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Sample records for uljin nuclear site

  1. A plan for safety evaluation of tsunamis at the Uljin nuclear power plant site

    International Nuclear Information System (INIS)

    Lee, H. K.; Lee, D. S.

    1999-01-01

    The sites of many nuclear and thermal power plants are located along the coast line to obtain necessary cooling water. Therefore, they are vulnerable to coastal disasters like tsunamis. The safety evaluation on tsunamis of the site of Uljin nuclear power plants was performed with the maximum potential earthquake magnitude and related fault parameters in 1986. But according to the results of recent research, the possibility was suggested that the earthquake which has bigger magnitude than was expected is likely to happen in the seismic gaps near Akita, Japan. Therefore, a plan for safety evaluation of tsunamis at the Uljin nuclear power plants was laid out

  2. Prediction of evacuation time for emergency planning zone of Uljin nuclear site

    International Nuclear Information System (INIS)

    Jeon, In Young; Lee, Jai Ki

    2002-01-01

    The time for evacuation of residents in Emergency Planning Zone (EPZ) of Uljin nuclear site in case of a radiological emergency was estimated with traffic analysis. Evacuees were classified into 4 groups by considering population density, local jurisdictions, and whether they are residents or transients. The survey to investigate the behavioral characteristics of the residents was made for 200 households and included a hypothetical scenario explaining the accident situation and questions such as dwelling place, time demand for evacuation preparation, transportation means for evacuation, sheltering place, and evacuation direction. The microscopic traffic simulation model, CORSIM, was used to simulate the behavior of evacuating vehicles on networks. The results showed that the evacuation time required for total vehicles to move out from EPZ took longer in the daytime than at night in spite that the delay times at intersections were longer at night than in the daytime. This was analyzed due to the differences of the trip generation time distribution. To validate whether the CORSIM model can appropriately simulate the congested traffic phenomena assumable in case of emergency, a benchmark study was conducted at an intersection without an actuated traffic signal near Uljin site during the traffic peak-time in the morning. This study indicated that the predicted output by the CORSIM model was in good agreement with the observed data, satisfying the purpose of this study

  3. Emergency preparedness for the accidental release of radionuclides from the Uljin Nuclear Power Plant in Korea.

    Science.gov (United States)

    Park, Soon-Ung; Lee, In-Hye; Joo, Seung Jin; Ju, Jae-Won

    2017-12-01

    Site specific radionuclide dispersion databases were archived for the emergency response to the hypothetical releases of 137 Cs from the Uljin nuclear power plant in Korea. These databases were obtained with the horizontal resolution of 1.5 km in the local domain centered the power plant site by simulations of the Lagrangian Particle Dispersion Model (LPDM) with the Unified Model (UM)-Local Data Assimilation Prediction System (LDAPS). The Eulerian Dispersion Model-East Asia (EDM-EA) with the UM-Global Data Assimilation Prediction System (UM-GDAPS) meteorological models was used to get dispersion databases in the regional domain. The LPDM model was performed for a year with a 5-day interval yielding 72 synoptic time-scale cases in a year. For each case hourly mean near surface concentrations, hourly mean column integrated concentrations, hourly total depositions for 5 consecutive days were archived by the LPDM model in the local domain and by the EDM-EA model in the regional domain of Asia. Among 72 synoptic cases in a year the worst synoptic case that showed the highest mean surface concentration averaged for 5 days in the LPDM model domain was chosen to illustrate the emergency preparedness to the hypothetical accident at the site. The simulated results by the LPDM model with the 137 Cs emission rate of the Fukushima nuclear power plant accident for the first 5-day period were found to be able to provide prerequisite information for the emergency response to the early phase of the accident whereas those of the EDM-EA model could provide information required for the environmental impact assessment of the accident in the regional domain. The archived site-specific database of 72 synoptic cases in a year could have a great potential to be used as a prognostic information on the emergency preparedness for the early phase of accident. Copyright © 2017 Elsevier Ltd. All rights reserved.

  4. Faults simulation on reactor internals of Uljin 1 and 2 nuclear power plant

    International Nuclear Information System (INIS)

    Ryu, J. S.; Park, J. H.; Nam, H. Y.; Woo, J. S.; Kim, T. R.

    1999-01-01

    The dynamic characteristics analysis were performed for finite element model of Uljin 1 and 2 NPP reactor internals with artificial faults on the hold-down ring and the thermal shield. To prove the validity of the modelling, the fundamental beam and shell mode frequencies of core support barrel(CSB) in normal state are compared with those from the measurement results, which shows good agreement. According to the analysis results, the fundamental natural frequency of the CSB beam decreases by 5%, 18%, 54% and 92% for 10%, 20%, 50% and 80% partial faults of the hold-down ring respectively. And the fundamental shell natural frequency is within 5.3% for 20% partial faults, but decrease by 22% and 72% for 50% and 80% partial faults. For the faults of the thermal shield with the normal hold-down ring, frequency decreases of the higher shell modes are more than the beam modes and the 5th to 8th natural frequencies decrease by 5%, 9%, 13% and 20% for 25%, 50%, 75% and 100% partial faults respectively

  5. Generation IV nuclear energy systems: road map and concepts. 3. Measurement and Analysis of Conducted Noise at Main Control Room in Uljin NPP

    International Nuclear Information System (INIS)

    Goo, Cheol-Soo; Kim, Bok-Ryul; Cho, Won-Seo

    2001-01-01

    The utility has implemented digital technology into the design of the plant protection system in new nuclear power plants (NPPs) and also replaced existing analog instrumentation and control (I and C) systems with computer-based digital I and C systems as the analog systems become obsolete. Digital I and C systems, which provide more operating capabilities than analog systems, operate at conditions that are more vulnerable to EMI/RFI than existing analog systems. The purpose of the site survey is to get the actual electromagnetic measurement (EM) level in NPPs and to eliminate the need for plant-specific EM at the point of installation to demonstrate the sufficiency of equipment test levels. Actual electromagnetic environments in NPPs are major elements to decide the limit for the susceptibility of the installed equipment. The data obtained with standard methods are indispensable to make guidelines for an electromagnetic qualification test for the equipment to be installed in the NPP. We performed EM at the power ports of the Plant Control System (PCS) and the Core Protection Calculator (CPC) in Uljin to obtain the conducted noise level, which can be utilized to determine the electromagnetic environment test limit for the equipment qualification test. The continuous conducted noise and discontinuous transient or surge at the power ports of the PCS and the CPC installed at the no.3 main control room in the Uljin NPP were measured and analyzed. The measurements were continuously conducted for 2 weeks of the power-escalated phase with reactor power from 0% to full power. The measurements selected for the power leaders were the current and voltage of the power cables using a current and voltage (passive) probe, EMI test receiver, and notebook computer. The data were recorded in accordance with standard industry practices and procedures. The conducted noise current was measured over the frequency range of 30 Hz to 50 kHz, and the voltage was captured over the frequency

  6. Distribution of a pelagic tunicate, Salpa fusiformis in warm surface current of the eastern Korean waters and its impingement on cooling water intakes of Uljin nuclear power plant.

    Science.gov (United States)

    Chae, Jinho; Choi, Hyun Woo; Lee, Woo Jin; Kim, Dongsung; Lee, Jae Hac

    2008-07-01

    Impingement of a large amount of gelatinous plankton, Salpa fusiformis on the seawater intake system-screens in a nuclear power plant at Uljin was firstly recorded on 18th June 2003. Whole amount of the clogged animals was estimated were presumptively at 295 tons and the shortage of cooling seawater supply by the animal clogging caused 38% of decrease in generation capability of the power plant. Zooplankton collection with a multiple towing net during the day and at night from 5 to 6 June 2003 included various gelatinous zooplanktons known to be warm water species such as salps and siphonophores. Comparatively larger species, Salpa fusiformis occupied 25.4% in individual density among the gelatinous plankton and showed surface distribution in the depth shallower than thermocline, performing little diel vertical migration. Temperature, salinity and satellite data also showed warm surface current predominated over the southern coastal region near the power plant in June. The results suggested that warm surface current occasionally extended into the neritic region may transfer S. fusiformis, to the waters off the power plant. The environmental factors and their relation to ecobiology of the large quantity of salpa population that are being sucked into the intake channel of the power plant are discussed.

  7. Upgraded Steam Generator Lancing System for Uljin NPP no.2

    International Nuclear Information System (INIS)

    Kim, Seok Tae; Jeong, Woo Tae; Hong, Sung Yull

    2005-01-01

    KEPRI(Korea Electric Power Research Institute) has developed various types of steam generator lancing systems since 1998. In this paper, we introduce a new lancing system with new improvements from the previous steam generator lancing system for Uljin NPP #2(nuclear power plant) constructed by KEPRI. The previous lancing system is registered as KALANS R -II and was developed for System-80 type steam generators. The previous lancing system was applied to Uljin unit #3 and it lowered radiation exposure of operators in comparison to manually operated lancing systems. And it effectively removed sludge accumulated around kidney bean zone in the Uljin unit #3 steam generators. But the previous lancing system could only clean partially the steam generators of Uljin unit #4. This was because the rail of the previous lancing system interfered with a part of the steam generator. Therefore we developed a new lancing system that can solve the interference problem. This new lancing system was upgraded from the previous lancing system. Also, a new lancing system for System-80 S/G will be introduced in this paper

  8. Nuclear installations sites safety

    International Nuclear Information System (INIS)

    Barber, P.; Candes, P.; Duclos, P.; Doumenc, A.; Faure, J.; Hugon, J.; Mohammadioun, B.

    1988-11-01

    This report is divided into ten parts bearing: 1 Safety analysis procedures for Basis Nuclear Installations sites (BNI) in France 2 Site safety for BNI in France 3 Industrial and transport activities risks for BNI in France 4 Demographic characteristics near BNI sites in France 5 Meteorologic characteristics of BNI sites in France 6 Geological aspects near the BNI sites in France 7 Seismic studies for BNI sites in France 8 Hydrogeological aspects near BNI sites in France 9 Hydrological aspects near BNI sites in France 10 Ecological and radioecological studies of BNI sites in France [fr

  9. Nuclear waste repository siting

    International Nuclear Information System (INIS)

    Soloman, B.D.; Cameron, D.M.

    1987-01-01

    This paper discusses the geopolitics of nuclear waste disposal in the USA. Constitutional choice and social equity perspectives are used to argue for a more open and just repository siting program. The authors assert that every potential repository site inevitably contains geologic, environmental or other imperfections and that the political process is the correct one for determining sites selected

  10. Nuclear site selection studies

    International Nuclear Information System (INIS)

    Gharib, A.; Zohoorian Izadpanah, A.A.; Iranmanesh, H.

    2000-01-01

    It is of special importance, especially from the nuclear safety viewpoint, to select suitable sites for different nuclear structures with the considered future activities. Site selection sometimes involves high costs not necessarily for merely selecting of site but for some preliminary measures to be taken so as the site may have the necessary characteristics. The more suitable the natural characteristics of the site for the considered project, the more successful and efficient the project, the lower the project costs and the longer the project operation period. If so, the project will cause the growth of public culture and sustainable socioeconomic development. This paper is the result of the conclusion of numerous massive reports of this activity in the preliminary phase based on theories, practices and the related safety principles on this ground as well as the application of data and information of the past and a glance to the future. The conception of need for a site for medium structures and nuclear research projects and how to perform this process are presented step by step here with a scientific approach to its selection during the investigations. In this study, it is practically described how the site is selected, by determining and defining the characteristics of research and nuclear projects with medium structures and also its fitting to the optimum site. The discovered sites typically involve the best advantages in technical and economic aspects and no particular contrast with the concerned structures

  11. Siting nuclear power plants

    International Nuclear Information System (INIS)

    Yellin, J.; Joskow, P.L.

    1980-01-01

    The first edition of this journal is devoted to the policies and problems of siting nuclear power plants and the question of how far commercial reactors should be placed from urban areas. The article is divided into four major siting issues: policies, risk evaluation, accident consequences, and economic and physical constraints. One concern is how to treat currently operating reactors and those under construction that were established under less-stringent criteria if siting is to be used as a way to limit the consequences of accidents. Mehanical cost-benefit analyses are not as appropriate as the systematic use of empirical observations in assessing the values involved. Stricter siting rules are justified because (1) opposition because of safety is growing: (2) remote siting will make the industry more stable; (3) the conflict is eliminated between regulatory policies and the probability basis for nuclear insurance; and (4) joint ownership of utilities and power-pooling are increasing. 227 references, 7 tables

  12. Nuclear power plant siting

    International Nuclear Information System (INIS)

    Sulkiewicz, M.; Navratil, J.

    The construction of a nuclear power plant is conditioned on territorial requirements and is accompanied by the disturbance of the environment, land occupation, population migration, the emission of radioactive wastes, thermal pollution, etc. On the other hand, a nuclear power plant makes possible the introduction of district heating and increases the economic and civilization activity of the population. Due to the construction of a nuclear power plant the set limits of negative impacts must not be exceeded. The locality should be selected such as to reduce the unfavourable effects of the plant and to fully use its benefits. The decision on the siting of the nuclear power plant is preceded by the processing of a number of surveys and a wide range of documentation to which the given criteria are strictly applied. (B.H.)

  13. Nuclear power: Siting and safety

    International Nuclear Information System (INIS)

    Openshaw, S.

    1986-01-01

    By 2030, half, or even two-thirds, of all electricity may be generated by nuclear power. Major reactor accidents are still expected to be rare occurrences, but nuclear safety is largely a matter of faith. Terrorist attacks, sabotage, and human error could cause a significant accident. Reactor siting can offer an additional, design-independent margin of safety. Remote geographical sites for new plants would minimize health risks, protect the industry from negative changes in public opinion concerning nuclear energy, and improve long-term public acceptance of nuclear power. U.K. siting practices usually do not consider the contribution to safety that could be obtained from remote sites. This book discusses the present trends of siting policies of nuclear power and their design-independent margin of safety

  14. The development of the operational program for seismic monitoring system of Uljin Unit 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J.R.; Heo, T.Y.; Cho, B.H. [Korea Electric Power Research Institute, Taejeon (Korea, Republic of); Kang, T.G.; Kim, H.M.; Kim, Y.S.; Oh, S.M.; Kang, Y.S. [Korea Electric Power Data Network Co., Seoul (Korea, Republic of)

    1997-12-31

    Due to aging of the imported seismic monitoring system of Uljin of t 1 and 2 units it is difficult for this system to provide enough functions needed for the security of seismic safety and the evaluation of the earthquake data from the seismic instrumentation. For this reason, it is necessary to replace the seismic monitoring system of Uljin 1 and 2 units with a new system which has the localized and upgraded hardware and corresponding software. In the part of standardization of existing seismic monitoring system, furthermore, it is necessary to develop the seismic wave analysis system which incorporate newly developed software and can real-timely analyze the seismic wave. This report is the finial product of research project ``The development of the operational program for seismic monitoring system of Uljin Unit 1 and 2`` which have been performed from June 1996 to June 1997 by KEPRI and KDN. Main accomplishments - Review of regulatory criteria for seismic monitoring system -Analysis and upgrade of hardware system -Analysis and upgrade of software system - Development of seismic wave analysis system. (author). 17 refs., 49 figs., 6 tabs.

  15. Nuclear waste disposal site

    International Nuclear Information System (INIS)

    Mallory, C.W.; Watts, R.E.; Sanner, W.S. Jr.; Paladino, J.B.; Lilley, A.W.; Winston, S.J.; Stricklin, B.C.; Razor, J.E.

    1988-01-01

    This patent describes a disposal site for the disposal of toxic or radioactive waste, comprising: (a) a trench in the earth having a substantially flat bottom lined with a layer of solid, fluent, coarse, granular material having a high hydraulic conductivity for obstructing any capillary-type flow of ground water to the interior of the trench; (b) a non-rigid, radiation-blocking cap formed from a first layer of alluvium, a second layer of solid, fluent, coarse, granular material having a high hydraulic conductivity for blocking any capillary-type flow of water between the layer of alluvium and the rest of the cap, a layer of water-shedding silt for directing surface water away from the trench, and a layer of rip-rap over the silt layer for protecting the silt layer from erosion and for providing a radiation barrier; (c) a solidly-packed array of abutting modules of uniform size and shape disposed in the trench and under the cap for both encapsulating the wastes from water and for structurally supporting the cap, wherein each module in the array is slidable movable in the vertical direction in order to allow the array of modules to flexibly conform to variations in the shape of the flat trench bottom caused by seismic disturbances and to facilitate the recoverability of the modules; (d) a layer of solid, fluent, coarse, granular materials having a high hydraulic conductivity in the space between the side of the modules and the walls of the trench for obstructing any capillary-type flow of ground water to the interior of the trench; and (e) a drain and wherein the layer of silt is sloped to direct surface water flowing over the cap into the drain

  16. G. Nuclear power plant siting

    International Nuclear Information System (INIS)

    1976-01-01

    The selection of a site for a nuclear power site is a complex process involving considerations of public health and safety, engineering design, economics, and environmental impact. Although policies adopted in various countries differ in some details, a common philosophy usually underlies the criteria employed. The author discusses the basic requirements, as they relate to New Zealand, under the headings: engineering and economics; health and safety; environmental factors

  17. Cancer mortality around nuclear sites

    International Nuclear Information System (INIS)

    Hill, C.; LaPlanche, A.

    1991-01-01

    Studies (including that of Gardner) of cancer mortality around individual nuclear sites in Britain show an excess of childhood leukemia near such sites. These have been attributed to radioactive discharges, increased radiation doses and radiation doses to the fathers of affected children. However, no such excess has been found in studies in other countries including France, Canada and the USA where similar radiation doses could have been received. Several explanations of this discrepancy are reviewed. It is possible that results from the small UK samples may be due to chance. A difference in external and internal doses for reprocessing plant workers may also be a factor. The possibility of a viral infection for leukemia spreading in new town populations is also mentioned. Whilst the studies in other countries are reassuring, the childhood leukemia excesses found in Britain round nuclear sites are still unexplained. (UK)

  18. Sellafield - a nuclear licensed site

    International Nuclear Information System (INIS)

    Bloom, Phillipa.

    1987-01-01

    The report is based on the experience gained when visiting the Exhibition Centre at the BNFL Sellafield site and joining the hour-long coach trip round the site. The sights are recorded and a description given of the processes undertaken at Sellafield to reprocess the Magnox fuel and store the spent fuel from AGR reactors. The purpose of the main plant building, and the passage of the spent fuel through the various processes is described. Criticism is made of the safety record at Sellafield and a full and open debate on nuclear power is called for. (UK)

  19. Siting of nuclear facilities. Selections from Nuclear Safety

    International Nuclear Information System (INIS)

    Buchanan, J.R.

    1976-07-01

    The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria

  20. Siting of nuclear facilities. Selections from Nuclear Safety

    Energy Technology Data Exchange (ETDEWEB)

    Buchanan, J.R.

    1976-07-01

    The report presented siting policy and practice for nuclear power plants as developed in the U.S. and abroad. Twenty-two articles from Nuclear Safety on this general topic are reprinted since they provide a valuable reference source. The appendices also include reprints of some relevant regulatory rules and guides on siting. Advantages and disadvantages of novel siting concepts such as underground containment, offshore siting, and nuclear energy parks are addressed. Other topics include site criteria, risk criteria, and nuclear ship criteria.

