedrock surface, in lakes in the Forsmark area. The investigation is carried out within areas where mapping of unconsolidated Quaternary deposits is presently carried out. Since small and shallow lakes cover a large part of the region, this work will give important information on the distribution and stratigraphy of sedimentary deposits not included in the regular mapping of unconsolidated Quaternary deposits within the site investigation programme. Samples were also collected for laboratory analyses of grain size distribution, mineralogical composition as well as the total content of C, N and S and calcium carbonate. The analyses will be carried out on selected samples of representative sedimentary units in order to characterise the chemical and physical properties of the unconsolidated deposits. The analytical data will be useful for the hydrogeological modelling and for models of the Quaternary evolution of the area. The mineralogical analyses of clay may provide information on the origin of the clay particles. One stratigraphic sequence from Lake Eckarfjaerden will be stored for later analyses, e.g. pollen analysis. This report includes field data from spring 2003. Together, the field data and the forthcoming results from the laboratory analyses will form the basis for construction of stratigraphical profiles to be presented in a following report in the fall 2003

  1. Advanced reactors transition fiscal year 1995 multi-year program plan WBS 7.3

    International Nuclear Information System (INIS)

    Loika, E.F.

    1994-01-01

    This document describes in detail the work to be accomplished in FY-1995 and the out years for the Advanced Reactors Transition (WBS 7.3). This document describes specific milestones and funding profiles. Based upon the Fiscal Year 1995 Multi-Year Program Plan, DOE will provide authorization to perform the work outlined in the FY 1995 MYPP. Following direction given by the US Department of Energy (DOE) on December 15, 1993, Advanced Reactors Transition (ART), previously known as Advanced Reactors, will provide the planning and perform the necessary activities for placing the Fast Flux Test Facility (FFTF) in a radiologically and industrially safe shutdown condition. The DOE goal is to accomplish the shutdown in approximately five years. The Advanced Reactors Transition Multi-Year Program Plan, and the supporting documents; i.e., the FFTF Shutdown Program Plan and the FFTF Shutdown Project Resource Loaded Schedule (RLS), are defined for the life of the Program. During the transition period to achieve the Shutdown end-state, the facilities and systems will continue to be maintained in a safe and environmentally sound condition. Additionally, facilities that were associated with the Office of Nuclear Energy (NE) Programs, and are no longer required to support the Liquid Metal Reactor Program will be deactivated and transferred to an alternate sponsor or the Decontamination and Decommissioning (D and D) Program for final disposition, as appropriate

  2. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

  3. Reactor Physics Programme

    International Nuclear Information System (INIS)

    De Raedt, C.

    2000-01-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

  4. Characteristics of UV-MicroO3 Reactor and Its Application to Microcystins Degradation during Surface Water Treatment

    Directory of Open Access Journals (Sweden)

    Guangcan Zhu

    2015-01-01

    Full Text Available The UV-ozone (UV-O3 process is not widely applied in wastewater and potable water treatment partly for the relatively high cost since complicated UV radiation and ozone generating systems are utilized. The UV-microozone (UV-microO3, a new advanced process that can solve the abovementioned problems, was introduced in this study. The effects of air flux, air pressure, and air humidity on generation and concentration of O3 in UV-microO3 reactor were investigated. The utilization of this UV-microO3 reactor in microcystins (MCs degradation was also carried out. Experimental results indicated that the optimum air flux in the reactor equipped with 37 mm diameter quartz tube was determined to be 18∼25 L/h for efficient O3 generation. The air pressure and humidity in UV-microO3 reactor should be low enough in order to get optimum O3 output. Moreover, microcystin-RR, YR, and LR (MC-RR, MC-YR, and MC-LR could be degraded effectively by UV-microO3 process. The degradation of different MCs was characterized by first-order reaction kinetics. The pseudofirst-order kinetic constants for MC-RR, MC-YR, and MC-LR degradation were 0.0093, 0.0215, and 0.0286 min−1, respectively. Glucose had no influence on MC degradation through UV-microO3. The UV-microO3 process is hence recommended as a suitable advanced treatment method for dissolved MCs degradation.

  5. Nuclear reactor (1960)

    International Nuclear Information System (INIS)

    Maillard, M.L.