  1. Underground Nuclear Testing Program, Nevada Test Site

    International Nuclear Information System (INIS)

    1975-09-01

    The Energy Research and Development Administration (ERDA) continues to conduct an underground nuclear testing program which includes tests for nuclear weapons development and other tests for development of nuclear explosives and methods for their application for peaceful uses. ERDA also continues to provide nuclear explosive and test site support for nuclear effects tests sponsored by the Department of Defense. This Supplement extends the Environmental Statement (WASH-1526) to cover all underground nuclear tests and preparations for tests of one megaton (1 MT) or less at the Nevada Test Site (NTS) during Fiscal Year 1976. The test activities covered include numerous continuing programs, both nuclear and non-nuclear, which can best be conducted in a remote area. However, if nuclear excavation tests or tests of yields above 1 MT or tests away from NTS should be planned, these will be covered by separate environmental statements

  2. Visitor centres at nuclear facility sites

    International Nuclear Information System (INIS)

    1993-01-01

    Communications strategies in the nuclear field are often based on the creation of visitor centres at nuclear facility sites. Today, the design, as well as the realization and management of such centres has become a specialized function, and its role is very complementary to the nuclear operator's. It also uses the latest technology in the field of audio-visual, experiment and interactivity. This publication contains the proceedings of an international seminar organized by the OECD Nuclear Energy Agency on the role of visitor centres at nuclear facility sites. It includes the main papers presented at this Seminar

  3. Site survey for nuclear power plants

    International Nuclear Information System (INIS)

    1984-01-01

    This Safety Guide describes the first stage of the siting process for nuclear power plants - the site survey to select one or more preferred candidate sites. Its purpose is to recommend procedures and provide information for use in implementing a part of the Code of Practice on Safety in Nuclear Power Plant Siting (IAEA Safety Series No.50-C-S). The organization, procedures, methodologies, guidance for documenting the site survey process and examples of detailed procedures on some safety-related site characteristics are given in the Guide

  4. Site evaluation for nuclear installations. Safety requirements

    International Nuclear Information System (INIS)

    2003-01-01

    This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Siting, which was issued in 1988 as Safety Series No. 50-C-S (Rev. 1). It takes account of developments relating to site evaluations for nuclear installations since the Code on Siting was last revised. These developments include the issuing of the Safety Fundamentals publication on The Safety of Nuclear Installations, and the revision of various safety standards and other publications relating to safety. Requirements for site evaluation are intended to ensure adequate protection of site personnel, the public and the environment from the effects of ionizing radiation arising from nuclear installations. It is recognized that there are steady advances in technology and scientific knowledge, in nuclear safety and in what is considered adequate protection. Safety requirements change with these advances and this publication reflects the present consensus among States. This Safety Requirements publication was prepared under the IAEA programme on safety standards for nuclear installations. It establishes requirements and provides criteria for ensuring safety in site evaluation for nuclear installations. The Safety Guides on site evaluation listed in the references provide recommendations on how to meet the requirements established in this Safety Requirements publication. The objective of this publication is to establish the requirements for the elements of a site evaluation for a nuclear installation so as to characterize fully the site specific conditions pertinent to the safety of a nuclear installation. The purpose is to establish requirements for criteria, to be applied as appropriate to site and site-installation interaction in operational states and accident conditions, including those that could lead to emergency measures for: (a) Defining the extent of information on a proposed site to be presented by the applicant; (b) Evaluating a proposed site to ensure that the site

  5. Managing Siting Activities for Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-06-15

    One of the IAEA's statutory objectives is to ''seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world''. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The introduction of nuclear power brings new challenges to States - one of them being the selection of appropriates sites. It is a project that needs to begin early, be well managed, and deploy good communications with all stakeholders; including regulators. This is important, not just for those States introducing nuclear power for the first time, but for any State looking to build a new nuclear power plant. The purpose of the siting activities goes beyond choosing a suitable site and acquiring a licence. A large part of the project is about producing and maintaining a validated

  6. Managing Siting Activities for Nuclear Power Plants

    International Nuclear Information System (INIS)

    2012-01-01

    One of the IAEA's statutory objectives is to ''seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world''. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The introduction of nuclear power brings new challenges to States - one of them being the selection of appropriates sites. It is a project that needs to begin early, be well managed, and deploy good communications with all stakeholders; including regulators. This is important, not just for those States introducing nuclear power for the first time, but for any State looking to build a new nuclear power plant. The purpose of the siting activities goes beyond choosing a suitable site and acquiring a licence. A large part of the project is about producing and maintaining a validated

  7. Approach of the safety of nuclear sites

    International Nuclear Information System (INIS)

    Faure, J.

    1991-08-01

    The implantation on a site of nuclear power plant, nuclear facility, laboratory or nuclear waste storage, or more generally a risk facility, require to take into account the aggression of the environment on the facility (earth quakes, explosions, inundations, aircraft crash...) and dangers presented by the facility on the environment (radioactive release, noise...). The consequences of releases on the environment aim to study and also the characteristics of the environment to evaluate the consequences in normal and accidental conditions [fr

  8. Introduction to Nuclear Power Plant Environment Supervisory Committee

    International Nuclear Information System (INIS)

    Lee, Byung Il

    2008-01-01

    In Korea, there are five nuclear power plant sites, located at Yongkwang, Kori, Shin Kori, Uljin, and Wolsong. Each administrative district has its own NESC (Nuclear plant Environment Public Supervisory Committee) which consists of a steering committee and a center. The purpose of NESC is to let the public survey and inspect nuclear plant environment and then improve a clarity and confidence in plant construction and operation by themselves. In order to understand the situation of NESC and explore ways toward a better role of NESC, in this paper we try to enumerate a few major facts related to a current status of NESC. As a summary, there must be a great role of NESC in the relationship between the residents, a nuclear industry company and the related government division. Furthermore, NESC would certainly do its role for all sides provided that more strong definition of NESC in law, more financial supporting and more philosophical speculation for the being of NESC

  9. Distributions of 137Cs and 90Sr in the soil of Uljin, South Korea

    International Nuclear Information System (INIS)

    Song, Ji Yeon; Kim, Wan; Maeng, Seong Jin; Lee, Sang Hoon

    2016-01-01

    For the purpose of baseline data collection and enhancement of environmental monitoring the distribution studies of 137 Cs and 90 Sr in the soil of Uljin province was performed and the relation between surface soil activities and soil properties (pH, TOC and median of the surface soil) was analyzed. For 14 spots within 10 km from the NPP surface soil samples were collected and soils for depth profile were sampled for 3 spots in April 2011. Using γ-ray spectrometry with HPGe detector, the concentrations of 137 Cs were determined and the concentrations of 90 Sr were measured by counting β-activity of 90 Y (in equilibrium with 90 Sr) in a gas flow proportional counter. The concentration ranges of 137 Cs and 90 Sr were <0.479-39.6 Bq (kg-dry)-1 (avg. 7.51 Bq·(kg-dry)-1) and 0.209-1.85 Bq·(kg-dry)-1 (avg. 0.74 Bq·(kg-dry)-1) which were similar to the reported values from other regions in Korea. The activity ratio of 137 Cs to 90 Sr in surface soils was around 9.67, which is much bigger than the initial value of 1.75 for worldwide fallouts because of faster downward movement of 90 Sr after fall-out than that of 137 Cs. For depth profile studies soils were collected down to 40 cm depth for the locations of Deokgu, Hujeong and Maehwa. The 137 Cs concentration distribution of the first two showed maximum values at top soils and decreased rapidly in exponential manner, while 90 Sr showed two local maximum values for soils near top and about 30 cm depth. Through linear fittings between the 137 Cs and 90 Sr concentrations of surface soil and pH, TOC and median of the surface soil, the only probable relationship obtained was between 137 Cs and TOC (determination coefficient R2=0.6). The concentration ranges of 137 Cs and 90 Sr in Uljin were similar to the reported values from other regions in Korea. The only probable relationship obtained between activities and soil properties was between 137 Cs and TOC

  10. Distributions of {sup 137}Cs and {sup 90}Sr in the soil of Uljin, South Korea

    Energy Technology Data Exchange (ETDEWEB)

    Song, Ji Yeon; Kim, Wan; Maeng, Seong Jin; Lee, Sang Hoon [Kyungpook National University, Daegu (Korea, Republic of)

    2016-05-15

    For the purpose of baseline data collection and enhancement of environmental monitoring the distribution studies of {sup 137}Cs and {sup 90}Sr in the soil of Uljin province was performed and the relation between surface soil activities and soil properties (pH, TOC and median of the surface soil) was analyzed. For 14 spots within 10 km from the NPP surface soil samples were collected and soils for depth profile were sampled for 3 spots in April 2011. Using γ-ray spectrometry with HPGe detector, the concentrations of {sup 137}Cs were determined and the concentrations of {sup 90}Sr were measured by counting β-activity of {sup 90}Y (in equilibrium with {sup 90}Sr) in a gas flow proportional counter. The concentration ranges of {sup 137}Cs and {sup 90}Sr were <0.479-39.6 Bq (kg-dry)-1 (avg. 7.51 Bq·(kg-dry)-1) and 0.209-1.85 Bq·(kg-dry)-1 (avg. 0.74 Bq·(kg-dry)-1) which were similar to the reported values from other regions in Korea. The activity ratio of {sup 137}Cs to {sup 90}Sr in surface soils was around 9.67, which is much bigger than the initial value of 1.75 for worldwide fallouts because of faster downward movement of {sup 90}Sr after fall-out than that of {sup 137}Cs. For depth profile studies soils were collected down to 40 cm depth for the locations of Deokgu, Hujeong and Maehwa. The {sup 137}Cs concentration distribution of the first two showed maximum values at top soils and decreased rapidly in exponential manner, while {sup 90}Sr showed two local maximum values for soils near top and about 30 cm depth. Through linear fittings between the {sup 137}Cs and {sup 90}Sr concentrations of surface soil and pH, TOC and median of the surface soil, the only probable relationship obtained was between {sup 137}Cs and TOC (determination coefficient R2=0.6). The concentration ranges of {sup 137}Cs and {sup 90}Sr in Uljin were similar to the reported values from other regions in Korea. The only probable relationship obtained between activities and soil properties

  11. Nuclear waste: Status of DOE's nuclear waste site characterization activities

    International Nuclear Information System (INIS)

    1987-01-01

    Three potential nuclear waste repository sites have been selected to carry out characterization activities-the detailed geological testing to determine the suitability of each site as a repository. The sites are Hanford in south-central Washington State, Yucca Mountain in southern Nevada, and Deaf Smith in the Texas Panhandle. Two key issues affecting the total program are the estimations of the site characterization completion data and costs and DOE's relationship with the Nuclear Regulatory Commission which has been limited and its relations with affected states and Indian tribes which continue to be difficult

  12. Radionuclide metrology research for nuclear site decommissioning

    Science.gov (United States)

    Judge, S. M.; Regan, P. H.

    2017-11-01

    The safe and cost-effective decommissioning of legacy nuclear sites relies on accurate measurement of the radioactivity content of the waste materials, so that the waste can be assigned to the most appropriate disposal route. Such measurements are a new challenge for the science of radionuclide metrology which was established largely to support routine measurements on operating nuclear sites and other applications such as nuclear medicine. In this paper, we provide a brief summary of the international measurement system that is established to enable nuclear site operators to demonstrate that measurements are accurate, independent and fit for purpose, and highlight some of the projects that are underway to adapt the measurement system to meet the changing demands from the industry.

  13. Citizen participation in nuclear waste repository siting

    International Nuclear Information System (INIS)

    Howell, R.E.; Olsen, D.

    1982-12-01

    The following study presents a proposed strategy for citizen participation during the planning stages of nuclear waste repository siting. It discusses the issue from the general perspective of citizen participation in controversial issues and in community development. Second, rural institutions and attitudes toward energy development as the context for developing a citizen participation program are examined. Third, major citizen participation techniques and the advantages and disadvantages of each approach for resolving public policy issues are evaluated. Fourth, principles of successful citizen participation are presented. Finally, a proposal for stimulating and sustaining effective responsible citizen participation in nuclear waste repository siting and management is developed

  14. Sites for locations of nuclear reactors

    International Nuclear Information System (INIS)

    Balcazar, M.; Huerta, M.; Lopez, A.

    2014-10-01

    A restriction on sites of nuclear energy is the history of seismic activity, in its magnitude (Richter) and intensity (Mercalli). This article delimits the areas of greatest magnitude and national seismic intensity, with restrictions of ground acceleration; the supplement areas with a low magnitude of seismic activity are shown. Potential sites for the location of these sites are introduced into a geographic information system. The set of geo-referenced data contains the location of the active volcanic manifestations; the historical record of earthquake epicenters, magnitudes and intensities; major geological faults; surface hydrology and water bodies; location of population density; protected areas; contour lines; the rock type or geology. The geographic information system allows entering normative criteria and environmental restrictions that correlate with geo-referenced data described above, forms both probable and exclusion areas for the installation of nuclear sites. (Author)

  15. How to solve nuclear siting problems

    International Nuclear Information System (INIS)

    Inhaber, H.

    1992-01-01

    In recent years, finding sites for nuclear facilities, both reactors and waste repositories, has become more of a problem. While all agree that the difficulties are more than technical, a technical solution is presently pursued. The reverse Dutch auction generates a solution to siting. It produces a volunteer community or state, at the same time retaining public safety and environmental standards. No coercion is required. Elements of the system already exist in a number of public policy areas. (orig.) [de

  16. Declassification and restoration of nuclear sites

    International Nuclear Information System (INIS)

    Noynaert, L.; Rahier, A.; Deboodt, P.; Massaut, V.

    1998-09-01

    The report describes the legal and technical aspects of the declassification and restoration of nuclear sites. This involves a number of technical and administrative operations. Different declassification strategies are discussed. The evaluation of the risks and impact on the environment are discussed as well as research and development needs, costs and possible sources for funding

  17. Demographic characteristics of nuclear installations sites

    International Nuclear Information System (INIS)

    Doumenc, A.; Faure, J.

    1988-01-01

    The selection of a nuclear installations sites can not be conceived without a deep analysis of demographic context. This analysis permits to define the critical populations around the installation and is an essential element of emergency plans. 1 tab., 2 refs. (F.M.)

  18. Population distribution around French nuclear sites

    International Nuclear Information System (INIS)

    Bastien, M.C.

    1985-10-01

    With the help of two files respectively from the Institut geographique national (IGN) containing the geographic reference of all cities in France, and from the Institut national de la statistique et des etudes economiques (INSEE) containing the population figures of the 1982 census, the distribution of the population around a geographic point can be determined according to a given grid. Tables of population distribution around the 30 french nuclear sites were obtained by this method; however, at a short distance from a site, a detailed local examination/survey/investigation is necessary. Data shall have to be collected to estimate the non-french population around frontier sites [fr

  19. Fate of nuclear waste site remains unclear

    International Nuclear Information System (INIS)

    Anderson, E.V.

    1980-01-01

    The only commercial nuclear fuel reprocessing plant in the U.S., located in West Valley, N.Y., has been shut down since 1972, and no efforts have yet been made to clean up the site. The site contains a spent-fuel pool, high level liquid waste storage tanks, and two radioactive waste burial grounds. Nuclear Fuel Services, Inc., has been leasing the site from the New York State Energy RandD Authority. Federal litigation may ensue, prompted by NRC and DOE, if the company refuses to decontaminate the area when its lease expires at the end of 1980. DOE has developed a plan to solidify the liquid wastes at the facility but needs additional legislation and funding to implement the scheme

  20. The siting of UK nuclear reactors.

    Science.gov (United States)

    Grimston, Malcolm; Nuttall, William J; Vaughan, Geoff

    2014-06-01

    Choosing a suitable site for a nuclear power station requires the consideration and balancing of several factors. Some 'physical' site characteristics, such as the local climate and the potential for seismic activity, will be generic to all reactors designs, while others, such as the availability of cooling water, the area of land required and geological conditions capable of sustaining the weight of the reactor and other buildings will to an extent be dependent on the particular design of reactor chosen (or alternatively the reactor design chosen may to an extent be dependent on the characteristics of an available site). However, one particularly interesting tension is a human and demographic one. On the one hand it is beneficial to place nuclear stations close to centres of population, to reduce transmission losses and other costs (including to the local environment) of transporting electricity over large distances from generator to consumer. On the other it is advantageous to place nuclear stations some distance away from such population centres in order to minimise the potential human consequences of a major release of radioactive materials in the (extremely unlikely) event of a major nuclear accident, not only in terms of direct exposure but also concerning the management of emergency planning, notably evacuation.This paper considers the emergence of policies aimed at managing this tension in the UK. In the first phase of nuclear development (roughly speaking 1945-1965) there was a highly cautious attitude, with installations being placed in remote rural locations with very low population density. The second phase (1965-1985) saw a more relaxed approach, allowing the development of AGR nuclear power stations (which with concrete pressure vessels were regarded as significantly safer) closer to population centres (in 'semi-urban' locations, notably at Hartlepool and Heysham). In the third phase (1985-2005) there was very little new nuclear development, Sizewell

  1. Nuclear power plant siting: Hydrogeologic aspects

    International Nuclear Information System (INIS)

    1984-01-01

    This Safety Guide gives guidelines and methods for determining the ground water concentration of radionuclides that could result from postulated releases from nuclear power plants. The Guide gives recommendations on the data to be collected and the investigations to be performed at various stages of nuclear power plant siting in relation to the various aspects of the movement of accidentally released radioactive material through the ground water, the selection of an appropriate mathematical or physical model for the hydrodynamic dispersion even two-phase distribution of the radioactive material and an appropriate monitoring programme

  2. Liability for on-site nuclear property damage

    International Nuclear Information System (INIS)

    Neems, H.J.

    2000-01-01

    Typically, liability for on-site property addressed in contracts between operator and its suppliers. Nuclear power plant operators ordinarily protect themselves against risk of nuclear damage to on-site property by insurance. Nuclear liability laws do not specifically address liability for nuclear damage to on-site property. Nuclear plant owners should address risk of damage to on-site property when developing risk management program

  3. A nuclear inspector's perspective on decommissioning at UK nuclear sites

    International Nuclear Information System (INIS)

    Robinson, I.F.

    1999-01-01

    The legislative framework used to regulate decommissioning of nuclear facilities in the UK is described. Pre-licensing requirements are outlined and the operation of a nuclear site licence is described. Mention is made of safety assessment and the published principles which are NII's view of what constitutes good practice within the nuclear industry. HSE's approach to the regulation of nuclear decommissioning is described before discussing issues associated with optioneering, the timing of decommissioning, occupational doses and public doses. It is noted that the professional approach taken by the nuclear industry within the framework of the existing regulatory requirements has resulted in considerable reductions in occupational dose over the last few years. The de-licensing process is described in the context of terminating a licensee's period of responsibility for safety, and principles by which 'no danger' may be judged are described. Impending new legislation on environmental impact assessment in relation to decommissioning nuclear reactors is mentioned. It is concluded that a powerful and flexible method of regulatory control is in place with regard to nuclear decommissioning. (author)

  4. Remote sensing for nuclear power plant siting

    International Nuclear Information System (INIS)

    Siegal, B.S.; Welby, C.W.

    1981-01-01

    It is shown that satellite remote sensing provides timely and cost-effective information for siting and site evaluation of nuclear power plants. Side-looking airborne radar (SLAR) imagery is especially valuable in regions of prolonged cloud cover and haze, and provides additional assurance in siting and licensing. In addition, a wide range of enhancement techniques should be employed and different types of image should be color-combined to provide structural and lithologic information. Coastal water circulation can also be studied through repetitive coverage and the inherently synoptic nature of imaging satellites. Among the issues discussed are snow cover, sun angle, and cloud cover, and actual site evaluation studies in the Bataan peninsula of the Philippines and Laguna Verde, California

  5. Dose assessments in nuclear power plant siting

    International Nuclear Information System (INIS)

    1988-03-01

    This document is mainly intended to provide information on dose estimations and assessments for the purpose of nuclear power plant (NPP) siting. It is not aimed at giving radiation protection guidance, criteria or procedures to be applied during the process of NPP siting nor even to provide recommendations on this subject matter. The document may however be of help for implementing some of the Nuclear Safety Standards (NUSS) documents on siting. The document was prepared before April 26, 1986, when a severe accident at the Unit 4 of Chernobyl NPP in the USSR had occurred. It should be emphasized that this document does not bridge the gap which exists in the NUSS programme as far as radiation protection guidance for the specific case of siting of NPP is concerned. The Agency will continue to work on this subject with the aim to prepare a safety series document on radiation protection requirements for NPP siting. This document could serve as a working document for this purpose. Refs, figs and tabs

  6. Pickering Nuclear site wide groundwater monitoring system

    International Nuclear Information System (INIS)

    DeWilde, J.; Chin-Cheong, D.; Lledo, C.; Wootton, R.; Belanger, D.; Hansen, K.

    2001-01-01

    Ontario Power Generation Inc. (OPG) is continuing its efforts to understand the chemical and physical characteristics of the groundwater flow systems beneath the Pickering Nuclear Generating Station (PNGS). To this end, OPG constructed a site-wide Groundwater Monitoring System (GMS) at the PNGS to provide support to other ongoing environmental investigations and to provide a means to monitor current and future groundwater environmental issues. This paper will present the results of this work, including the development of a state-of-the-art data management system for storage and retrieval of environmental data for the site, which has applications for other power generation facilities. (author)

  7. Site selection for new nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Rizzo, Paul C.; Dubinsky, Melissa; Tastan, Erdem Onur, E-mail: paul.rizzo@rizzoassoc.com, E-mail: melissa.dubinsky@rizzoassoc.com, E-mail: onur.tastan@rizzoassoc.com [RIZZO Associates Inc., Pittsburgh, PA (United States); Miano, Sandra C., E-mail: scm27@psu.edu [Eletrobras Termonuclear S.A. (ELETRONUCLEAR), RJ (Brazil); Pennsylvania State University, Department of Mechanical and Nuclear Engineering, State College, PA (United States)

    2015-07-01

    The current methodology for selecting the most advantageous site(s) for nuclear power plant (NPP) development is based on the latest evolution of protocols originally established in the 1990's by the Electric Power Research Institute (EPRI) and others for programs in the USA, and more recently by the International Atomic Energy Agency (IAEA), among others. The methodology includes protocols that account for lessons learned from both the Gen III projects and the catastrophic event at Fukushima, Japan. In general, the approach requires consideration of Exclusionary or 'fatal flaw' Criteria first, based on safety as well as significant impact to the environment or human health. Sites must meet all of these Exclusionary Criteria to be considered for NPP development. Next, the remaining sites are evaluated for Avoidance Criteria that affect primarily ease of construction and operations, which allow a ranking of sites best suited for NPP development. Finally, Suitability Criteria are applied to the potential sites to better differentiate between closely ranked sites. Generally, final selection of a Preferred and an Alternate Site will require balancing of factors, expert judgment, and client input, as sites being compared will differ in their scores associated with different Avoidance Criteria and Suitability Criteria. RIZZO Associates (RIZZO) offers in this paper a modification to this methodology for selecting the site for NPP development, which accords to the categories of Exclusionary, Avoidance and Suitability Criteria strict definitions which can be considered as Absolute Factors, Critical Factors, and Economic Factors for a more focused approach to site selection. Absolute Factors include all of the safety-related Exclusionary Criteria. Critical Factors are those that are difficult to overcome unless extraordinary mitigation measures are implemented; they have a significant impact on the ability of the project to be successful and may cause the

  8. Site selection for new nuclear power plants

    International Nuclear Information System (INIS)

    Rizzo, Paul C.; Dubinsky, Melissa; Tastan, Erdem Onur; Miano, Sandra C.

    2015-01-01

    The current methodology for selecting the most advantageous site(s) for nuclear power plant (NPP) development is based on the latest evolution of protocols originally established in the 1990's by the Electric Power Research Institute (EPRI) and others for programs in the USA, and more recently by the International Atomic Energy Agency (IAEA), among others. The methodology includes protocols that account for lessons learned from both the Gen III projects and the catastrophic event at Fukushima, Japan. In general, the approach requires consideration of Exclusionary or 'fatal flaw' Criteria first, based on safety as well as significant impact to the environment or human health. Sites must meet all of these Exclusionary Criteria to be considered for NPP development. Next, the remaining sites are evaluated for Avoidance Criteria that affect primarily ease of construction and operations, which allow a ranking of sites best suited for NPP development. Finally, Suitability Criteria are applied to the potential sites to better differentiate between closely ranked sites. Generally, final selection of a Preferred and an Alternate Site will require balancing of factors, expert judgment, and client input, as sites being compared will differ in their scores associated with different Avoidance Criteria and Suitability Criteria. RIZZO Associates (RIZZO) offers in this paper a modification to this methodology for selecting the site for NPP development, which accords to the categories of Exclusionary, Avoidance and Suitability Criteria strict definitions which can be considered as Absolute Factors, Critical Factors, and Economic Factors for a more focused approach to site selection. Absolute Factors include all of the safety-related Exclusionary Criteria. Critical Factors are those that are difficult to overcome unless extraordinary mitigation measures are implemented; they have a significant impact on the ability of the project to be successful and may cause the

  9. Siting technology of underground nuclear power station

    International Nuclear Information System (INIS)

    Motojima, M.; Hibino, S.

    1989-01-01

    For the site of a nuclear power station, it may be possible to select a seaside mountain area, if the condition is suitable to excavate large rock caverns in which a reactor and other equipments are installed. As the case study on the siting technology for an underground nuclear power station, the following example was investigated. The site is a seaside steep mountain area, and almost all the equipments are installed in plural tunnel type caverns. The depth from the ground surface to the top of the reactor cavern is about 150 m, and the thickness of the rock pillar between the reactor cavern of 33 m W x 82 mH x 79 mD and the neighboring turbine cavern is 60 m. In this paper, the stability of rock caverns in this example, evaluated by numerical analysis, is described. The numerical analysis was carried out on the central cross section of the reactor cavern, taking the turbine cavern, geostress, the mechanical properties of rock mass and the process of excavation works in consideration. By the analysis, the underground caverns in this example were evaluated as stable, if the rock quality is equivalent to C H class or better according to the CRIEPI rock classification. (K.I.)

  10. Remediation of Soil at Nuclear Sites

    International Nuclear Information System (INIS)

    Holmes, R.; Boardman, C.; Robbins, R; Fox, Robert Vincent; Mincher, Bruce Jay

    2000-01-01

    As the major nuclear waste and decontamination and decommissioning projects progress, one of the remaining problems that faces the nuclear industry is that of site remediation. The range of contamination levels and contaminants is wide and varied and there is likely to be a significant volume of soil contaminated with transuranics and hazardous organic materials that could qualify as mixed TRU waste. There are many technologies that offer the potential for remediating this waste but few that tackle all or most of the contaminants and even fewer that have been deployed with confidence. This paper outlines the progress made in proving the ability of Supercritical Fluid Extraction as a method of remediating soil, classified as mixed (TRU) transuranic waste

  11. Remote sensing for nuclear power plant siting

    International Nuclear Information System (INIS)

    Siegal, B.S.; Welby, C.W.

    1981-01-01

    Remote sensing techniques enhance the selection and evaluation process for nuclear power plant siting. The principal advantage is the synoptic view which improves recognition of linear features, possibly indicative of faults. The interpretation of such images, in conjunction with seismological studies, also permits delineation of seismo-tectonic provinces. In volcanic terrains, geomorphic-age boundaries can be delineated and volcanic centers identified, providing necessary guidance for field sampling and regional model derivation. The use of such techniques is considered for studies in the Philippines, Mexico, and Greece. 5 refs

  12. Seismic studies for nuclear installations sites

    International Nuclear Information System (INIS)

    Mohammadioun, B.; Faure, J.

    1988-01-01

    The french experience in seismic risks assessment for french nuclear installations permits to set out the objectives, the phases the geographic extensions of workings to be realized for the installation safety. The data to be collected for the safety analysis are specified, they concern the regional seismotectonics, the essential seismic data for determining the seism level to be taken into account and defining the soil movement spectra adapted to the site. It is necessary to follow up the seismic surveillance during the installation construction and life. 7 refs. (F.M.)

  13. ESPSD, Nuclear Power Plant Siting Database

    International Nuclear Information System (INIS)

    Slezak, S.

    2001-01-01

    1 - Description of program or function: This database is a repository of comprehensive licensing and technical reviews of siting regulatory processes and acceptance criteria for advanced light water reactor (ALWR) nuclear power plants. The program is designed to be used by applicants for an early site permit or combined construction permit/operating license (10CFRR522), Sub-parts A and C) as input for the development of the application. The database is a complete, menu-driven, self-contained package that can search and sort the supplied data by topic, keyword, or other input. The software is designed for operation on IBM compatible computers with DOS. 2 - Method of solution: The database is an R:BASE Runtime program with all the necessary database files included

  14. Site selection of nuclear power plants

    International Nuclear Information System (INIS)

    Schnappauf, W.

    1982-01-01

    A stock report of the development of the extent as well as the fundamentals of the conflict about nuclear energy shows that the effective law is both another cause and a mirror of the discussions about it. In total the investigation shows that the planning of site selection suffers from a number of legal problems. They are mainly of structural kind and are concerned with the issues of citizens' participation and graduation of procedures which are central for the management of the conflict. Therefore the present set of instruments is hardly able to contribute to increasing the acceptancy. The kind and extent of issues on one hand as well as the dimension of the conflict on the other make clear that the executive power itself is overtaxed. In this situation the legislative authorities are called up to take responsibility upon themselves. There are no objections from the constitutional or other aspects to legal site selection. (orig./HSCH) [de

  15. A future for nuclear sites beyond their service life. Nuclear site value development

    International Nuclear Information System (INIS)

    2008-01-01

    As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites in built

  16. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies

  17. Underground siting of nuclear power plants

    International Nuclear Information System (INIS)

    Bender, F.

    1982-01-01

    The symposium gave the opportunity for an international exchange of views on the concepts of underground nuclear power plants, which are presently world wide under consideration. The results of investigations into the advantages and disadvantages with regard to the technical safety aspects of the underground plants in comparison to plants on the surface led to open and sometimes controversal discussions. As a result of the symposium (32 contributions) a general agreement can be stated on the judgement concerning the advantages and the disadvantages of underground nuclear power plants (nnp). The advantages are: increased protection against external events; delayed release of fission products in accident situations, if the closures operate properly. The disadvantages are: increased costs of the construction of underground and restrictions to such sites where either large caverns or deep pits can be constructed, which also requires that certain technical problems must be solved beforehand. Also, additional safety certificates related to the site will be required within the licensing procedures. The importance of these advantages and disadvantages was in some cases assessed very differently. The discussions also showed, that there are a number of topics where some questions have not been finally answered yet. (orig./HP) [de

  18. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

    1990-09-01

    The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

  19. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords

  20. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

    1989-09-01

    The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

  1. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.

    2013-09-30

    This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.

  2. The problem of nuclear power plants site survey and selection

    International Nuclear Information System (INIS)

    Anh, T.H.; Hung, H.V.; Bui Quoc Thang

    1986-01-01

    The article presents the main steps of nuclear power plants siting, including the requirements from a nuclear power station onto the site, and the analysis of potential effects of a nuclear power station to the environment. Attentions are called upon the analysis of important factors such as electric transmission losses, cooling water supply, site accessibility, local infrastructure, risks due to man made and natural sources of aggression to the nuclear power plants, population, distribution, hydrological and atmospheric dispersion conditions

  3. Nuclear Materials Management for the Nevada Test Site (NTS)

    International Nuclear Information System (INIS)

    Jesse C. Schreiber

    2007-01-01

    The Nevada Test Site (NTS) has transitioned from its historical role of weapons testing to a broader role that is focused on being a solution to multiple National Nuclear Security Administration (NNSA) challenges and opportunities with nuclear materials for the nation. NTS is supporting other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to make the production complex smaller, more consolidated, and more modern. With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through dispositioning and consolidating nuclear material. This includes moving material from other sites to NTS. State-of-the-art nuclear material management and control practices at NTS are essential for NTS to ensure that these new activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS is aggressively addressing this challenge

  4. Rehabilitation of nuclear test site at Maralinga

    International Nuclear Information System (INIS)

    Grad, P.

    1997-01-01

    A program to rehabilitate contaminated areas at the Maralinga Nuclear Test Range in South Australia is being undertaken by the Australian Department of Primary Industries and Energy (DPIE). A major part of the program is directed at reducing the risk presented by the contaminated debris buried at Taranaki, Maralinga's most heavily contaminated site. The rehabilitation program is using the insitu vitrification technology developed for the US Department of Energy. The program is now in its third phase, involving the construction of the full-scale treatment plant. This will be completed later this year. The fourth and last phase will involve the treatment of the Taranaki pits. This will commence in 1998. Tests carried out so far indicated that the normalized leach rates for all oxides in the vitrified product were less than 0.1g/m 2 . ills

  5. Hydrosphere monitoring at nuclear power plant sites

    International Nuclear Information System (INIS)

    Belousova, A.P.; Zakharova, T.V.; Shvets, V.M.

    1993-01-01

    The paper deals with problems related to protection of the environment in areas occupied by nuclear power plants (NPP). NPP construction and operation result in destruction of ecological, geochemical and geological equilibria in and around NPP sites. This process requires monitoring. Recommendations of the International Agency for Atomic Energy (IAAE) suggest monitoring to commence 2-3 years prior to the start of NPP construction. The paper describes the extent of hydrosphere monitoring and guidelines along which monitoring is to be organized. The authors recommend a certain approach toward the planning observation networks and provide description of forecasting subsystem that consist of a data bank, a continuously operating model (COM) and a forecast unit

  6. Siting and environment: towards an effective nuclear siting policy

    Energy Technology Data Exchange (ETDEWEB)

    Muntzing, L M

    1976-03-01

    The author looks at pending U.S. legislation which aims to streamline planning and regulatory procedures while at the same time preserving the existing social and environmental safeguards. The origins of the environmental factors of regulatory concern in the United States are largely rooted in the social phenomenon of environmental awareness of the late 1960s. This public awareness was given expression in the National Environmental Policy Act of 1969 (NEPA). How this Act has affected the U.S. regulatory processes, other environmental programs, and the nuclear power industry is reviewed briefly. NEPA directed the Federal Government to improve and coordinate Federal plans and programs to protect the environment and to develop methods and procedures that would balance environmental values with economic and technical considerations. The changes effected by this legislation have been dramatic. It has resulted in the rapid infusion into the governmental decision-making process of the full range of environmental considerations. The lessons of the Calvert Cliffs decision are summarized, and the siting of fuel-cycle facilities in the U.S. is reviewed. A recent study by Chase Econometrics Associates indicates that United States Federal pollution control requirements will have only a very small impact on economic growth, employment, and prices between now and 1982. For example, the Chase Study concludes that by 1982 the real GNP should be virtually the same as it would have been in the absence of pollution controls. (MCW)

  7. Nuclear energy center site survey reactor plant considerations

    International Nuclear Information System (INIS)

    1976-05-01

    The Energy Reorganization Act of 1974 required the Nuclear Regulatory Commission (NRC) to make a nuclear energy center site survey (NECSS). Background information for the NECSS report was developed in a series of tasks which include: socioeconomic inpacts; environmental impact (reactor facilities); emergency response capability (reactor facilities); aging of nuclear energy centers; and dry cooled nuclear energy centers

  8. Site-Specific Atmospheric Dispersion Characteristics of Korean Nuclear Power Plant Sites

    International Nuclear Information System (INIS)

    Han, M. H.; Kim, E. H.; Suh, K. S.; Hwang, W. T.; Choi, Y. G.

    2001-01-01

    Site-specific atmospheric dispersion characteristics have been analyzed. The northwest and the southwest wind prevail on nuclear sites of Korea. The annual isobaric surface averaged for twenty years around Korean peninsula shows that west wind prevails. The prevailing west wind is profitable in the viewpoint of radiation protection because three of four nuclear sites are located in the east side. Large scale field tracer experiments over nuclear sites have been conducted for the purpose of analyzing the atmospheric dispersion characteristics and validating a real-time atmospheric dispersion and dose assessment system FADAS. To analyze the site-specific atmospheric dispersion characteristics is essential for making effective countermeasures against a nuclear emergency

  9. Issues in clustered nuclear siting: a comparison of a hypothetical nuclear energy center in New Jersey with dispersed nuclear siting

    International Nuclear Information System (INIS)

    Meier, P.M.; Morell, D.

    1976-09-01

    The report is an analysis of a hypothetical nuclear energy center (NEC) conducted in support of the recently completed study by the Nuclear Regulatory Commission, mandated by the Congress in the Energy Reorganization Act of 1974. The intent of the analysis of the hypothetical, or ''surrogate'', site was to inject a local and regional perspective into the assessment of technical, environmental, institutional, and socioeconomic issues which could be adequately addressed only by reference to a specific site. The hypothetical NEC site in Ocean County, New Jersey, was chosen to illustrate the problems and impacts of potential energy centers in coastal and near-coastal sites in relatively close proximity to large metropolitan areas. Earlier studies of hypothetical energy centers on the Mississippi River at River Bend, La., and on the Columbia River near Hanford, Washington, were also re-examined for their relevance to this new study effort. Neither Ocean County, nor any of the other surrogate sites, have been considered for actual construction of an NEC, nor does their selection for study purposes imply any judgement of desirability. Indeed, the major finding of the report presented is that Ocean County is a relatively poor location for an energy center, and this may well be true of many coastal locations similar to the Jersey shore. The objective in selecting surrogate sites, then, was not to find the best locations, but to select sites that would illustrate the broadest range of potential public policy and siting issues

  10. Borehole geophysics in nuclear power plant siting

    International Nuclear Information System (INIS)

    Crosby, J.W.; Scott, J.D.

    1979-01-01

    Miniaturized borehole geophysical equipment designed for use in ground-water investigations can be adapted to investigations of nuclear power plant sites. This equipment has proved to be of value in preliminary and comprehensive studies of interior basins where thick sequences of Quaternary clastic sediment, occasionally with associated volcanic rocks, pose problems of stratigraphic correlation. The unconsolidated nature of the deposits generally requires that exploratory holes be cased, which ordinarily restricts the borehole geophysical studies to the radiation functions--natural gamma, gamma-gamma, neutron-gamma, and neutron-epithermal neutron logs. Although a single log response may be dominant in a given area, correlations derive from consideration of all log responses as a composite group. Because major correlations usually are based upon subtle differences in the physical properties of the penetrated sediment, high-resolution logging procedures are employed with some sacrifice of the quantitative perameters important to petroleum technology. All geophysical field data are recorded as hard copy and as digital information on punched paper tape

  11. Borehole geophysics in nuclear power plant siting

    International Nuclear Information System (INIS)

    Crosby, J.W.; Scott, J.D.

    1979-01-01

    Miniaturized borehole geophysical equipment designed for use in ground-water investigations can be adapted to investigations of nuclear power plant sites. This equipment has proved to be of value in preliminary and comprehensive studies of interior basins where thick sequences of Quaternary clastic sediment, occasionally with associated volcanic rocks, pose problems of stratigraphic correlation. The unconsolidated nature of the deposits generally requires that exploratory holes be cased, which ordinarily restricts the borehole geophysical studies to the radiation functions--natural gamma, gamma-gamma, neutron-gamma, and neutron-epithermal neutron logs. Although a single log response may be dominant in a given area, correlations derive from consideration of all log responses as a composite group. Because major correlations usually are based upon subtle differences in the physical properties of the penetrated sediment, high-resolution logging procedures are employed with some sacrifice of the quantitative parameters important to petroleum technology. All geophysical field data are recorded as hard copy and as digital information on punched paper tape. Digital data are subsequently computer processed and plotted to scales that enhance the stratigraphic data being correlated. Retention of the data in analog format permits rapid review, whereas computer plotting allows playback and detailed examination of log sections and sequences that may be attenuated on hard copy because of the logarithmic nature of the response to the physical property being examined

  12. Site selection for nuclear power plants

    International Nuclear Information System (INIS)

    Ehjchkholz, D.

    1980-01-01

    Problem of NPP site selection in the USA including engineering factors, radiation and environmental protection factors is stated in detail. Floating and underground sites are considered especially. The attention in paid to waste storage and risk criterium in siting [ru

  13. Nuclear energy center site survey: fuel cycle studies

    International Nuclear Information System (INIS)

    1976-05-01

    Background information for the Nuclear Regulatory Commission Nuclear Energy Center Site Survey is presented in the following task areas: economics of integrated vs. dispersed nuclear fuel cycle facilities, plutonium fungibility, fuel cycle industry model, production controls and failure contingencies, environmental impact, waste management, emergency response capability, and feasibility evaluations

  14. Off-site nuclear emergency management

    International Nuclear Information System (INIS)

    Miska, H.

    2003-01-01

    Full text: Urgent protective measures for the possibly affected population are the main items to be addressed here, that means actions to be planned and taken in the pre-release and release phase of a nuclear accident. Since we will focus an off-site nuclear emergency management, the utility or licensee only plays a subordinate role, but nevertheless may be the potential cause of all actions. At the other end, there is the possible affected population, the environment, and also economic values. Emergency preparedness and response aims at minimizing adverse effects from the power plant to the values to protect. In the early phase of an accident under consideration here, prompt and sharp actions are necessary to ensure efficacy. On the other hand, the available information on the situation is most limited in this phase such that pre-determined actions based on simple criteria are indispensable. The responsibility for early response actions normally rest with a regional authority which may have some county administrations at subordinate level. The leader of the regional staff has to decide upon protective measures to be implemented at county or municipal level; thus, coherence of the response is ensured at least at a regional level. The decision will be governed at the one side by the existing or predicted radiological situation, on the other side an practical limitations like availability of teams and means. The radiological situation has to be assessed by an advisory team that compiles all information from the utility, the weather conditions, and monitoring results. While the staff leader is experienced through response to major non-nuclear events, the advisors mainly come from the environmental side, having no experience in taking swift decisions in an emergency, but are used to control and prevent. This might be the source of conflicts as observed in several exercises. The radiation protection advisors collect information from the utility, especially about time

  15. Semipalatinsk nuclear test site: History of building and function

    International Nuclear Information System (INIS)

    Sergazina, G.M.; Balmukhanov, S.B.