    1960-01-01

    The first French plutonium-making reactors G1, G2 and G3 built at Marcoule research center are linked to a power plant. The G1 electrical output does not offset the energy needed for operating this reactor. On the contrary, reactors G2 and G3 will each generate a net power of 25 to 30 MW, which will go into the EDF grid. This power is relatively small, but the information obtained from operation is great and will be helpful for starting up the power reactor EDF1, EDF2 and EDF3. The paper describes how, previous to any starting-up operation, the tests performed, especially those concerned with the power plant and the pressure vessel, have helped to bring the commissioning date closer. (author) [fr

  6. Construction of Research Reactors for Gen 3 and Gen 4 Reactors Development

    International Nuclear Information System (INIS)

    Behar, Christophe

    2014-01-01

    Christophe Behar, Director of the Nuclear Energy Division at CEA, detailed the different kind of research reactors and the issues in term of investment, use, side application such as the medical isotopes production

  7. Simulation of a reactor FBR with hexagonal-Z geometry using the code PARCS 3.1

    International Nuclear Information System (INIS)

    Reyes F, M. C.; Del Valle G, E.; Filio L, C.

    2013-10-01

    The nuclear reactor core type FBR (Fast Breeder Reactor) was modeled in three dimensions of hexagonal-Z geometry using the code PARCS (Purdue Advanced Reactor Core Simulator) version 3.1 developed by Purdue University researchers. To carry out the modeling of the mentioned reactor was taken the corresponding information to one of the described benchmarks in the document NEACRP-L-330 (3-D Neutron Transport Benchmarks, 1991); fundamentally the corresponding to the geometric data and the cross sections. Being a quick reactor of breeding, known as the Knk-II, for which are considered 4 energy groups without dispersions up. The reactor core is formed by prismatic elements of hexagonal transversal cut where part of them only corresponds to nuclear fuel assemblies. This has four reflector rings and 6 identical control elements that together with the active part of the core is configured with 8 different types of elements.With the extracted information of the mentioned document the entrance file was prepared for PARCS 3.1 only considering a sixth part of the core due to the symmetry that presents their configuration. The NEACRP-L-330 shows a wide range of results reported by those who collaborated in its elaboration using different solution techniques that go from the Monte Carlo method to the approaches S 2 and P 1 . Of all the results were selected those obtained with the code HEXNOD, to which were carried out a comparison of the effective multiplication factor, being smaller differences to the 300 pcm, for three different scenarios: a) with the control bars extracted totally, b) with the semi-inserted control bars and c) with the control bars inserted completely and two different axial meshes, a thick mesh with 14 slices and another fine with 38, that which implies that the results can be considered very similar among if same. Radial maps and axial profiles are included, as much of the power as of the neutrons flow. (Author)

  8. Operating experiences and utilization programmes of the BAEC 3 MW TRIGA Mark-II research reactor of Bangladesh

    International Nuclear Information System (INIS)

    Haque, M.M.; Soner, M.A.M.; Saha, P.K.; Salam, M.A.; Zulquarnain, M.A.

    2008-01-01

    The 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC) has been operating since September 14, 1986. The reactor is used for radioisotope production ( 131 I, 99m Tc, 46 Sc), various R and D activities, manpower training and education. The reactor has been operated successfully since its commissioning with the exception of a few reportable incidents. Of these, the decay tank leakage incident of 1997 is considered to be the most significant one. As a result of this incident, reactor operation at full power remained suspended for about 4 years. However, the reactor operation was continued during this period at a power level of 250 kW to cater the needs of various R and D groups, which required lower neutron flux for their experiments. This was made possible by establishing a temporary by pass connection across the decay tank using local technology. The reactor was made operational again at full power after successful replacement of the damaged decay tank in August 2001. At that time, several modifications of the reactor cooling system along with its associated structures were also implemented and then necessary testing and commissioning of the newly installed component/equipment were carried out. The other incident was the contamination of the Dry Central Thimble (DCT) that took place in March 2002 when a pyrex vial containing 50g of TeO 2 powder got melted inside the DCT. The vial was melted due to high heat generation on its surface while the reactor was operated for 8 hours at 3 MW for trial production of Iodine-131 ( 131 I). A Wet Central Thimble (WCT) was used to replace the damaged DCT in June 2002 such that the reactor operation could be resumed. The WCT was again replaced by a new DCT in June 2003 such that radioisotope production could be continued. The facility has so far been used to train up a total of 27 personnel including several foreign nationals to the level of Senior Reactor Operator (SRO) and Reactor Operator (RO). The

  9. Effect of fuel assembly when changing from AFA 2G to AFA 3G on seismic loads of reactor internal

    International Nuclear Information System (INIS)

    Liu Wenjin; Zeng Zhongxiu; Ye Xianhui; Wu Wanjun

    2013-01-01

    Nonlinear seismic model for reactor with fuel assemblies of AFA 2G and AFA 3G is established. Using ANSYS software, seismic nonlinear time -history analysis is completed and the effects on seismic loads of reactor system are obtained. The result shows that when the fuel assembly changing from AFA 2G to AFA 3G, it is necessary to reevaluate the fuel assembly itself, but not the reactor internal. (authors)

  10. FMDP Reactor Alternative Summary Report: Volume 3 - partially complete LWR alternative

    International Nuclear Information System (INIS)

    Greene, S.R.; Fisher, S.E.; Bevard, B.B.