    1999-01-01

    A vast materials on history of Semipalatinsk nuclear test site creation and it building and function are presented. Authors with big reliability report one page of Kazakhstan's history. In steppe on naked place thousands of soldiers and officers, construct and military specialists have built the nuclear site on which during 40 years were conducting nuclear tests . Prolonged chronic radiation on population living near by site results to tragedy which is confessed by General Assembly of United Nations. In the book aspects of test site conversion and rehabilitation of injured population are considered. The book consists of introduction, three chapters and conclusion. The book is intended to wide circle of readers. (author)

  16. Siting studies for new nuclear power plants in Argentina

    International Nuclear Information System (INIS)

    Barbaran, Gustavo A.

    2008-01-01

    This paper is a summary of the thesis prepared by the Group of Prospective and Energy Planning of the National Atomic Energy Commission for the 'Specialization on Applications of Nuclear Technology Course' of the Instituto Balseiro in 2007. It describes the evolution of siting studies through time and the main focus worldwide in this type of studies. Then, it makes a brief review of previous siting studies of nuclear power plants conducted in Argentina. It carries out a description of the methodology to conduct a site evaluation for nuclear power plants according to actual international criteria. Finally, it describes the licensing process that follows every site study. (author) [es

  17. Underground siting of nuclear power plants

    International Nuclear Information System (INIS)

    Pinto, S.; Telleschi, P.

    1978-10-01

    Two of the main underground siting alternatives, the rock cavity plant and the pit siting, have been investigated in detail and two layouts, developed for specific sites, have been proposed. The influence of this type of siting on normal operating conditions and during abnormal occurences have been investigated. (Auth.)

  18. Socioeconomic impacts: nuclear power station siting

    International Nuclear Information System (INIS)

    1977-06-01

    The rural industrial development literature is used to gain insights on the socioeconomic effects of nuclear power stations. Previous studies of large industrial facilities in small towns have important implications for attempts to understand and anticipate the impacts of nuclear stations. Even a cursory review of the nuclear development literature, however, reveals that industrialization research in rural sociology, economic geography and agricultural economics has been largely ignored

  19. The evaluation of site characteristics for Guangdong nuclear power plant

    International Nuclear Information System (INIS)

    Zhou Ruming; Wu Dizhong; Yan Zhongmin

    1987-01-01

    This paper gives an account of the features of the site of Guangdong Nuclear Power Plant (GNPP) in general and in particular evaluates the outstanding site characteristics related to nuclear safety and public health. It is composed of two parts: the first part describes the seismo-geologic conditions of the site and the other treats the atmospheric dispersion conditions. It also contains the discussion why the possibility of inhabitancy within 5 km from the exclusion ares boundary would not be affected. (author)

  20. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

    International Nuclear Information System (INIS)

    Zull, Lawrence M.; Yeniscavich, William

    2008-01-01

    The Defense Nuclear Facilities Safety Board (Board) is an independent federal agency established by Congress in 1988 to provide nuclear safety oversight of activities at U.S. Department of Energy (DOE) defense nuclear facilities. The activities under the Board's jurisdiction include the design, construction, startup, operation, and decommissioning of defense nuclear facilities at DOE sites. This paper reviews the Board's safety oversight of decommissioning activities at DOE sites, identifies the safety problems observed, and discusses Board initiatives to improve the safety of decommissioning activities at DOE sites. The decommissioning of former defense nuclear facilities has reduced the risk of radioactive material contamination and exposure to the public and site workers. In general, efforts to perform decommissioning work at DOE defense nuclear sites have been successful, and contractors performing decommissioning work have a good safety record. Decommissioning activities have recently been completed at sites identified for closure, including the Rocky Flats Environmental Technology Site, the Fernald Closure Project, and the Miamisburg Closure Project (the Mound site). The Rocky Flats and Fernald sites, which produced plutonium parts and uranium materials for defense needs (respectively), have been turned into wildlife refuges. The Mound site, which performed R and D activities on nuclear materials, has been converted into an industrial and technology park called the Mound Advanced Technology Center. The DOE Office of Legacy Management is responsible for the long term stewardship of these former EM sites. The Board has reviewed many decommissioning activities, and noted that there are valuable lessons learned that can benefit both DOE and the contractor. As part of its ongoing safety oversight responsibilities, the Board and its staff will continue to review the safety of DOE and contractor decommissioning activities at DOE defense nuclear sites

  1. A survey of the underground siting of nuclear power plants

    International Nuclear Information System (INIS)

    Pinto, S.

    1979-12-01

    The idea of locating nuclear power plants underground is not new, since in the period of time between the late fifties and the early sixties, four small nuclear plants have been built in Europe in rock cavities. Safety has been, in general, the main motivation for such a siting solution. In the last years several factors such as increasing power transmission costs, decreasing number of suitable sites above ground, increased difficulties in obtaining site approval by the licensing authorities, increasing opposition to nuclear power, increasing concern for extreme - but highly improbable - accidents, together with the possibility of utilizing the waste heat and the urban siting concept have renewed the interest for the underground siting as an alternative to surface siting. The author presents a survey of the main studies carried out on the subject of underground siting. (Auth.)

  2. Geological and geotechnical investigations for nuclear power plants sites

    International Nuclear Information System (INIS)

    Alves, P.R.R.

    1984-09-01

    This dissertation presents a general methodology for the tasks of geological and geotechnical investigations, to be performed in the proposed sites for construction of nuclear Power Plants. In this work, items dealing with the standards applied to licensing of Nuclear Power Plants, with the selection process of sites and identification of geological and geotechnical parameters needed for the regional and local characterization of the area being studied, were incorporated. This dissertation also provides an aid to the writing of Technical Reports, which are part of the documentation an owner of a Nuclear Power Plant needs to submit to the Comissao Nacional de Energia Nuclear, to fulfill the nuclear installation licensing requirements. Moreover, this work can contribute to the planning of field and laboratory studies, needed to determine the parameters of the area under investigation, for the siting of Nuclear Power Plants. (Author) [pt

  3. Nuclear power plant site selection: a case study

    International Nuclear Information System (INIS)

    Lugasi, Y.; Mehrez, A.; Sinuany-Stern, Z.

    1985-01-01

    Selecting the site for a nuclear power plant involves the evaluation of numerous criteria and the professional judgment of various experts. The Israel Atomic Energy Commission has been concerned with the problem of selecting a site for a nuclear power station. Previous studies have been performed by the commission to identify potential sites. There were initial screenings where potential sites were chosen according to various minimal criteria and international standards. Only sites that met all the criteria were chosen. A study was made to find the most preferred site among the potential sites that met all the criteria. Two mathematical approaches were used: Keeney's multiattribute utility function and Saaty's eigenvalue prioritization technique. Both models ranked the same site as the most desirable; however, the models differed in their ranking of the other sites

  4. Trace of nuclear energy with pictures

    International Nuclear Information System (INIS)

    1992-05-01

    This book traces the history of development over nuclear energy with pictures, which contains preface, development history of the world, development history of Korea, nuclear power plant in Kori, nuclear power plant in Wolseong, nuclear power plant in Yeonggwang, nuclear power plant in Uljin, nuclear fuel, using of radiation and radioactive isotope, development of nuclear energy in the world and a Chronological table of nuclear energy. This book is written to record the development history of Korea through pictures of the nuclear power plants in Korea.

  5. Political aspects of nuclear test effects at Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Sydykov, E.B.; Panin, M.S.

    2003-01-01

    The paper describes tense struggle of Kazakhstan people for closure of the Semipalatinsk Nuclear Test Site. It reveals major foreign policy aspects and nuclear test effects for both Kazakhstan and the world community. (author)

  6. Site release in the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Revilla, Jose Luis; Sanz, Maria Teresa; Marugan, Inmaculada; Simon, Inmaculada; Martin, Manuel; Solis, Susana; Sterling, Agustina

    2008-01-01

    Spanish regulatory framework for the decommissioning process of a nuclear facility ends up with a decommission statement, which releases the licence-holder of the facility from its responsibilities as an operator. It also establishes -where a restricted site release applies- the appropriate future use restrictions, and the responsible of both maintaining such restrictions and ensuring their compliance. Releasing a site implies eliminating all radiological monitoring. The Regulations, however, did not specify either the radiological conditions to be met for the site to be released, or the possibility of a partial release -with or without restrictions-. In case of restricted site release, the Regulations did not specify either the required criteria for such a release. This paper presents the main features of the Safety Instruction IS-13 'Radiological criteria for the release of nuclear facilities sites' issued recently by the Spanish Nuclear Safety Council as a new specific regulation. This Safety Instruction establishes the requirements and conditions for the release of nuclear facility sites, that is, radiological criteria on the effective dose to the public, partial release of nuclear facility sites and restricted release of nuclear facility sites. (author).

  7. Argentinian experience in selecting sites for nuclear power stations

    International Nuclear Information System (INIS)

    Csik, B.J.

    1975-01-01

    One nuclear power station is in operation in the Republic of Argentina, a second is under construction, and the decision to build a third has been taken. According to existing plans, about ten nuclear power stations should go into operation during the next decade. The present paper analyses the experience acquired in selecting sites for the first units, commenting on the criteria and methods applied, the studies that were carried out, the specific problems encountered and the solutions adopted, as well as on the question of acceptance of the chosen sites by the public. It goes on to describe the current programme of selection and study of sites for future nuclear power stations

  8. Summary of wind data from nuclear power plant sites. [USA

    Energy Technology Data Exchange (ETDEWEB)

    Verholek, M. G.

    1977-03-01

    A summary of wind data from nuclear power plant sites is presented. National Weather Service archives are an immediately obvious source of wind data, but additional data sources are also available. Utility companies proposing to build nuclear power plants are required to establish on-site meteorological monitoring programs that include towers for collecting wind and temperature data for use in environmental impact assessments. These data are available for more than one hundred planned or operating nuclear power plant sites. A list of the sites, by state, is provided in Appendix A, while Appendix B contains an alphabetical list of the sites. This site wind data provides a valuable addition to the existing NWS data sets, and significantly enlarges the multilevel data presently available. The wind data published through the NRC is assembled and assessed here in order to provide a supplement to existing data sets.

  9. Method for assigning sites to projected generic nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Holter, G.M.; Purcell, W.L.; Shutz, M.E.; Young, J.R.

    1986-07-01

    Pacific Northwest Laboratory developed a method for forecasting potential locations and startup sequences of nuclear power plants that will be required in the future but have not yet been specifically identified by electric utilities. Use of the method results in numerical ratings for potential nuclear power plant sites located in each of the 10 federal energy regions. The rating for each potential site is obtained from numerical factors assigned to each of 5 primary siting characteristics: (1) cooling water availability, (2) site land area, (3) power transmission land area, (4) proximity to metropolitan areas, and (5) utility plans for the site. The sequence of plant startups in each federal energy region is obtained by use of the numerical ratings and the forecasts of generic nuclear power plant startups obtained from the EIA Middle Case electricity forecast. Sites are assigned to generic plants in chronological order according to startup date.

  10. Method for assigning sites to projected generic nuclear power plants

    International Nuclear Information System (INIS)

    Holter, G.M.; Purcell, W.L.; Shutz, M.E.; Young, J.R.

    1986-07-01

    Pacific Northwest Laboratory developed a method for forecasting potential locations and startup sequences of nuclear power plants that will be required in the future but have not yet been specifically identified by electric utilities. Use of the method results in numerical ratings for potential nuclear power plant sites located in each of the 10 federal energy regions. The rating for each potential site is obtained from numerical factors assigned to each of 5 primary siting characteristics: (1) cooling water availability, (2) site land area, (3) power transmission land area, (4) proximity to metropolitan areas, and (5) utility plans for the site. The sequence of plant startups in each federal energy region is obtained by use of the numerical ratings and the forecasts of generic nuclear power plant startups obtained from the EIA Middle Case electricity forecast. Sites are assigned to generic plants in chronological order according to startup date

  11. Penetration Testing Model for Web sites Hosted in Nuclear Malaysia

    International Nuclear Information System (INIS)

    Mohd Dzul Aiman Aslan; Mohamad Safuan Sulaiman; Siti Nurbahyah Hamdan; Saaidi Ismail; Mohd Fauzi Haris; Norzalina Nasiruddin; Raja Murzaferi Mokhtar

    2012-01-01

    Nuclear Malaysia web sites has been very crucial in providing important and useful information and services to the clients as well as the users worldwide. Furthermore, a web site is important as it reflects the organisation image. To ensure the integrity of the content of web site, a study has been made and a penetration testing model has been implemented to test the security of several web sites hosted at Nuclear Malaysia for malicious attempts. This study will explain how the security was tested in the detailed condition and measured. The result determined the security level and the vulnerability of several web sites. This result is important for improving and hardening the security of web sites in Nuclear Malaysia. (author)

  12. Site response calculations for nuclear power plants

    International Nuclear Information System (INIS)

    Wight, L.H.

    1975-01-01

    Six typical sites consisting of three soil profiles with average shear wave velocities of 800, 1800, and 5000 ft/sec as well as two soil depths of 200 and 400 ft were considered. Seismic input to these sites was a synthetic accelerogram applied at the surface and corresponding to a statistically representative response spectrum. The response of each of these six sites to this input was calculated with the SHAKE program. The results of these calculations are presented

  13. Database on radioecological situation in Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Turkebaev, T.Eh.; Kislitsin, S.B.; Lopuga, A.D.; Kuketaev, A.T.; Kikkarin, S.M.

    1999-01-01

    One of the main objectives of the National Nuclear Center of the Republic of Kazakstan is to define radioecological situation in details, conduct a continuous monitoring and eliminate consequences of nuclear explosions at Semipalatinsk nuclear test site. Investigations of Semipalatinsk nuclear test site area contamination by radioactive substances and vindication activity are the reasons for development of computer database on radioecological situation of the test site area, which will allow arranging and processing the available and entering information about the radioecological situation, assessing the effect of different testing factors on the environment and health of the Semipalatinsk nuclear test site area population.The described conception of database on radioecological situation of the Semipalatinsk nuclear test site area cannot be considered as the final one. As new information arrives, structure and content of the database is updated and optimized. New capabilities and structural elements may be provided if new aspects in Semipalatinsk nuclear test site area contamination study (air environment study, radionuclides migration) arise

  14. American National Standard: guidelines for evaluating site-related geotechnical parameters at nuclear power sites

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    This standard presents guidelines for evaluating site-related geotechnical parameters for nuclear power sites. Aspects considered include geology, ground water, foundation engineering, and earthwork engineering. These guidelines identify the basic geotechnical parameters to be considered in site evaluation, and in the design, construction, and performance of foundations and earthwork aspects for nuclear power plants. Also included are tabulations of typical field and laboratory investigative methods useful in identifying geotechnical parameters. Those areas where interrelationships with other standards may exist are indicated

  15. Risk assessment for nuclear processes at the Savannah River Site

    International Nuclear Information System (INIS)

    Durant, W.S.

    1992-01-01

    The Savannah River Site, one of the US Department of Energy's nuclear materials processing facilities, has for many years conducted risk-based safety analyses for the nuclear processes conducted at the facilities. This approach has allowed comparisons of risks to established criteria for acceptability. When the risk-based program was begun, it was evident that its success would depend upon having a compilation of data that was site specific. The decision was made to create a data bank of undesirable events that had occurred at the site's nuclear fuel reprocessing facilities. From this modest beginning, five data banks have been created for nuclear fuel reprocessing, waste management, nuclear fuel fabrication, tritium operations, and the Savannah River Technology Center. In addition to the primary purpose of providing a sound basis for risk-based safety analyses, these highly versatile data banks are routinely used for equipment breakdown histories, incident investigations, design studies, project justifications, reliability studies, process problem solving, training, and audits

  16. Code on the safety of nuclear power plants: Siting

    International Nuclear Information System (INIS)

    1988-01-01

    This Code provides criteria and procedures that are recommended for safety in nuclear power plant siting. It forms part of the Agency's programme for establishing Codes and Safety Guides relating to land based stationary thermal neutron power plants

  17. Construction plant requirements for nuclear sites

    International Nuclear Information System (INIS)

    Tatum, C.B.; Harris, J.A.

    1981-01-01

    Planning and developing the temporary construction plant facilities for a nuclear project is equivalent to providing utility services for a small city. Provision of adequate facilities is an important factor in the productivity of both the manual and non-manual work force. This paper summarizes construction facility requirements for a two unit (1300 MWe each) nuclear project. Civil, mechanical and electrical facilities are described, including design, installation and operation. Assignment of responsibility for specific work tasks regarding the construction plant is also discussed. In presenting this data, the authors seek to transfer experience and assist in the provision of adequate facilities on future projects

  18. A future for nuclear sites beyond their service life. Nuclear site value development; Un avenir pour les sites nucleaires en fin de cycle. Valorisation des sites nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites

  19. Safety criteria for siting a nuclear power plant

    International Nuclear Information System (INIS)

    2001-01-01

    The guide sets forth requirements for safety of the population and the environment in nuclear power plant siting. It also sets out the general basis for procedures employed by other competent authorities when they issue regulations or grant licences. On request STUK (Radiation and Nuclear Safety Authority of Finland) issues case-specific statements about matters relating to planning and about other matters relating to land use in the environment of nuclear power plants

  20. The role of economic incentives in nuclear waste facility siting

    International Nuclear Information System (INIS)

    Davis, E.M.

    1986-01-01

    There is a need to provide some public benefit and/or reward for accepting a ''locally unwanted land use'' (LULU) facility such as a nuclear waste storage or disposal facility. This paper concludes that DOE, Congress and the states should immediately quantify an economic incentive for consideration ''up front'' by society on siting decisions for nuclear waste storage and disposal facilities

  1. Site selection and evaluation of nuclear power units in Egypt

    International Nuclear Information System (INIS)

    Bonnefille, R.

    1980-01-01

    The selection of sites for nuclear power units in Egypt by SOFRATOME for Nuclear Plants Authority is carried on using a method based on interaction between different criteria. The method and the main results on criterion 'radio-ecological impact' are sketched briefly [fr

  2. Expansion potential for existing nuclear power station sites

    Energy Technology Data Exchange (ETDEWEB)

    Cope, D. F.; Bauman, H. F.

    1977-09-26

    This report is a preliminary analysis of the expansion potential of the existing nuclear power sites, in particular their potential for development into nuclear energy centers (NECs) of 10 (GW(e) or greater. The analysis is based primarily on matching the most important physical characteristics of a site against the dominating site criteria. Sites reviewed consist mainly of those in the 1974 through 1976 ERDA Nuclear Power Stations listings without regard to the present status of reactor construction plans. Also a small number of potential NEC sites that are not associated with existing power stations were reviewed. Each site was categorized in terms of its potential as: a dispersed site of 5 GW(e) or less; a mini-NEC of 5 to 10 GW(e); NECs of 10 to 20 GW(e); and large NECs of more than 20 GW(e). The sites were categorized on their ultimate potential without regard to political considerations that might restrain their development. The analysis indicates that nearly 40 percent of existing sites have potential for expansion to nuclear energy centers.

  3. Expansion potential for existing nuclear power station sites

    International Nuclear Information System (INIS)

    Cope, D.F.; Bauman, H.F.

    1977-01-01

    This report is a preliminary analysis of the expansion potential of the existing nuclear power sites, in particular their potential for development into nuclear energy centers (NECs) of 10 (GW(e) or greater. The analysis is based primarily on matching the most important physical characteristics of a site against the dominating site criteria. Sites reviewed consist mainly of those in the 1974 through 1976 ERDA Nuclear Power Stations listings without regard to the present status of reactor construction plans. Also a small number of potential NEC sites that are not associated with existing power stations were reviewed. Each site was categorized in terms of its potential as: a dispersed site of 5 GW(e) or less; a mini-NEC of 5 to 10 GW(e); NECs of 10 to 20 GW(e); and large NECs of more than 20 GW(e). The sites were categorized on their ultimate potential without regard to political considerations that might restrain their development. The analysis indicates that nearly 40 percent of existing sites have potential for expansion to nuclear energy centers

  4. Public reactions to nuclear waste: Citizens' views of repository siting

    International Nuclear Information System (INIS)

    Rosa, E.A.

    1993-01-01

    This book presents revised and updated papers from a panel of social scientists, at the 1989 AAAS meetings, that examined the public's reactions to nuclear waste disposal and the repository siting process. The papers report the results of original empirical research on citizens' views of nuclear waste repository siting. Topics covered include the following: content analysis of public testimony; sources of public concern about nuclear waste disposal in Texas agricultural communities; local attitudes toward high-level waste repository at Hanford; perceived risk and attitudes toward nuclear wastes; attitudes of Nevada urban residents toward a nuclear waste repository; attitudes of rural community residents toward a nuclear waste respository. An introductory chapter provides background and context, and a concluding chapter summarizes the implications of the reports. Two additional chapters cover important features of high-level waste disposal: long term trends in public attitudes toward nuclear energy and nuclear waste policy and assessment of the effects on the Los Vegas convention business if a high-level nuclear waste depository were sited in Nevada

  5. Site selection - siting of the final repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    2011-03-01

    SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

  6. Site selection - siting of the final repository for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    2011-03-15

    SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection is the end result of an extensive siting process that began in the early 1990s. The strategy and plan for the work was based on experience from investigations and development work over a period of more than ten years prior to then. This document describes the siting work and SKB's choice of site for the final repository. It also presents the information on which the choice was based and the reasons for the decisions made along the way. The document comprises Appendix PV to applications under the Nuclear Activities Act and the Environmental Code for licences to build and operate an encapsulation plant adjacent to the central interim storage facility for spent nuclear fuel in Oskarshamn, and to build and operate a final repository for spent nuclear fuel in Forsmark in Oesthammar Municipality

  7. Land contamination. Technical guidance on special sites: nuclear sites

    International Nuclear Information System (INIS)

    Hill, M.; Steeds, J.; Slade, N.

    2001-01-01

    Part IIA of the Environmental Protection Act 1990 sets out a regulatory regime for the identification and remediation of land where contamination is causing unacceptable risks to defined receptors. The Environment Agency has a number of regulatory roles under this regime. Where land is designated as a Special Site, as defined in the Contaminated Land (England) Regulations 2000, the Agency will act as the enforcing authority. It is expected that a similar regime will be introduced in Wales during 2001, but the reader should check whether definitions of Special Sites in the Welsh regulations are the same as in the English ones. The Environment Agency's approach to carrying out its regulatory responsibilities is set out in its Part RA Process Documentation,, available on the Agency website (www.environment-agency. gov.uk). This documentation sets out how the Agency intends to carry out its responsibilities under Part IIA of the Environmental Protection Act 1990, which came into force in England on 1 April 2000

  8. Optimal Procedure for siting of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Aziuddin, Khairiah Binti; Park, Seo Yeon; Roh, Myung Sub

    2013-01-01

    This study discusses on a simulation approach for sensitivity analysis of the weights of multi-criteria decision models. The simulation procedures can also be used to aid the actual decision process, particularly when the task is to select a subset of superior alternatives. This study is to identify the criteria or parameters which are sensitive to the weighting factor that can affect the results in the decision making process to determine the optimal site for nuclear power plant (NPP) site. To perform this study, we adhere to IAEA NS-R-3 and DS 433. The siting process for nuclear installation consists of site survey and site selection stages. The siting process generally consists of an investigation of a large region to select one or more candidate sites by surveying the sites. After comparing the ROI, two candidate sites are compared for final determination, which are Wolsong and Kori site. Some assumptions are taken into consideration due to limitations and constraints throughout performing this study. Sensitivity analysis of multi criteria decision models is performed in this study to determine the optimal site in the site selection stage. Logical Decisions software will be employed as a tool to perform this analysis. Logical Decisions software helps to formulate the preferences and then rank the alternatives. It provides clarification of the rankings and hence aids the decision makers on evaluating the alternatives, and finally draw a conclusion on the selection of the optimal site

  9. Optimal Procedure for siting of Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Aziuddin, Khairiah Binti; Park, Seo Yeon; Roh, Myung Sub [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2013-10-15

    This study discusses on a simulation approach for sensitivity analysis of the weights of multi-criteria decision models. The simulation procedures can also be used to aid the actual decision process, particularly when the task is to select a subset of superior alternatives. This study is to identify the criteria or parameters which are sensitive to the weighting factor that can affect the results in the decision making process to determine the optimal site for nuclear power plant (NPP) site. To perform this study, we adhere to IAEA NS-R-3 and DS 433. The siting process for nuclear installation consists of site survey and site selection stages. The siting process generally consists of an investigation of a large region to select one or more candidate sites by surveying the sites. After comparing the ROI, two candidate sites are compared for final determination, which are Wolsong and Kori site. Some assumptions are taken into consideration due to limitations and constraints throughout performing this study. Sensitivity analysis of multi criteria decision models is performed in this study to determine the optimal site in the site selection stage. Logical Decisions software will be employed as a tool to perform this analysis. Logical Decisions software helps to formulate the preferences and then rank the alternatives. It provides clarification of the rankings and hence aids the decision makers on evaluating the alternatives, and finally draw a conclusion on the selection of the optimal site.

  10. Quality assurance in siting of Nuclear Power Plants

    International Nuclear Information System (INIS)

    2005-03-01

    This guide describes the requirements of quality assurance programme (QAP) that need to be implemented at the siting stage, by the organisation having overall responsibility for the nuclear power plant. The scope of the guide covers the quality assurance aspects related to management, performance and assessment activities during siting stage of NPPs

  11. Evaluation of vibratory ground motion at nuclear power plant sites

    International Nuclear Information System (INIS)

    Hofmann, R.B.; Greeves, J.T.

    1978-01-01

    The evaluation of vibratory ground motion at nuclear power plant sites requires the cooperative effort of scientists and engineers in several disciplines. These include seismology, geology, geotechnical engineering and structural engineering. The Geosciences Branch of the NRC Division of Site Safety and Environmental Analysis includes two sections, the Geology/Seismology Section and the Geotechnical Engineering Section

  12. Regulatory Aspects for Site Selection for Radiological and Nuclear Installations

    International Nuclear Information System (INIS)

    Sirag, N.M.

    2016-01-01

    The purpose of this research is to check in one of the considerations necessary for any new nuclear facility. A previous study that was conducted using a questionnaire reported that general admission to the public, aesthetic considerations, and characteristics associated with the site are able to adequately accept the existence of new nuclear facilities. The findings of this research revealed that public involvement in the process of site selection and in the design of nuclear power plants, an understanding of their point of view is an important aspect of a participatory approach. An important factor for any new nuclear program is to improve confidence in the energy choices in the future. A survey was conducted on 1304 adults to, to get the main goal. The study concluded showed that the prevalence of culture of safety reflected on the public acceptance of the site, especially if it takes into account the aesthetic and environmental considerations.

  13. Nuclear architecture and landscape: the power plant creates the site

    International Nuclear Information System (INIS)

    Parent, Claude; Bouvier, Yves

    2005-01-01

    The implementation, from 1974, of the French nuclear programme, was associated with an 'Architecture Plan' requested by Michel Hug, Equipment Manager at power utility EDF. The objective was to create an architecture language specific to nuclear power. Far from trying to hide the nuclear power stations, the nuclear architecture college conversely designed one set of ambitious and powerful shapes. Systematically associated to one landscape and to one colourist, the architect sought to use in the best possible way the potentialities available on one site. The power station should not blend in with the landscape, but on the contrary, participate in the creation of a fresh landscape

  14. Demographic statistics pertaining to nuclear power reactor sites

    International Nuclear Information System (INIS)

    1979-10-01

    Population statistics are presented for 145 nuclear power plant sites. Summary tables and figures are included that were developed to aid in the evaluation of trends and general patterns associated with the various parameters of interest, such as the proximity of nuclear plant sites to centers of population. The primary reason for publishing this information at this time is to provide a factual basis for use in discussions on the subject of reactor siting policy. The report is a revised and updated version of a draft report published in December 1977. Errors in the population data base have been corrected and new data tabulations added

  15. An integrated approach to site selection for nuclear power plants

    International Nuclear Information System (INIS)

    Hassan, E.M.A.

    1975-01-01

    A method of analysing and evaluating the large number of factors influencing site selection is proposed, which can interrelate these factors and associated problems in an integrated way and at the same time establish a technique for site evaluation. The objective is to develop an integrated programme that illustrates the complexity and dynamic interrelationships of the various factors to develop an improved understanding of the functions and objectives of siting nuclear power plants and would aim finally at the development of an effective procedure and technique for site evaluation and/or comparative evaluation for making rational site-selection decisions. (author)

  16. Ecological and radioecological studies of nuclear installation sites

    International Nuclear Information System (INIS)

    Caries, J. C.; Hugon, J.; Grauby, A.

    1988-01-01

    The site study method consists of a dynamic and estimated analysis and of following up the release impact on all natural or non natural media compartments that take a part in the protection of man and his environment. The stages of knowing a nuclear site include the site preliminary radioecological evaluation, diffusion parameters evaluation, the quantification of factors of radioelements transfer to man, the ecological baseline carrying out, the radioactive baseline establishment, the radioecological synthesis of the results, the site radioactive and ecological control. This method applys to selection and detailed study of site. 1 tab., 7 refs. (F.M.)

  17. Nuclear Energy Center Site Survey, 1975. Part III. Technical considerations

    International Nuclear Information System (INIS)

    1976-01-01

    Studies of the technical feasibility of nuclear energy centers (NECs) and the comparison between NEC technical feasibility and that of nuclear facilities on dispersed sites are reviewed. The conclusions related to technical feasibility of NEC are summarized. Technical feasibility was found to rest mainly on five major issues: heat dissipation, transmission, facility construction, radiological impact, and environmental impact. Although general conclusions can be reached in these five areas, it is recognized that they are interdependent, and detailed site-by-site analysis will be necessary. Some general conclusions on technical feasibility of NECs are presented, then detailed conclusions derived from the technical evaluation of NECs compared to dispersed site facilities are presented. The findings of this study on each of the five major feasibility issues are then discussed in sequence. The study concludes that nuclear energy centers, as defined herein, are technically feasible

  18. Nuclear Energy Center Site Survey, 1975. Executive summary

    International Nuclear Information System (INIS)

    1976-01-01

    The Nuclear Energy Center Site Survey is a study of a potential alternative siting approach for nuclear power and fuel-cycle facilities, an approach that would cluster sizable groups of such facilities on a relatively small number of sites. The largest aggregation of reactors on a single site being planned today is four, and this quad is assumed (for comparative study purposes) to be the typical dispersed site by the year 2000. Three basic types of nuclear energy centers are considered: power-plant centers, consisting of 10 to 40 nuclear electric generating units of 1200-megawatt electric capacity each; fuel-cycle centers, consisting of fuel reprocessing plants, mixed-oxide fuel fabrication facilities, and radioactive waste management facilities; and combined centers, containing both power plants and fuel-cycle facilities. The results of the general site-location screening efforts are shown on a United States map that shows the locations of large areas identified as likely to contain suitable candidate sites for power NECs, on the basis of four coarse screening criteria: water resources, seismic activity, population density, and statutory excluded lands

  19. Nuclear Energy Center Site Survey, 1975. Part V. Resource availability and site screening

    International Nuclear Information System (INIS)

    1976-01-01

    Resource requirements for nuclear energy centers are discussed and the large land areas which meet these requirements and may contain potential sites for a nuclear energy center (NEC) are identified. Maps of the areas are included that identify seismic zones, river flow rates, and population density

  20. Overview of clustered nuclear siting and its technical aspects

    International Nuclear Information System (INIS)

    Meier, P.M.

    1976-09-01

    In recent years there has been growing discussion over the ability of new siting approaches to redress the increasing problems of nuclear plant location. This debate has focused largely on three alternatives to the conventional siting of nuclear reactors; floating offshore plants; underground siting; and nuclear energy centers (NECs) consisting of up to 40 reactors at a single site, and, possibly, including fuel cycle facilities within their perimeter. Congressional interest in energy centers, especially in view of concern over the proliferation of nuclear reactors throughout the country, and with the special problems of safeguards over fuel reprocessing and the use of plutonium as a reactor fuel, resulted in a mandate to the Nuclear Regulatory Commission to make a comprehensive analysis of the energy center concept. A common finding of all of the studies of the nuclear energy center concept thus far is that there appear to be no technical considerations that would clearly preclude energy centers. With the one significant exception regarding the meteorological impacts of the concentration of heat and moisture releases to the atmosphere, engineering solutions would appear to be quite adequate to address any difficulties of environmental impact, electrical systems management, water supply or construction management, and to keep the overall physical environmental impact of an energy center not significantly different to that of an equivalent number of dispersed reactors

  1. Conflict, location, and politics: Siting a nuclear waste repository

    International Nuclear Information System (INIS)

    Jacob, G.R.

    1988-01-01

    Nuclear power and the management of high-level radioactive waste is examined with the goal of explaining the forces driving the formulation of the 1982 Nuclear Waste Policy Act and a subsequent decision to site a nuclear waste repository at Yucca Mountain, Nevada. The study draws upon geographic, political, economic, and organizational factors to examine the commitment to dispose of spent fuel in a geologic repository located in Nevada or in Utah, Texas, Mississippi, Louisiana, or at Hanford Washington. Special attention is given to the impact of location, science and technology on the definition of the nuclear waste problem and political agendas, public participation, and the power of the nuclear establishment. The study finds that the choice of a Yucca Mountain Nevada as the preferred site for a repository was based more on technological precedent and political-economic expediency than on the demonstrated superiority of that site's geology. Conflict over a repository location is interpreted as a symptom of more fundamental conflicts concerning: the credibility of nuclear science, the legitimacy of federal authority and administration, and the priorities of environmental protection and a nuclear economy

  2. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Massaro, Lawrence M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditions relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.

  3. Working together with regulators on nuclear sites

    International Nuclear Information System (INIS)

    Holloway, N.J.

    2004-01-01

    A scheme for earlier and clearer communications with the Health and Safety Executive (HSE) and the Environment Agency (EA) on jointly regulated issues has been developed across the nuclear industry over the past two years. The matched pair of industry and regulators' 'Working Together' documents was published in January 2003. In the United Kingdom Atomic Energy Authority (UKAEA), the scheme is being put into practice through the issue of Initial Regulatory Notifications (IRN) of various projects and issues, to capture key regulatory topics and prompt regulators' initial responses. The IRN may be based on a safety and environment overview report or may be a precursor to it. Positive responses, in line with the Working Together documents, were received from HSE and the EA, following receipt of the first three UKAEA IRNs. (author)

  4. Preparation of site emergency preparedness plans for nuclear installations

    International Nuclear Information System (INIS)

    1999-10-01

    Safety of public, occupational workers and the protection of environment should be assured while activities for economic and social progress are pursued. These activities include the establishment and utilisation of nuclear facilities and use of radioactive sources. This safety guidelines is issued as a lead document to facilitate preparation of specific site manuals by the responsible organisation for emergency response plans at each site to ensure their preparedness to meet any eventuality due to site emergency in order to mitigate its consequences on the health and safety of site personnel. It takes cognizance of an earlier AERB publications on the subject: Safety manual on site emergency plan on nuclear installations. AERB/SM/NISD-1, 1986 and also takes into consideration the urgent need for promoting public awareness and drawing up revised emergency response plans, which has come about in a significant manner after the accidents at Chernobyl and Bhopal

  5. Volcanic Hazards in Site Evaluation for Nuclear Installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-10-15

    This publication provides comprehensive and updated guidance for site evaluation in relation to volcanic hazards. It includes recommendations on assessing the volcanic hazards at a nuclear installation site, in order to identify and characterize, in a comprehensive manner, all potentially hazardous phenomena that may be associated with future volcanic events. It describes how some of these volcanic phenomena may affect the acceptability of the selected site, resulting in exclusion of a site or determining the corresponding design basis parameters for the installation. This Safety Guide is applicable to both existing and new sites, and a graded approach is recommended to cater for all types of nuclear installations. Contents: 1. Introduction; 2. Overview of volcanic hazard assessment; 3. General recommendations; 4. Necessary information and investigations (database); 5. Screening of volcanic hazards; 6. Site specific volcanic hazard assessment; 7. Nuclear installations other than nuclear power plants; 8. Monitoring and preparation for response; 9. Management system for volcanic hazard assessment; Annex I: Volcanic hazard scenarios; Annex II: Worldwide sources of information.

  6. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Fermi Research Alliance (FRA), Batavia, IL (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power plant sites was performed. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: Characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory A description of the on-site infrastructure at the shutdown sites An evaluation of the near-site transportation infrastructure and transportation experience at the shutdown sites An evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. The primary sources for the inventory of SNF and GTCC waste were the U.S. Department of Energy (DOE) spent nuclear fuel inventory database, industry publications such as StoreFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of on-site infrastructure and near-site transportation infrastructure and experience included information collected during site visits, information provided by managers at the shutdown sites, Facility Interface Data Sheets compiled for DOE in 2005, Services Planning Documents prepared for DOE in 1993 and 1994, industry publications such as Radwaste Solutions, and Google Earth. State staff, State Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative have participated in nine of the shutdown site visits. Every shutdown site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an

  7. Delegated Democracy. The Siting of Swedish Nuclear Waste

    Energy Technology Data Exchange (ETDEWEB)

    Johansson, Hanna Sofia (Stockholm Univ., SCORE, SE-106 91 Stockholm (Sweden))

    2009-12-15

    This paper aims to characterise Swedish democracy in connection with the disposal of Swedish nuclear waste. To this end, an analysis is performed to discern which democratic ideals that can be found within the nuclear waste issue. The study analyses various actors' views on democracy and expertise as well as their definitions of the nuclear waste issue, and discusses this from the perspective of democracy theory. Which definitions that become influential has democratic implications. In addition, various actors' possible attempts to help or hinder other actors from gaining influence over the nuclear waste issue in the four municipalities are studied. In connection with the case studies the aim of the paper can be narrowed to comprise the following questions: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? Which democratic ideals were influential during the feasibility studies and in the consultation process?

  8. Integrated planning for nuclear siting - The South African experience

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, J C.A.; Heidstra, N; Graupner, O F [Eskom, Johannesburg (South Africa); Hambleton-Jones, B [Atomic Energy Corporation of South Africa Ltd., Pellindaba, Pretoria (South Africa)

    1990-06-01

    This paper describes the process involved in the current national programme to identify potential sites for nuclear power development in South Africa. A description is given of the sensitivity studies - the evaluation of the potential perturbations to and opportunities for the biophysical and socioeconomic environments and the suitability studies - the evaluation of environmental influences on geotechnical, safety and financial considerations. This programme is divorced from any decision of whether or not to build further nuclear power station in South Africa. The programme described is a long range land-use planning exercise considered expedient in the face of competition for land that share similar requirements as those of nuclear power station sites. It is also designed to streamline nuclear power station lead times and to make national and regional planners aware of Eskom's requirements in the drafting of their policies and plans. (author)

  9. Integrated planning for nuclear siting - The South African experience

    International Nuclear Information System (INIS)

    Hobbs, J.C.A.; Heidstra, N.; Graupner, O.F.; Hambleton-Jones, B.

    1990-01-01

    This paper describes the process involved in the current national programme to identify potential sites for nuclear power development in South Africa. A description is given of the sensitivity studies - the evaluation of the potential perturbations to and opportunities for the biophysical and socioeconomic environments and the suitability studies - the evaluation of environmental influences on geotechnical, safety and financial considerations. This programme is divorced from any decision of whether or not to build further nuclear power station in South Africa. The programme described is a long range land-use planning exercise considered expedient in the face of competition for land that share similar requirements as those of nuclear power station sites. It is also designed to streamline nuclear power station lead times and to make national and regional planners aware of Eskom's requirements in the drafting of their policies and plans. (author)

  10. Delegated Democracy. The Siting of Swedish Nuclear Waste

    International Nuclear Information System (INIS)

    Johansson, Hanna Sofia

    2009-12-01

    This paper aims to characterise Swedish democracy in connection with the disposal of Swedish nuclear waste. To this end, an analysis is performed to discern which democratic ideals that can be found within the nuclear waste issue. The study analyses various actors' views on democracy and expertise as well as their definitions of the nuclear waste issue, and discusses this from the perspective of democracy theory. Which definitions that become influential has democratic implications. In addition, various actors' possible attempts to help or hinder other actors from gaining influence over the nuclear waste issue in the four municipalities are studied. In connection with the case studies the aim of the paper can be narrowed to comprise the following questions: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? Which democratic ideals were influential during the feasibility studies and in the consultation process?