    1996-09-01

    The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 3 of a four volume report summarizes the results of these analyses for the partially complete LWR (PCLWR) reactor based plutonium disposition alternative

  11. FMDP Reactor Alternative Summary Report: Volume 3 - partially complete LWR alternative

    Energy Technology Data Exchange (ETDEWEB)

    Greene, S.R.; Fisher, S.E.; Bevard, B.B. [and others

    1996-09-01

    The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 3 of a four volume report summarizes the results of these analyses for the partially complete LWR (PCLWR) reactor based plutonium disposition alternative.

  12. Modelling and thermal hydraulic analysis of the Angra-2 nuclear reactor using RELAP5-3D code

    International Nuclear Information System (INIS)

    González Mantecón, Javier

    2015-01-01

    The evaluation of Nuclear Power Plants (NPPs) performance during steady-state and accident conditions has been one of the main research subjects in the nuclear field. In order to simulate the behavior of water-cooled reactors, several complex thermal-hydraulic codes systems have been developed. Particularly, the RELAP5 code, developed by the Idaho National Laboratory, is a best-estimate thermal-hydraulic analysis tool and one of the most used in nuclear industry. The RELAP5-3D 3.0.0 code was used to develop a detailed model of Angra 2 nuclear reactor using reference data from the Final Safety Analysis Report. Angra 2 is the second Brazilian NPP, which began commercial operation in 2001. The plant is equipped with a Pressurized Water Reactor (PWR) type with 3771.0 MWt. Simulations of the reactor behavior during normal operation conditions and postulated accident conditions were performed. Results achieved in the reactor steady-state simulation were compared with nominal parameters of the NPP. These results proved to be in good agreement, with relative errors less than 1%. In the transient simulation, the obtained results were coherent and satisfactory. This study demonstrates that the RELAP5-3D model is capable to reproduce the thermal-hydraulic behavior of the Angra-2 PWR during diverse operation conditions and it can contribute for the process of the plant safety analysis. (author)

  13. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2009

    International Nuclear Information System (INIS)

    2014-02-01

    JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography, Irradiation for activation analyses, radioisotope (RI) productions, fission tracks, Irradiation test of reactor materials, etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT), Prompt gamma-ray analyses, Sensitivity measurement of radiation detectors, Experiment in the nuclear reactor training, Practice of Reactor operation, Irradiation for activation analyses, RI productions, fission tracks, etc. In the fiscal year 2009, The research reactor JRR-3 was operated 7 cycles (cycle operation : 26days/cycle) for utilization sharing of the facility. And JRR-4 was operated 6 cycles (daily operation : 24 days). The volume contains 138 activity reports, which are categorized into the fields of neutron scattering (11 subcategories), neutron radiography, prompt gamma-ray analyses, neutron activation analyses, RI productions, and others submitted by the users in JAEA and from other organizations. (author)

  14. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2005

    International Nuclear Information System (INIS)

    2007-03-01

    In the fiscal year 2005, The research reactor JRR-3 was operated 7 cycles (cycle operation : 26days/cycle) for utilization sharing of the facility. And JRR-4 was operated 37 cycles (daily operation : 137 days). JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography. Irradiation for activation analyses, radioisotope (RI) productions, fission tracks. Irradiation test of reactor materials etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT). Prompt gamma-ray analyses. Sensitivity measurement of radiation detectors. Experiment in the nuclear reactor training. Practice of Reactor operation. Irradiation for activation analyses, RI productions, fission tracks etc. The volume contains 100 activity reports, which are categorized into the fields of neutron scattering (9 subcategories), neutron radiography, neutron activation analyses, RI productions, prompt gamma-ray analyses, and others submitted by the users in JAEA and from other organizations. (author)

  15. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2006

    International Nuclear Information System (INIS)

    2009-01-01

    In the fiscal year 2006, the research reactor JRR-3 was operated 7 cycles (cycle operation: 26 days/cycle) for utilization sharing of the facility. And JRR-4 was operated 37 cycles (daily operation: 151 days). JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography, Irradiation for activation analyses, radioisotope (RI) productions, fission tracks, Irradiation test of reactor materials, etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT), Prompt gamma-ray analyses, Sensitivity measurement of radiation detectors, Experiment in the nuclear reactor training, Practice of Reactor operation, Irradiation for activation analyses, RI productions, fission tracks, etc. The volume contains 294 activity reports, which are categorized into the fields of neutron scattering (11 subcategories), neutron radiography, neutron activation analyses, RI productions, prompt gamma-ray analyses, and others submitted by the users in JAEA and from other organizations. (author)