  11. War protected underground siting of nuclear power plants -a summary

    International Nuclear Information System (INIS)

    1974-06-01

    In connection with studies concerning the need of war protected nuclear power production the technical and economical conditions with war protection of nuclear power plants have been studied within CDL. Comprehensively one have shown that no technical construction obstacles for siting a nuclear power plant underground exist that the additional costs for underground siting with price level mid 1973 are some 175-250 MSwCr (In today's price level 250 MSwCr will probably correspond to some 300 MSwCr per unit) and that the construction time is some one year longer than for an above ground plant. A study ought to examine more closely the consequences of underground siting from a radiological point of view and what demands on that occasion ought to be put on the technical design. (author)

  12. Safety in nuclear power plant siting. A code of practice

    International Nuclear Information System (INIS)

    1978-01-01

    This publication is brought out within the framework of establishing Codes of Practice and Safety Guides for nuclear power plants: NUSS programme. The scope of the document encompasses site and site-plant interaction factors related to operational states and accident conditions. The purpose of the Code is to give criteria and procedures to be applied as appropriate to operational states and accident conditions, including those which could lead to emergency situations. This Code is mainly concerned with severe events of low probability which relate to the siting of nuclear power plants and have to be considered in designing a particular nuclear power plant. Annex: Examples of natural and man-made events relevant for design basis evaluation

  13. Nuclear Power Plant project site selection geotechnical considerations

    International Nuclear Information System (INIS)

    Katti, V.J.; Banerjee, D.C.

    1997-01-01

    During the selection of a site for Nuclear Power Plant (NPP) and Radioactive Waste Plant (RWP), geotechnical investigations play a significant role in deciding merits and demerits of the sites. Any accidents in these units can play havoc on mankind and may leave bitter imprints on generations to come. Hence proper care has to be taken at the early stage for selecting the sites. Site selection procedure is a complicated one, because it involves experts from various disciplines like geology, geophysics, civil, mechanical electrical engineering, health-physics and other fields

  14. Risk analysis and solving the nuclear waste siting problem

    International Nuclear Information System (INIS)

    Inhaber, H.

    1993-01-01

    In spite of millions of dollars and countless human resources being expended on finding nuclear wastes sites, the search has proved extremely difficult for the nuclear industry. This may be due to the approach followed, rather than inadequacies in research or funding. A new approach to the problem, the reverse Dutch auction, is suggested. It retains some of the useful elements of the present system, but it also adds new ones

  15. Risk analysis and solving the nuclear waste siting problem

    Energy Technology Data Exchange (ETDEWEB)

    Inhaber, H.

    1993-12-01

    In spite of millions of dollars and countless human resources being expended on finding nuclear wastes sites, the search has proved extremely difficult for the nuclear industry. This may be due to the approach followed, rather than inadequacies in research or funding. A new approach to the problem, the reverse Dutch auction, is suggested. It retains some of the useful elements of the present system, but it also adds new ones.

  16. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Federal Railroad Administration (FRA) (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-10-01

    This report presents a preliminary evaluation of removing used nuclear fuel (UNF) from 12 shutdown nuclear power plant sites. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites are Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. The evaluation was divided into four components: characterization of the UNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory; a description of the on-site infrastructure and conditions relevant to transportation of UNF and GTCC waste; an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing UNF and GTCC waste, including identification of gaps in information; and, an evaluation of the actions necessary to prepare for and remove UNF and GTCC waste. The primary sources for the inventory of UNF and GTCC waste are the U.S. Department of Energy (DOE) RW-859 used nuclear fuel inventory database, industry sources such as StoreFUEL and SpentFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of site and near-site transportation infrastructure and experience included observations and information collected during visits to the Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion sites; information provided by managers at the shutdown sites; Facility Interface Data Sheets compiled for DOE in 2005; Services Planning Documents prepared for DOE in 1993 and 1994; industry publications such as Radwaste Solutions; and Google Earth. State and Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative participated in six of the shutdown site

  17. Case study of siting technology for underground nuclear power plant

    International Nuclear Information System (INIS)

    Hibino, Satoshi; Komada, Hiroya; Honsho, Shizumitsu; Fujiwara, Yoshikazu; Motojima, Mutsumi; Nakagawa, Kameichiro; Nosaki, Takashi

    1991-01-01

    Underground siting method is one of new feasible siting methods for nuclear power plants. This report presents the results on case studies on underground siting. Two sites of a steeply inclined and plateau like configurations were selected. 'Tunnel type cavern; all underground siting' method was applied for the steeply inclined configuration, and 'shaft type semi-cavern; partial underground siting' method was applied for the plateau like configuration. The following designs were carried out for these two sites as case studies; (1) conceptual designs, (2) geological surveys and rock mechanics tests, (3) stability analysis during cavern excavations, (4) seismic stability analysis of caverns during earthquake, (5) reinforcement designs for caverns, (6) drainage designs. The case studies showed that these two cases were fully feasible, and comparison between two cases revealed that the 'shaft type semi-cavern; partial underground siting' method was more suitable for Japanese islands. As a first step of underground siting, therefore, the authors recommend to construct a nuclear power plant by this method. (author)

  18. Site selection for nuclear power plants and geologic seismologia influence

    International Nuclear Information System (INIS)

    Castro Feitosa, G. de.

    1985-01-01

    The site selection for nuclear power plants is analised concerning to the process, methodology and the phases in an overall project efforts. The factors affecting are analised on a general viewpoint, showing the considerations given to every one. The geologic and seismologic factors influence on the foundation design are more detailed analised, with required investigation and procedures accordingly sub-soil conditions in the site [pt

  19. Underground siting of nuclear power plants: potential benefits and penalties

    International Nuclear Information System (INIS)

    Allensworth, J.A.; Finger, J.T.; Milloy, J.A.; Murfin, W.B.; Rodeman, R.; Vandevender, S.G.

    1977-08-01

    The potential for improving nuclear power safety is analyzed by siting plants underground in mined cavities or by covering plants with fill earth after construction in an excavated cut. Potential benefits and penalties of underground plants are referenced to analogous plants located on the surface. Three representative regional sites having requisite underground geology were used to evaluate underground siting. The major factors which were evaluated for all three sites were: (1) containment of radioactive materials, (2) transport of groundwater contamination, and (3) seismic vulnerability. External protection, plant security, feasibility, operational considerations, and cost were evaluated on a generic basis. Additionally, the national availability of sites having the requisite geology for both underground siting concepts was determined

  20. Seismic Hazard Assessment in Site Evaluation for Nuclear Installations: Ground Motion Prediction Equations and Site Response

    International Nuclear Information System (INIS)

    2016-07-01

    The objective of this publication is to provide the state-of-the-art practice and detailed technical elements related to ground motion evaluation by ground motion prediction equations (GMPEs) and site response in the context of seismic hazard assessments as recommended in IAEA Safety Standards Series No. SSG-9, Seismic Hazards in Site Evaluation for Nuclear Installations. The publication includes the basics of GMPEs, ground motion simulation, selection and adjustment of GMPEs, site characterization, and modelling of site response in order to improve seismic hazard assessment. The text aims at delineating the most important aspects of these topics (including current practices, criticalities and open problems) within a coherent framework. In particular, attention has been devoted to filling conceptual gaps. It is written as a reference text for trained users who are responsible for planning preparatory seismic hazard analyses for siting of all nuclear installations and/or providing constraints for anti-seismic design and retrofitting of existing structures

  1. The Approach to Cleanup at West Cumbria's Nuclear Sites

    International Nuclear Information System (INIS)

    Price, T.

    2006-01-01

    The cleanup of West Cumbria's nuclear sites is one of the most important and demanding managerial, technical and environmental challenges facing the UK over the next century. Considerable progress has already been made in cleaning up the Sellafield, Calder Hall, and Low-level Waste Repository (LLWR) sites but there remains significant challenge ahead. There are more than 200 nuclear facilities at the sites including redundant fuel storage ponds, redundant chemical plants and silos of solid waste and sludge. These legacy buildings exist alongside commercially operating reprocessing and fuel fabrication facilities. They are all linked together by a complex network of services including gas supplies, water supplies, waste disposal routes, and chemical supply routes. Many of the buildings requiring cleanup are very old and date back to the early years of the British nuclear industry. They were not designed with decommissioning in mind, and some require substantial improvement to provide a safe foundation from which to retrieve waste and decommission. The cleanup of these legacy facilities must be carefully balanced with the ongoing operations that provide services to commercial customers. Cleanup must be carried out safely and efficiently, without impacting upon commercial operations whose revenue is vital to funding the Cleanup organizations scope of work. This paper will introduce the cleanup approach at West Cumbria's Sellafield nuclear site. It will provide an overview of what is being done in preparation to meet the formidable but rewarding challenge ahead. (authors)

  2. Quality assurance during site construction of nuclear power plants

    International Nuclear Information System (INIS)

    1981-01-01

    This Safety Guide provides requirements and recommendations related to the establishment and implementation of a quality assurance programme for the site construction activities at nuclear power plants. These include activities such as fabricating, erecting, installing, handling, storing, cleaning, flushing, inspecting, testing, modifying, repairing, and maintaining

  3. On-site tests on the nuclear power plants

    International Nuclear Information System (INIS)

    Morilhat, P.; Favennec, J.M.; Neau, P.; Preudhomme, E.

    1996-01-01

    On-site tests and experiments are performed by EDF Research and Development Division on the nuclear power plants to assess the behaviour of major components submitted to thermal and vibratory solicitations. On-going studies deal with the qualification of new nuclear power plant standard and with the feedback of plants under operation. The tests, particularly the investigation tests, correspond to large investments and entail an important data volume which must ensure the continuity over a long period of the order of magnitude of the in-service plant life (around 40 years). This paper addresses the on-site experimental activities, describes the means to be used, and gives an example: the qualification of SG of new 1450 MW nuclear power plants. (author)

  4. History of creation of Semipalatinsk test nuclear site. Chapter 1

    International Nuclear Information System (INIS)

    1999-01-01

    In 1949 August USSR's Government adopted decision about creation of nuclear site with conditional name Uchebnyj polygon 2. For its building was chosen territory in 140 km from Semipalatinsk city. Semipalatinsk test site consists of the land of three regions: Semipalatinsk, Pavlodar, Karaganda and it occupies 18,500 km 2 of fertile land, rich with minerals. Now this territory was alienated from national using. Polygon was complex object and it incorporated three main zones: Opytnoe Pole, zone of radiation safety, site Sh. Opytnoe Pole was equipped by special constructions ensuring nuclear test conducting, its observing and registration of physical measurements and occupied 2,300 km 2 . Around of the Opytnoe Pole is situated zone of radiation safety with area 45 thousand ha. Site Sh was situated in 14 km from center of Opytnoe Pole and it was intended for distribution of individual protection devices, dosimeters and for conducting of dis-activation and sanitary works. History of the site creation is connected with building of Kurchatov city. In dozen and hundred of kilometers from Kurchatov city there were top secret objects: site Balapan with total area 100,000 ha intended for conducting of nuclear tests in wells with threshold capacity 100-200 kt. Here simultaneously with main problems on the site the military-applied works were conducted on mechanics, physics of combustion, simulation of Earthquakes and determination of seismic stability of buildings and constructions. Research site Degelen with total area 33,100 ha which has been used for underground testing of nuclear charges with small capacity. Site 10 one of large research technical complex on which two reactor units were installed. Main tasks of the complex were as follows: high-temperature fuel materials testing, conducting of fundamental researches in field of physics of fissile products, thermal physics and gas hydrodynamics. On site M a laboratory base for radiochemical, radiological and chemical

  5. Review of underground siting of nuclear power plants

    International Nuclear Information System (INIS)

    1974-01-01

    A review of the potential for the underground siting of nuclear power generating plants has been undertaken. The review comprised a survey and assessment of relevant published documents currently available, together with discussions with Government sponsored agencies and other bodies, to evaluate the current status of technology related to the design and construction of underground nuclear power plants. It includes a review of previous work related to the underground siting of power plants and other facilities; a preliminary evaluation of the relative merits of the various concepts of undergrounding which have been proposed or constructed; a review of current technology as it relates to the requirements for the design, construction and operation of underground nuclear power plants; an examination of the safety and environmental aspects; and the identification of areas of further study which will be required if the underground is to be established as a fully viable alternative to surface siting. No attempt has been made to draw final conclusions at this stage. Nothing has been found to suggest that the underground siting concept could not provide a viable alternative to the surface concept. It is also apparent that no major technological developments are required. It is not clear, however, whether the improvements in safety and containment postulated for the underground can be realized at an economic cost; or even whether any additional cost is in fact involved. The problem is essentially site dependent and requires further study for which recommendations are made. (auth)

  6. Nuclear Material Processing at the Savannah River Site

    International Nuclear Information System (INIS)

    Severynse, T.F.

    1998-07-01

    Plutonium production for national defense began at Savannah River in the mid-1950s, following construction of production reactors and separations facilities. Following the successful completion of its production mission, the site's nuclear material processing facilities continue to operate to perform stabilization of excess materials and potentially support the disposition of these materials. A number of restoration and productivity improvement projects implemented in the 1980s, totaling nearly a billion dollars, have resulted in these facilities representing the most modern and only remaining operating large-scale processing facilities in the DOE Complex. Together with the Site's extensive nuclear infrastructure, and integrated waste management system, SRS is the only DOE site with the capability and mission of ongoing processing operations

  7. Expected brine movement at potential nuclear waste repository salt sites

    International Nuclear Information System (INIS)

    McCauley, V.S.; Raines, G.E.

    1987-08-01

    The BRINEMIG brine migration code predicts rates and quantities of brine migration to a waste package emplaced in a high-level nuclear waste repository in salt. The BRINEMIG code is an explicit time-marching finite-difference code that solves a mass balance equation and uses the Jenks equation to predict velocities of brine migration. Predictions were made for the seven potentially acceptable salt sites under consideration as locations for the first US high-level nuclear waste repository. Predicted total quantities of accumulated brine were on the order of 1 m 3 brine per waste package or less. Less brine accumulation is expected at domal salt sites because of the lower initial moisture contents relative to bedded salt sites. Less total accumulation of brine is predicted for spent fuel than for commercial high-level waste because of the lower temperatures generated by spent fuel. 11 refs., 36 figs., 29 tabs

  8. On the population dose around the Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Hill, P.; Dederichs, H.; Ostapczuk, P.; Hille, R.; Artemev, O.; Ptitskaya, L.; Akhmetov, M.; Pivovarov, S.

    2002-01-01

    Since 1949 the Semipalatinsk Nuclear Test Site (NTS) was extensively used by the former Soviet government as a testing range for atomic weapons. Atmospheric and underground tests were finally stopped in 1962 and 1989, respectively. The Ministry of the Russian Federation of Atomic Energy officially counts a total of 456 tests, including 116 atmospheric tests. The total yield of the nuclear explosions carried out was 6.3 Megatons equivalent with 6.7 PetaBq of 1 37C s and 3.7 PetaBq of 9 0S r being released into the athmosphere. Some of the athmospheric radioactive tests shielded plumes, which extended far beyond the outer borders of the NTS. Already the first Soviet atomic bomb test on August 29, 1949 due to unfavourable meteorological conditions affected the villages of Dolon and Moistik. Since 1995 joint investigations performed by the Research Centre Julich in cooperation with the Kazakh National Nuclear Centre in the region of the former nuclear test site near Semipalatinsk besides environmental measurents also involve the assessment of the current dose of the population at and around the test site in addition to the important retrospective determination of the dose of persons affected by the atmospheric tests

  9. Off-site nuclear emergency exercises in Japan

    International Nuclear Information System (INIS)

    Eiji, U.; Kiyoshi, T.; Masao, O.; Shigeru, F.

    1993-01-01

    Nuclear emergency planning and preparedness in Japan have been organized by both national and local governments based on the Disaster Countermeasures Basic Act. Off-site nuclear emergency exercises are classified into two types: national-government level exercises and local-government level exercises. National-government level exercises are carried out once a year by the competent national authorities. Among these authorities, the Science and Technology Agency (STA) fills a leading position in the Japanese nuclear emergency planning and preparedness. Local-government level exercises are carried out once a year or once in a few years by the local governments of the prefectures where nuclear facilities are located. Most of the off-site nuclear emergency exercises in Japan are performed by local-governments. The aim of these exercises is to reinforce the skills of the emergency staff. The national government (STA etc.) provides advices and assistance including financial support to the local-governments. Emergency exercises with the participation of residents have been carried out in some local-governments. As an example of local-government level exercises, an experience in Shizuoka prefecture (central part of Japan) is presented

  10. Nuclear project sites on Shimokita Peninsula in summer 1989

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    The present report outlines the current progress in the nuclear projects implemented on the Shimokita Peninsula. At Rokkashomura, Japan Nuclear Fuel Industries is building a uranium enrichment plant. The basic work began in October 1988 and was completed by the end of May, and building work on the plant began. The plant building construction has now progressed to 50% for the first unit of 150,000 SUW/year. The site for the low level radioactive waste storage facility is still flat ground. For the reprocessing plant, Japan Nuclear Fuel Service's permit for waste management business is still before STA. Only road construction, unrelated to licensing, is going on. The completion of the safety examination for reprocessing is expected around 1991. At Higashidorimura, a fishery cooperative has rejected the proposal of compensation, and the compensation problem is at a stalemate. Following a zig-zag course in political disturbances, the Nuclear Ship Mutsu entered its port at Sekinehama in January 1988. Corrosion dots were found on some of the fuel assemblies, and Japan Atomic Energy Research Institute plans to carry out the recovery work in this autumn. Site acquisition procedures for building an Ohma nuclear power plant are now under way. (N.K.)

  11. Siting and early-stage project management of nuclear power plant

    International Nuclear Information System (INIS)

    Wang Kai; Li Guojin

    2013-01-01

    In this paper, difficulties and challenges facing in siting of nuclear power plant after Fukushima nuclear accident is introduced. The key points for siting are analyzed. The site characteristics related to nuclear safety and the evaluated methods are discussed. From project management perspective, main procedures and key points for the early-stage of a nuclear power project are described. (authors)

  12. A systems analysis approach to nuclear facility siting

    International Nuclear Information System (INIS)

    Gros, J.G.; Avenhaus, R.; Linnerooth, J.; Pahner, P.D.; Otway, H.J.

    1975-01-01

    An attempt is made to demonstrate an application of the techniques of systems analysis, which have been successful in solving a variety of problems, to nuclear facility siting. Within the framework of an overall regional land-use plan, a methodology for establishing the acceptability of a combination of site and facility is discussed. The consequences (e.g. the energy produced, thermal and chemical discharges, radioactive releases, aeshetic values, etc.) of the site-facility combination are identified and compared with formalized criteria in order to ensure 'legal acceptability'. Failure of any consequences to satisfy standard requirements results in a feedback channel which works to effect design changes in the facility. When 'legal acceptability' has been assured, the project enters the public sector for consideration. The responses of individuals and of various interested groups to the external attributes of the nuclear facility gradually emerge. The criteria by which interest groups judge technological advances reflect both their rational assessment and unconscious motivations. This process operates on individual, group, societal and international levels and may result in two basic feedback loops: one which might act to change regulatory criteria; the other which might influence facility design or site selection. Such reactions and responses on these levels result in a continuing process of confrontation, collaborative interchange and possible resolution in the direction of an acceptable solution. Finally, a Paretian approach to optimizing the site-facility combination is presented for the case where there are several possible combinations of site and facility. A hypothetical example of the latter is given, based upon typical preference functions determined for four interest groups. The research effort of the IIASA Energy Systems Project and the Joint IAEA/IIASA Research Project in the area of nuclear siting is summarized. (author)

  13. Negotiating the voluntary siting of nuclear waste facilities

    International Nuclear Information System (INIS)

    Mussler, R.M.

    1992-01-01

    This paper discusses the Office of the Nuclear Waste Negotiator which was created by Congress with the purpose of seeking a voluntary host State or Indian tribe for a high level nuclear waste repository or monitored retrievable storage facility. Given the history of the Federal government's efforts at siting such facilities, this would appear to be an impossible mission. Since commencing operations in August 1990, the Office has accomplished perhaps more than had been expected. Some of the approaches it has taken to implementing this mission may be applicable to other endeavors

  14. Declassification and restoration of nuclear sites; Declassement et restauration des sites nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Noynaert, L; Rahier, A; Deboodt, P; Massaut, V

    1998-09-01

    The report describes the legal and technical aspects of the declassification and restoration of nuclear sites. This involves a number of technical and administrative operations. Different declassification strategies are discussed. The evaluation of the risks and impact on the environment are discussed as well as research and development needs, costs and possible sources for funding.

  15. Anti-nuclear activities and critics concerning nuclear power plant sites

    International Nuclear Information System (INIS)

    Rhee, We-Beg

    2000-01-01

    Korea has dynamic nuclear power expansion programs, operating 16 nuclear units producing 13710 MW in total located on 4 different sites. Last year, nuclear power supplied over 40 % of national total electricity demands. In 1998, Korean government initiated re-designation work investigating circumstance changes to rule out the unnecessary sites in consideration of a long-term power supply. Korean government has determined to expand the Ulchin site and to designate one point of Woolju county as a new candidate site, and ruled out the rest candidate sites at the end of 1998. About such a governmental measure, the two areas show different reactions. Ulchin where nuclear power plant has been operated safely for about 10 years was likely to accept the governmental determination in spite of some opposition and called for several financial supports for local development. WooIju county, however, showed a strong opposition among local environmental groups and autonomous politicians, and they presented a variety of anti-nuclear activities including demonstrations mainly at the neighbouring metropolis, Ulsan city

  16. Towards a regional siting approach for canadian nuclear fuel waste

    International Nuclear Information System (INIS)

    Kuhn, R.G.

    1999-01-01

    The proposal to construct a nuclear fuel waste (NFW) disposal facility in Canada is fraught with difficulties, particularly with respect to gaining public acceptance and consent. Public perceptions of risk associated with a disposal facility are generally negative. Indeed, it was found that over 60% of residents in northern Ontario communities are opposed to the possibility of a disposal facility being constructed within 120 km of their community. Even after being offered the possibility of compensation and incentives, the majority of residents are strongly opposed. Canadian decision makers have generally endorsed a siting framework known as the open siting approach. The major characteristic of this approach is that it allows for substantial public participation in any siting process. It is premised on the notion that only communities where a majority of citizens favour the siting of a facility will be considered as potential hosts. However, given that the majority of residents on the Ontario portion of the Canadian Shield are strongly opposed to a NFW facility, the open approach will not be a panacea for a successful siting process. The major limitation of this approach is the fact that a single community cannot be isolated from its surrounding region and communities. The purpose of this paper is to work towards the development of a regional siting strategy for Canadian nuclear fuel waste management. There are no clear precedents of a regional siting approach to facility location in Canada. However, some analogous planning regimes and initiatives have been attempted. Common to these initiatives is the consideration of a large geographical region and attempts to integrate, at least formally, social, cultural, political and environmental concerns in a coherent and comprehensive manner. Under this type of 'siting strategy' NFW management would be considered within a broad array of resource management initiatives, social and cultural priorities, and institutional

  17. Radionuclides around nuclear sites in England and Wales

    International Nuclear Information System (INIS)

    Sanchez, A.L.; Horrill, A.D.; Singleton, D.L.; Leonard, D.R.P.

    1996-01-01

    Environmental releases of low levels of radioactivity can occur as a consequence of normal operations at nuclear facilities. In England and Wales, the impact of gaseous discharges on the terrestrial environment is monitored routinely by the site operators as well as by Food Science Division of the Ministry of Agriculture, Fisheries and Food. The terrestrial surveillance programme carried out by MAFF Food Science concentrates on agricultural produce to provide assessments of doses to members of the population derived from the consumption of terrestrial foodstuffs. We present here the results of a survey, undertaken in 1993 to supplement the monitoring data of MAFF, of artificial radioactive contamination around eighteen nuclear establishments in England and Wales. Grass and soil samples were used as indicators of environmental contamination at these sites for the radionuclides 137 Cs, 90 Sr, 239+240 Pu and 241 Am. When compared to estimated background radionuclide concentrations close to each site, these data reveal that four of the 18 sites have contributed measurable increases to both the 137 Cs and 239+240 Pu inventory within 500 m outside the boundary fence. Two additional sites showed slight increases above the expected background soil levels of 239+240 Pu

  18. Delegated democracy. Siting selection for the Swedish nuclear waste

    International Nuclear Information System (INIS)

    Johansson, Hanna Sofia

    2008-11-01

    The present study concerns the siting of the Swedish nuclear waste repository. Four cases are examined: the feasibility studies in Nykoeping and Tierp (cases 1 and 2), as well as three public consultation meetings with conservationist and environmental organisations, and two study visits to nuclear facilities in Oskarshamn and Oesthammar, which were held during what is called the site-investigation phase (cases 3 and 4). The Swedish Nuclear Fuel and Waste Management Co (SKB) began the search for a nuclear waste site in the 1970s. Since 1992 SKB has conducted feasibility studies in eight municipalities, including in the four municipalities mentioned above. At the present time more comprehensive site investigations are underway in Oskarshamn and Oesthammar, two municipalities that already host nuclear power plants as well as storages for nuclear waste. In addition to SKB and the municipalities involved in the site-selection process, politicians, opinion groups, concerned members of the public, and oversight bodies are important actors. The analysis of the cases employs the concepts of 'sub-politics', 'boundary work', and 'expertise', together with the four models of democracy 'representative democracy', participatory democracy', 'deliberative democracy', and 'technocracy'. The aim of the study is to describe the characteristics of Swedish democracy in relation to the disposal of Swedish nuclear waste. The main questions of the study are: Which democratic ideals can be found within SKB's siting process during the feasibility studies and in the consultation process during the site investigations? and Which democratic ideals were influential during the feasibility studies and in the consultation process? The study is based on qualitative methods, and the source materials consist of documents, interviews, and participant observations. In summary, the form of democracy that emerges in the four case studies can be described as delegated democracy. This means that a large

  19. Modelling of nuclear explosions in hard rock sites

    International Nuclear Information System (INIS)

    Brunish, W.M.; App, F.N.

    1993-01-01

    This study represents part of a larger effort to systematically model the effects of differing source region properties on ground motion from underground nuclear explosions at the Nevada Test Site. In previous work by the authors the primary emphasis was on alluvium and both saturated and unsaturated tuff. We have attempted to model events on Pahute Mesa, where either the working point medium, or some of the layers above the working point, or both, are hard rock. The complex layering at these sites, however, has prevented us from drawing unambiguous conclusions about modelling hard rock

  20. Safety aspects of geological studies around nuclear installations sites

    International Nuclear Information System (INIS)

    Faure, J.

    1988-01-01

    The experience of geological studies of about forty french nuclear sites allows to set out the objectives, the phases and the geographic extensions of workings to be realized for confirming a site. The data to be collected for the safety analysis are specified; they concern the local and regional geology, the geotechnical characteristics and the essential elements for evaluating the hazards related to the soil liquefaction, the surface fracturing and in some cases the volcanic risks. It is necessary to follow up the geology during the installation construction and life. 8 refs. (F.M.)

  1. Utility survey on nuclear power plant siting and nuclear energy centers

    International Nuclear Information System (INIS)

    Cope, D.F.; Bauman, H.F.

    1977-01-01

    Most of the large U.S. utilities were surveyed by telephone and mail on questions concerning nuclear power plant siting and nuclear energy centers (NECs). The main purpose of the survey was for guidance of ERDA's NEC program. The questions covered the following topics: availability of sites; impact of environmental and other restraints; plans for development of multi-unit sites; interest in NEC development; interest in including fuel-cycle facilities in NECs; and opinions on the roles desired for the state and Federal governments in power plant siting. The main conclusion of the survey was that, while many utilities were considering multiple-unit sites of 2 to 5 units, none were planning larger energy centers at the present time. However, several expressed interest in NECs as a long-range future development

  2. Should the public be encouraged to visit nuclear plant sites?

    International Nuclear Information System (INIS)

    Ferte, J. de la

    1993-01-01

    As we all know, technological progress does not only depend on the innovation capacity of scientists and engineers or the sophistication of technology, but also on public acceptance. People - today - are not only more curious about new applications of technology but also more inquiring about their potential impact on their own safety and environment. This is particularly true in the nuclear field, where the people are afraid of nuclear installations and processes unknown to them. On the contrary, the more opportunities they have to see or live near nuclear plants, the less they are inclined to reject them as a whole. The past two decades have confirmed the increasing importance of visitor centres at nuclear plant sites as a major communication tool between the nuclear industry and the public. Already today, for example, 16% of the US public and 11% of the French public have visited a nuclear power plant or its information centre. A rich experience is therefore available from existing visitor centres at nuclear power stations in most industrialised countries. Furthermore, the construction and industrial operation of new facilities in the nuclear fuel cycle presents new challenges in terms of public understanding and acceptance which are progressively taken into account. As a result, visitor centres with new communication strategies and tools are now being put in place at radioactive waste management sites and nuclear fuel cycle sites as well as near nuclear installations being dismantled. The OECD Nuclear Energy Agency (NEA) organised an international Seminar in November 1992 in Madrid (Spain) in co-operation with the Spanish Agency for the Management of Radioactive Waste (ENRESA) and the Union of Spanish Electricity Utilities (UNESA) to: 1. take stock of the experience of OECD countries in the design and operation of visitor centres; 2. assess the educational and information methods and tools used in these centres, and 3. measure their impact on public opinion and

  3. Should the public be encouraged to visit nuclear plant sites?

    Energy Technology Data Exchange (ETDEWEB)

    Ferte, J de la [External Relations and Public Affairs, OECD Nuclear Energy Agency, Paris (France)

    1993-07-01

    As we all know, technological progress does not only depend on the innovation capacity of scientists and engineers or the sophistication of technology, but also on public acceptance. People - today - are not only more curious about new applications of technology but also more inquiring about their potential impact on their own safety and environment. This is particularly true in the nuclear field, where the people are afraid of nuclear installations and processes unknown to them. On the contrary, the more opportunities they have to see or live near nuclear plants, the less they are inclined to reject them as a whole. The past two decades have confirmed the increasing importance of visitor centres at nuclear plant sites as a major communication tool between the nuclear industry and the public. Already today, for example, 16% of the US public and 11% of the French public have visited a nuclear power plant or its information centre. A rich experience is therefore available from existing visitor centres at nuclear power stations in most industrialised countries. Furthermore, the construction and industrial operation of new facilities in the nuclear fuel cycle presents new challenges in terms of public understanding and acceptance which are progressively taken into account. As a result, visitor centres with new communication strategies and tools are now being put in place at radioactive waste management sites and nuclear fuel cycle sites as well as near nuclear installations being dismantled. The OECD Nuclear Energy Agency (NEA) organised an international Seminar in November 1992 in Madrid (Spain) in co-operation with the Spanish Agency for the Management of Radioactive Waste (ENRESA) and the Union of Spanish Electricity Utilities (UNESA) to: 1. take stock of the experience of OECD countries in the design and operation of visitor centres; 2. assess the educational and information methods and tools used in these centres, and 3. measure their impact on public opinion and

  4. Incentives and nuclear waste siting: Prospects and constraints

    International Nuclear Information System (INIS)

    Carnes, S.A.; Copenhaver, E.D.; Sorensen, J.H.; Soderstrom, E.J.; Reed, J.H.; Bjornstad, D.J.; Peelle, E.

    1983-01-01

    Limited anecdotal evidence from existing incentive-based facility sitings, and from a survey of rural Wisconsin residents in 1980 regarding the acceptability of a nuclear waste repository, indicates that incentives may help ahcieve the twin goals of increasing local support and decreasing local opposition to hosting nuclear waste facilities. Incentives are classified according to functional categories (i.e., mitigation, compensation, and reward), and prerequisites to the use of incentives are outlined (i.e., guarantee of public health and safety, some measure of local control, and a legitimation of negotiations during siting). Criteria for evaluating the utility of incentives packages may be more useful than single incentives, and nonmonetary incentives, such as independent monitoring and access to credible information, may be as important in eliciting support as monetary incentives. 54 references, 1 figure, 4 tables

  5. Risk analysis and solving the nuclear waste siting problem

    International Nuclear Information System (INIS)

    Inhaber, H.

    1994-01-01

    In spite of millions of dollars and countless human resources being expended on finding nuclear wastes sites, the search has proved extremely difficult for the nuclear industry. This may be due to the approach followed, rather than inadequacies in research or funding. A new approach to the problem, the reverse Dutch auction, is suggested. It retains some of the useful elements of the present system, but it also adds new ones. It allows natural market forces to set the level of compensation, rather than relying on close-door negotiations or theoretical calculations. Two flow charts show the pre-bid and post-bid steps of the reverse Duch auction system of Inhaber. It is assumed that a state wishes to site a waste facility somewhere in its boundaries. 22 refs., 3 figs

  6. Improvements MOIRA system for application to nuclear sites Spanish river

    International Nuclear Information System (INIS)

    Gallego Diaz, E.; Iglesias Ferrer, R.; Dvorzhak, A.; Hofman, D.

    2011-01-01

    Possible consequences of a nuclear accident must have radioactive contamination in the medium and long-term freshwater aquatic systems. Faced with this problem, it is essential to have a realistic assessment of the radiological impact, ecological, social and economic potential management strategies, to take the best decisions rationally. MOIRA is a system of decision support developed in the course of the European Framework Programmes with participation of the UPM, which has been improved and adapted to Spanish nuclear sites in recent years in the context ISIDRO Project, sponsored by the Council Nuclear, with the participation of CIEMAT and UPM. The paper focuses on these advances, primarily related to complex hydraulic systems such as rivers Tajo, Ebro and Jucar, which are located several Spanish plants.

  7. Nuclear test at Semipalatinsk test site and their environmental impacts

    International Nuclear Information System (INIS)

    Logachev, V.A.

    2000-01-01

    This paper present classification of nuclear tests conducted at the Semipalatinsk test site by tier radiation hazards. The Institute of Biophysics of the Russian Ministry of Health established a data base the archival data on radiation situation parameters and compiled an album of radioactive plum footprints. The paper states that external and internal exposure doses received by population lived in the test vicinity can sufficiently reliably assesses using archival data. (author)

  8. Nuclear site in the Semipalatinsk and Kazakhstan population health

    International Nuclear Information System (INIS)

    Moshkevich, V.S.; Atchabarov, B.A.

    2001-01-01

    It is noted, that during underground nuclear weapons tests (1963-1991) in inhabitants living in areas adjoining to Semipalatinsk test site a set of pathologies were revealed. Children illness rate in 2-3 times is higher than in the control regions, blood circulation organs in adults in the 3 times higher, skin diseases in 2.5 times higher, blood diseases and immunity reduction in 2 times frequently, etc

  9. Assessment of off-site consequences of nuclear accidents (MARIA)

    International Nuclear Information System (INIS)

    Haywood, S.M.

    1985-01-01

    A brief report is given of a workshop held in Luxembourg in 1985 on methods for assessing the off-site radiological consequences of nuclear accidents (MARIA). The sessions included topics such as atmospheric dispersion; foodchain transfer; urban contamination; demographic and land use data; dosimetry, health effects, economic and countermeasures models; uncertainty analysis; and application of probabilistic risk assessment results as input to decision aids. (U.K.)

  10. Site characterization requirements for nuclear-cratering design

    International Nuclear Information System (INIS)

    Terhune, R.W.; Carlson, R.C.

    1977-01-01

    A material properties measurement program for the design of large engineering nuclear-excavation projects by computer calculation is presented. Material properties of the site and their relative effect on crater size are analyzed and ordered in relation to their importance in determining the overall cratering efficiency. The measurement program includes both in situ logging and laboratory measurement of core samples, together with the reason for each measurement and its use in the calculations

  11. UFOs and nukes. Extraordinary encounters at nuclear weapons sites

    International Nuclear Information System (INIS)

    Hastings, Robert L.

    2015-01-01

    Everyone knows about the reported recovery of a crashed alien spaceship near Roswell, New Mexico in July 1947. However, most people are unaware that, at the time of the incident, Roswell Army Airfield was home to the world's only atomic bomber squadron, the 509th Bomb Group. Was this merely a coincidence? During the Cold War, the United States and the Soviet Union built thousands of the far more destructive hydrogen bombs, some of them a thousand times as destructive as the first atomic bombs dropped on Japan. If the nuclear standoff between the superpowers had erupted into World War III, human civilization - and perhaps the very survival of our species - would have been at risk. Did this ominous state of affairs come to the attention of outside observers? Was there a connection between the atomic bomber squadron based at Roswell and the reported crash of a UFO nearby? Did those who pilot the UFOs monitor the superpowers' nuclear arms race during the dangerous Cold War era? Do they scrutinize American and Russian weapons sites even now? UFOs and Nukes provides the startling and sometimes shocking answers to these questions. Veteran researcher Robert Hastings has investigated nuclear weapons-related UFO incidents for more than three decades and has interviewed more than 120 ex-US Air Force personnel, from former Airmen to retired Colonels, who witnessed extraordinary UFO encounters at nuclear weapons sites. Their amazing stories are presented here.

  12. Estimation of Typhoon Wind Hazard Curves for Nuclear Sites

    Energy Technology Data Exchange (ETDEWEB)

    Choun, Young-Sun; Kim, Min-Kyu [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The intensity of such typhoons, which can influence the Korean Peninsula, is on an increasing trend owing to a rapid change of climate of the Northwest Pacific Ocean. Therefore, nuclear facilities should be prepared against future super-typhoons. Currently, the U.S. Nuclear Regulatory Commission requires that a new NPP should be designed to endure the design-basis hurricane wind speeds corresponding to an annual exceedance frequency of 10{sup -7} (return period of 10 million years). A typical technique used to estimate typhoon wind speeds is based on a sampling of the key parameters of typhoon wind models from the distribution functions fitting statistical distributions to the observation data. Thus, the estimated wind speeds for long return periods include an unavoidable uncertainty owing to a limited observation. This study estimates the typhoon wind speeds for nuclear sites using a Monte Carlo simulation, and derives wind hazard curves using a logic-tree framework to reduce the epistemic uncertainty. Typhoon wind speeds were estimated for different return periods through a Monte-Carlo simulation using the typhoon observation data, and the wind hazard curves were derived using a logic-tree framework for three nuclear sites. The hazard curves for the simulated and probable maximum winds were obtained. The mean hazard curves for the simulated and probable maximum winds can be used for the design and risk assessment of an NPP.

  13. The disposal of Canada's nuclear fuel waste: site screening and site evaluation technology

    International Nuclear Information System (INIS)

    Davison, C.C.; Brown, A.; Everitt, R.A.; Gascoyne, M.; Kozak, E.T.; Lodha, G.S.; Martin, C.D.; Soonawala, N.M.; Stevenson, D.R.; Thorne, G.A.; Whitaker, S.H.

    1994-06-01

    The concept for the disposal of Canada's nuclear fuel waste is to dispose of the waste in an underground vault, nominally at 500 m to 1000 m depth, at a suitable site in plutonic rock of the Canadian Shield. The feasibility of this concept and assessments of its impact on the environment and human health, will be documented by AECL in an Environmental Impact Statement (EIS). This report is one of nine primary references for the EIS. It describes the approach and methods that would be used during the siting stage of the disposal project to identify a preferred candidate disposal site and to confirm its suitability for constructing a disposal facility. The siting stage is divided into two distinct but closely related substages, site screening and site evaluation. Site screening would mainly involve reconnaissance investigations of siting regions of the Shield to identify potential candidate areas where suitable vault locations are likely to exist. Site screening would identify a small number of candidate areas where further detailed investigations were warranted. Site evaluation would involve progressively more detailed surface and subsurface investigations of the candidate areas to first identify potentially suitable vault locations within the candidate areas, and then characterize these potential disposal sites to identify the preferred candidate location for constructing the disposal vault. Site evaluation would conclude with the construction of exploratory shafts and tunnels at the preferred vault location, and underground characterization would be done to confirm the suitability of the preferred candidate site. An integrated program of geological, geophysical, hydrogeological, geochemical and geomechanical investigations would be implemented to obtain the geoscience information needed to assess the suitability of the candidate siting areas and candidate sites for locating a disposal vault. The candidate siting areas and candidate disposal vault sites would be

  14. Final disposal of spent nuclear fuel - basis for site selection

    International Nuclear Information System (INIS)

    Anttila, P.