  16. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-02-15

    JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography, Irradiation for activation analyses, radioisotope (RI) productions, fission tracks, Irradiation test of reactor materials, etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT), Prompt gamma-ray analyses, Sensitivity measurement of radiation detectors, Experiment in the nuclear reactor training, Practice of Reactor operation, Irradiation for activation analyses, RI productions, fission tracks, etc. In the fiscal year 2009, The research reactor JRR-3 was operated 7 cycles (cycle operation : 26days/cycle) for utilization sharing of the facility. And JRR-4 was operated 6 cycles (daily operation : 24 days). The volume contains 138 activity reports, which are categorized into the fields of neutron scattering (11 subcategories), neutron radiography, prompt gamma-ray analyses, neutron activation analyses, RI productions, and others submitted by the users in JAEA and from other organizations. (author)

  17. A 3D transport-based core analysis code for research reactors with unstructured geometry

    International Nuclear Information System (INIS)

    Zhang, Tengfei; Wu, Hongchun; Zheng, Youqi; Cao, Liangzhi; Li, Yunzhao

    2013-01-01

    Highlights: • A core analysis code package based on 3D neutron transport calculation in complex geometry is developed. • The fine considerations on flux mapping, control rod effects and isotope depletion are modeled. • The code is proved to be with high accuracy and capable of handling flexible operational cases for research reactors. - Abstract: As an effort to enhance the accuracy in simulating the operations of research reactors, a 3D transport core analysis code system named REFT was developed. HELIOS is employed due to the flexibility of describing complex geometry. A 3D triangular nodal S N method transport solver, DNTR, endows the package the capability of modeling cores with unstructured geometry assemblies. A series of dedicated methods were introduced to meet the requirements of research reactor simulations. Afterwards, to make it more user friendly, a graphical user interface was also developed for REFT. In order to validate the developed code system, the calculated results were compared with the experimental results. Both the numerical and experimental results are in close agreement with each other, with the relative errors of k eff being less than 0.5%. Results for depletion calculations were also verified by comparing them with the experimental data and acceptable consistency was observed in results

  18. Detecting long-range correlation with detrended fluctuation analysis: Application to BWR stability

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa-Paredes, Gilberto [Departamento de Ingenieria de Procesos e Hidraulica, Universidad Autonoma Metropolitana-Iztapalapa, Apartado Postal 55-534, Mexico, DF 09340 (Mexico)]. E-mail: gepe@xanum.uam.mx; Alvarez-Ramirez, Jose [Departamento de Ingenieria de Procesos e Hidraulica, Universidad Autonoma Metropolitana-Iztapalapa, Apartado Postal 55-534, Mexico, DF 09340 (Mexico); Vazquez, Alejandro [Departamento de Ingenieria de Procesos e Hidraulica, Universidad Autonoma Metropolitana-Iztapalapa, Apartado Postal 55-534, Mexico, DF 09340 (Mexico)

    2006-11-15

    The aim of this paper is to explore the application of detrended fluctuation analysis (DFA) to study boiling water reactor stability. DFA is a scaling method commonly used for detecting long-range correlations in non-stationary time series. This method is based on the random walk theory and was applied to neutronic power signal of Forsmark stability benchmark. Our results shows that the scaling properties breakdown during unstable oscillations.

  19. Detecting long-range correlation with detrended fluctuation analysis: Application to BWR stability

    International Nuclear Information System (INIS)

    Espinosa-Paredes, Gilberto; Alvarez-Ramirez, Jose; Vazquez, Alejandro

    2006-01-01

    The aim of this paper is to explore the application of detrended fluctuation analysis (DFA) to study boiling water reactor stability. DFA is a scaling method commonly used for detecting long-range correlations in non-stationary time series. This method is based on the random walk theory and was applied to neutronic power signal of Forsmark stability benchmark. Our results shows that the scaling properties breakdown during unstable oscillations

  20. Verification of using SABINE-3.1 code for calculations of radioactive inventory in reactor shield

    International Nuclear Information System (INIS)

    Moukhamadeev, R.; Suvorov, A.

    2000-01-01

    This report presents the results of calculations of radioactive inventory and doses of activation radiation for the International Benchmark Calculations of Radioactive Inventory for Fission Reactor Decommissioning, IAEA, and measurements of activation doses in shield of WWER-440 (Armenian NPP), using one-dimension modified code SABINE-3.1. For decommissioning of NPP it is very important to evaluate in correct manner radioactive inventory in reactor construction and shield materials. One-dimension code SABINE-3.1 (removing-diffusion method for neutron calculation) was modified to perform calculation of radioactive inventory in reactor shield materials and dose from activation photons behind them. These calculations are carried out on the base of nuclear constant system ABBN-78 and new library of activation data for a number of long-lived isotopes, prepared by authors on the base of [9], which present at shield materials as microimpurities and manage radiation situation under the decay more than 1 year. (Authors)