    1995-05-01

    International organizations, e.g. IAEA, have published several recommendations and guides for the safe disposal of radioactive waste. There are three major groups of issues affecting the site selection process, i.e. geological, environmental and socioeconomic. The first step of the site selection process is an inventory of potential host rock formations. After that, potential study areas are screened to identify sites for detailed investigations, prior to geological conditions and overall suitability for the safe disposal. This kind of stepwise site selection procedure has been used in Finland and in Sweden. A similar approach has been proposed in Canada, too. In accordance with the amendment to the Nuclear Energy Act, that entered into force in the beginning of 1995, Imatran Voima Oy has to make preparations for the final disposal of spent fuel in the Finnish bedrock. Relating to the possible site selection, the following geological factors, as internationally recommended and used in the Nordic countries, should be taken into account: topography, stability of bedrock, brokenness and fracturing of bedrock, size of bedrock block, rock type, predictability and natural resources. The bedrock of the Loviisa NPP site is a part of the Vyborg rapakivi massif. As a whole the rapakivi granite area forms a potential target area, although other rock types or areas cannot be excluded from possible site selection studies. (25 refs., 7 figs.)

  15. Risk-benefit evaluation of nuclear power plant siting

    International Nuclear Information System (INIS)

    Miettinen, J.; Savolainen, I.; Silvennoinen, P.

    1976-01-01

    An assessment scheme is described for the risk-benefit analyses of nuclear power versus conventional alternatives. Given the siting parameters for the proposed nuclear plant an economic comparison is made with the most advantageous competitive conventional production scenario. The economic benefit is determined from the differential discounted annual energy procurement cost as a function of the real interest rate and amortization time. The risk analysis encompasses the following factors: radiation risks in normal operation, reactor accident hazards and economic risks, atmospheric pollutants from the conventional power plants, and fuel transportation. The hazards are first considered in terms of probabilistic dose distributions. In the second stage risk components are converted to a compatible form where excess mortality is used as the risk indicator. Practical calculations are performed for the power production alternatives of Helsinki where district heat would be extracted from the nuclear power plant. At the real interest rate of 10% and amortization time of 20 yr the 1000 MW(e) nuclear option is found to be Pound9.1 m per yr more economic than the optimal conventional scenario. Simultaneously the nuclear alternative is estimated to reduce excess mortality by 2 to 5 fatal injuries annually. (author)

  16. A new approach to the nuclear power plant site licensing

    Energy Technology Data Exchange (ETDEWEB)

    Kidron, A A [Israel Electric Corp. Ltd., Haifa (Israel)

    1996-12-01

    The Israel Electric Corporation Ltd.(IEC) conducted a survey to determine the geotechnical suitability of the Shivta Site for the purpose of erecting a Nuclear Power Station and presented the results in a Preliminary Safety Analysis Report (PSAR) to the Licensing Division of the Israel Atomic Energy Commission (LD). The studies for selecting a site in the NW Negev were conducted by multi-disciplinary teams of Israeli and US professionals, beginning in 1982, over a twelve-year period. The investigations involved comprehensive geological, geophysical, geotechnical, hydrological, as well as geomorphic and pedologic evaluations of the region and the then- proposed site locale. The prior studies were completed using highly advanced and modern tools and approaches and provided a significant amount of information related to the tectonic and seismic characteristics of the NW Negev region. (author).

  17. Study on Quaternary ground siting of nuclear power plant, (1)

    International Nuclear Information System (INIS)

    Kokusho, Takaji; Nishi, Koichi; Honsho, Shizumitsu

    1991-01-01

    A seismic stability evaluation method for a nuclear power plant to be located on a Quaternary sandy/gravelly ground is discussed herein in terms of the geological and geotechnical survey, design earthquake motion evaluation and geotechnical seismic stability analyses. The geological and geotechnical exploration tunnel in the rock-foundation siting will be difficult in the Quaternary ground siting. Boring, geophysical surveys and soil samplings will play a major role in this case. The design earthquake input spectrum for this siting is proposed so as to take account the significant effect of longer period motion on the ground stability. Equivalent and non-linear analyses demonstrate the seismic stability of the foundation ground so long as the soil density is high. (author)

  18. Quaternary ground siting technology of nuclear power plants

    International Nuclear Information System (INIS)

    Nishi, K.; Kokusho, T.; Iwatate, Y.; Ishida, K.; Honsho, S.; Okamoto, T.; Tohma, J.; Tanaka, Y.; Kanatani, M.

    1992-01-01

    A seismic stability evaluation method for a nuclear power plant to be located on Quaternary sandy/gravelly ground is discussed herein in terms of a geological and geotechnical survey, a design earthquake motion evaluation and geotechnical seismic stability analyses. The geological and geotechnical exploration tunnel in the rock foundation siting will be difficult in the Quaternary ground siting. Boring, geophysical surveys and soil sampling will play a major role in this case. A design earthquake input spectrum for this siting is proposed to take in account the significant effect of longer period motion on ground stability. Equivalent and non-linear analyses demonstrate the seismic stability of the foundation ground so long as the soil density is high. (author)

  19. Sites for locations of nuclear reactors; Sitios para emplazamientos de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Balcazar, M.; Huerta, M.; Lopez, A., E-mail: miguel.balcazar@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2014-10-15

    A restriction on sites of nuclear energy is the history of seismic activity, in its magnitude (Richter) and intensity (Mercalli). This article delimits the areas of greatest magnitude and national seismic intensity, with restrictions of ground acceleration; the supplement areas with a low magnitude of seismic activity are shown. Potential sites for the location of these sites are introduced into a geographic information system. The set of geo-referenced data contains the location of the active volcanic manifestations; the historical record of earthquake epicenters, magnitudes and intensities; major geological faults; surface hydrology and water bodies; location of population density; protected areas; contour lines; the rock type or geology. The geographic information system allows entering normative criteria and environmental restrictions that correlate with geo-referenced data described above, forms both probable and exclusion areas for the installation of nuclear sites. (Author)

  20. Site selection for Canada's national repository for used nuclear fuel

    International Nuclear Information System (INIS)

    Ben Belfadhel, M.; Watts, B.; Facella, J.

    2015-01-01

    In 2007, the Government of Canada selected Adaptive Phased Management as Canada's plan for the long-term management of Canada's used nuclear fuel. The approach provides for containment and isolation of the material in a deep geological repository at a safe site with an informed and willing host. The Nuclear Waste Management Organization is tasked through federal legislation with selecting the site and developing and managing all aspects of the plan. In May 2010, the organization published and initiated the site selection process that serves as a road map for decision making on the location for the deep geological repository. It continues to lead the site selection process for the repository and an associated Centre of Expertise. The screening process is advancing and, from an initial starting point of 22 communities expressing interest in learning about the project; as of September 2015, 9 communities are the focus of more detailed technical and community well-being studies. Preliminary Assessments, the third step in the 9-step site selection process are underway in these communities. The Assessments involve preliminary technical and social desktop and field assessments, engagement activities within and beyond each interested community, and involvement of Indigenous peoples and nearby municipalities in the planning and conduct of the work. This paper provides an update on the advancement of the site selection process. It describes the nature of the technical and social studies being conducted at this phase of work, including the progressively more detailed field studies that are the focus of technical work at the current stage, the approach to engagement and collaboration with communities to direct these studies, and the work underway to ensure the framework used for this assessment and engagement includes the range of priorities and perspectives of First Nations and Metis peoples and communities in the broader area. (author)

  1. The ANCLI White Paper on Local Governance of Nuclear Sites

    International Nuclear Information System (INIS)

    Delalonde, Jean-Claude; Demet, Michel; Gadbois, Serge; Heriard Dubreuil, Gilles

    2006-01-01

    The 1981 circular, 'Information Commissions attached to Power Stations', was an important regulatory step, which enabled local communities to come together to discuss nuclear issues with the site operators and official inspectorates. However the Local Information Commissions (CLI), have encountered numerous obstacles, both practical and legislative, in fulfilling their role as information providers and, particularly, as monitors. It is now acknowledged in France both by members of commissions at local level and by public authorities that CLI would benefit from a more statutory role in the decision-making process as well as from a specific legal statute associated with independent resources. The forthcoming Nuclear Safety and Transparency Bill should establish a new legal and institutional framework for local commissions. The National Association of CLI (ANCLI) gathers and represents the CLI at national level. In Spring 2005, in the perspective of the Nuclear Safety and Transparency bill, the ANCLI initiated a participatory process involving about 30 delegates from a dozen CLI (elected representatives, NGOs, local experts) in order to raise a common expertise and make recommendations on this new legal statute, on the basis of their own return of experience. The White Paper is structured around four main subject areas: Structure and status of CLIs, local powers; - Role of CLIs and ANCLI in the national and international decision-making process; Local communities' access to specialist expertise; and Waste management. The CLIs reaffirm their local powers and ability to best assure the continued monitoring of nuclear sites and any other nuclear issues in their area. In particular, this local authority allows them to balance different risks as well as political and economic decisions which have a bearing on their region's future. It implies a certain autonomy on the part of CLIs in the exercise of their scrutiny functions, evaluating all the factors impacting both on the

  2. Sites and social assessment of nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Nemoto, K [Central Research Inst. of Electric Power Industry, Tokyo (Japan)

    1977-09-01

    The sites of nuclear power plants in Japan have two features, first the extreme expectation for regional development because of the selection of depopulated districts for most locations, and the second, apprehensions of local people for two reasons of nuclear power generating techniques which do not plant the roots in society and handling of radioactive materials. In order to cope with these problems, it is necessary to consider that the development plan of the regions around reactor sites must be compiled systematically. Its premise is the ''social assessment'' which estimates the economical and social influences and evaluates the merit and demerit of nuclear power plants prior to the construction. This is of course inevitable. The objects of the assessment may be divided as follows: the human effect to individuals, the institutional effect to local community, the economical effect to region, and the national influence to the whole country. While the developmental action of locations includes the stages of examination, planning, construction and operation, and three location patterns are recognized according to the emphasized function, the improvement of national economy, upgrading of environmental quality, and the most priority in local welfare. In the process of the assessment, the following items may be taken notice that each item requires sometimes the weighting; the pattern to abandon location may exist; positive and negative effects are required to be distributed evenly in a triangle having the apexes each representing one of the above three patterns.

  3. [Assessment of modern radioecological situation at nuclear explosion "Chagan" (Balapan Site, Semipalatinsk Nuclear Test Site, Kazakhstan)].

    Science.gov (United States)

    Evseeva, T I; Maĭstrenko, T A; Geras'kin, S A; Belykh, E S; Umarov, M A; Sergeeva, I Iu; Sergeev, V Iu

    2008-01-01

    Results on estimation of modern radioecological situation at nuclear explosion "Chagan" based on large-scale cartographic studies (1:25000) of a test area (4 km2) are presented. Maximum gamma-irradiation doses were observed at bulk of ground surrounded a crater and at radioactive fall-outs extended to the North-East and to the SouthWest from the crater. Based on data on artificial radionuclide specific activity most part of soil samples were attributed to radioactive wastes according to IAEA (1996) and OSPORB (1999). Natural decrease of soil radioactivity up to safety level due to 60Co, 137Cs, 90Sr, 152Eu, 154Eu radioactive decay and 241Am accumulation-decay will not take place within the next 60 years at the studied area.

  4. Visitor Centre at Nuclear Facility Site of La Hague

    International Nuclear Information System (INIS)

    Marie-Sainte, E.; Jozeau-Marigne, M.

    1993-01-01

    Cogema, a french fuel reprocessing plant, reprocesses spent fuel issued from french nuclear power plants, but also japanese, german, swiss, belgian, dutch ones. Since 1976, Cogema has reprocessed more than 5000 tons of spent fuel, about 85% of spent fuel in the world with a market economy. Since 1976, Cogema has a department which is in charge of visits of the firm. Five persons, communication assistants in charge of relations with the public organize all year long, visits on the site. A visitor centre has been built in 1974 by the CEA (Commissariat a l'Energie Atomique). It is opened to the public six months by year, from 1st of april until 30 of september, seven days a week. The visitor centre is situated out of the factory enclosure, so everybody can come in without formality. Entrance is free. Four floors to explain what is fuel cycle, reprocessing, environment surveillance, radiation protection, dosimetry, panels with elementary notions of nuclear physics (atom, fission, reactor working), use of atom in medicine and non nuclear industry, a whole of general information related to nuclear historical record, fuel cycle, and particularly activities of La Hague

  5. Nuclear facility decommissioning and site remedial actions: a selected bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

    1982-09-01

    This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints.

  6. Nuclear facility decommissioning and site remedial actions: a selected bibliography

    International Nuclear Information System (INIS)

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Johnson, C.A.

    1982-09-01

    This bibliography contains 693 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. Foreign, as well as domestic, literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Uranium Mill Tailings Remedial Action Program, Grand Junction Remedial Action Program, and Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General Studies. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. An appendix of 202 bibliographic references without abstracts or indexes has been included in this bibliography. This appendix represents literature identified but not abstracted due to time constraints

  7. Radiation burden of population in nuclear power plant siting

    International Nuclear Information System (INIS)

    Navratil, J.

    The significance is discussed of the determination of the radiobiological consequences of normal operation and design basis accidents in nuclear power plant siting. The basic diagram and brief description is given of the programme for calculating the radiation load of the population in the surroundings of the nuclear power plant. The programme consists of two subprogrammes, i.e., the dispersion of radioactive gases (for normal operation and for accidents), the main programme for the determination of biological consequences and one auxiliary programme (the distribution of the population in the surroundings of the power plant). The four most important types of exposure to ionizing radiation are considered, namely inhalation, external irradiation from a cloud, ingestion (water, milk, vegetables), external irradiation from the deposit. (B.S.)

  8. Nuclear engineering R ampersand D at the Savannah River Site

    International Nuclear Information System (INIS)

    Strosnider, D.R.; Ferrara, W.R.

    1991-01-01

    The Westinghouse Savannah River Company (WSRC) is the prime operating contractor for the US Department of Energy at the Savannah River Site (SRS), located near Aiken, South Carolina. One division of WSRC, the Savannah River Laboratory (SRL), has the primary responsibility for research and development, which includes supporting the safe and efficient operation of the SRS production reactors. Several Sections of SRL, as well as other organization in WSRC, pursue R ampersand D and oversight activities related to nuclear engineering. The Sections listed below are described in more detail in this document: (SRL) nuclear reactor technology and scientific computations department; (SRL) safety analysis and risk management department; (WSRC) new production reactor program; and (WSRC) environment, safety, health, and quality assurance division

  9. Avian radioecology on a nuclear power station site. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Levy, C.K.; Maletskos, C.J.; Youngstrom, K.A.

    1975-01-01

    A summary of a six-year avian radioecology study at the site of a nuclear power plant in Massachusetts is reported. A completed historical summary is followed by a description of mathematical models developed to calculate the effects on bird body burdens of various changes in environmental radionuclide levels. Examples are presented. Radionuclide metabolism studies in which acute doses of /sup 131/I and /sup 137/Cs were administered to four species of wild birds are presented. Radionuclides were administered both intravenously and orally; no apparent differences in uptake or elimination rates were observed between the two methods.

  10. External doses of residents near semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Takada, Jun; Hoshi, Masaharu; Nagatomo, Tsuneto

    1999-01-01

    Accumulated external radiation doses of residents near the Semipalatinsk nuclear test site of the former USSR are presented as a results of study by the thermoluminescence technique for bricks sampled at several settlements in 1995 and 1996. The external doses that we evaluated from exposed bricks were up to about 100 cGy for resident. The external doses at several points in the center of Semipalatinsk City ranged from a background level to 60 cGy, which was remarkably high compared with the previously reported values based on military data. (author)

  11. Avian radioecology on a nuclear power station site. Final report

    International Nuclear Information System (INIS)

    Levy, C.K.; Maletskos, C.J.; Youngstrom, K.A.

    1975-01-01

    A summary of a six-year avian radioecology study at the site of a nuclear power plant in Massachusetts is reported. A completed historical summary is followed by a description of mathematical models developed to calculate the effects on bird body burdens of various changes in environmental radionuclide levels. Examples are presented. Radionuclide metabolism studies in which acute doses of 131 I and 137 Cs were administered to four species of wild birds are presented. Radionuclides were administered both intravenously and orally; no apparent differences in uptake or elimination rates were observed between the two methods

  12. Perry Nuclear Plant's Plans for on-site storage

    International Nuclear Information System (INIS)

    Ratchen, J.T.

    1993-01-01

    Because of current radwaste disposal legislation and the eventual denial of access to the Barnwell, Richland, and Beatty burial sites, it was imperative for the Perry nuclear power plant to develop alternative means for handling its generated radioactive waste. The previous radwaste facilities at Perry were developed for processing, packaging, short-term storage, and shipment for burial. In order to meet the changing needs, new facilities have been constructed to handle the processing, packaging, and 5-yr interim storage of both dry active waste (DAW) and dewatered or solidified resin, filter media, etc

  13. Nuclear site selection and environmental protection. The decision making methods

    International Nuclear Information System (INIS)

    Bresson, G.; Lacourly, G.; Fitoussi, L.

    1975-01-01

    The selection of the site of a nuclear plant most often comes to seek out and compound between two trends: that of the operator who will try and reduce the cost price of his product to the lowest and that of the protectionist who will try and reduce to the minimum the hazards resulting from the plant operation. Such a compromise is the result of a more or less empirical choice, which enters within the frame of a cost-benefit analysis, in which theoretically, the choice between several possible solutions is made of the selection giving the higher advantage [fr

  14. Off-site monitoring for the Mighty Oak nuclear test

    International Nuclear Information System (INIS)

    Black, S.C.; Smith, A.E.; Costa, C.F.

    1986-07-01

    After a nuclear explosives test, code name Mighty Oak, the tunnel leading to the test point became contaminated with radioactive debris. To re-enter and recover valuable equipment and data, the DOE purged the tunnel air using particulate and charcoal filters to minimize discharge of radioactivity to the atmosphere. During this purging, the EPA established special air samples supplementing their routine air monitoring networks. Analysis of the collected samples for radioactive noble gases and for gamma-emitting radionuclides indicated that only low levels of xenon-133 were released in amounts detectable in populated areas near the Nevada Test Site. The maximum dose to an individual was calculated to be 0.36 microrem, assuming that person remained in the open field at the measurement site during the whole period of the purging

  15. Nuclear method applied in archaeological sites at the Amazon basin

    International Nuclear Information System (INIS)

    Nicoli, Ieda Gomes; Bernedo, Alfredo Victor Bellido; Latini, Rose Mary

    2002-01-01

    The aim of this work was to use the nuclear methodology to character pottery discovered inside archaeological sites recognized with circular earth structure in Acre State - Brazil which may contribute to the research in the reconstruction of part of the pre-history of the Amazonic Basin. The sites are located mainly in the Hydrographic Basin of High Purus River. Three of them were strategic chosen to collect the ceramics: Lobao, in Sena Madureira County at north; Alto Alegre in Rio Branco County at east and Xipamanu I, in Xapuri County at south. Neutron Activation Analysis in conjunction with multivariate statistical methods were used for the ceramic characterization and classification. An homogeneous group was established by all the sherds collected from Alto Alegre and was distinct from the other two groups analyzed. Some of the sherds collected from Xipamunu I appeared in Lobao's urns, probably because they had the same fabrication process. (author)

  16. Nuclear-physical methods in macro- and microanalytical investigations of contamination with radionuclides at Semipalatinsk Nuclear Test Site

    International Nuclear Information System (INIS)

    Solodukhin, V.P.

    2005-01-01

    A complex of nuclear-physical methods developed in the Institute of Nuclear Physics of Kazakhstan National Nuclear Center for the investigations of the rate, character and peculiarities of contamination with radionuclides of the Semipalatinsk Nuclear Test Site (SNTS) is presented. The developed method combines both macroinvestigations (radionuclide analysis, NAA, XRFA, ESR- and NGR-spectroscopy) and microinvestigations (MS, micro-PIXE, electron microscopy). The results of the investigations at the main SNTS test sites 'Opytnoye pole' and 'Degelen' are presented. (author)

  17. Capability for intrusion detection at nuclear fuel sites

    International Nuclear Information System (INIS)

    1978-03-01

    A safeguards vulnerability assessment was conducted at three separate licensed nuclear processing facilities. Emphasis was placed on: (1) performance of the total intrusion detection system, and (2) vulnerability of the system to compromise by insiders. The security guards were interviewed to evaluate their effectiveness in executing their duties in accordance with the plant's security plan and to assess their knowledge regarding the operation of the security equipment. A review of the training schedule showed that the guards, along with the other plant employees, are required to periodically attend in-plant training sessions. The vulnerability assessments continued with interviews of the personnel responsible for maintaining the security equipment, with discussions of detector false alarm and maintenance problems. The second part of the vulnerability assessments was to evaluate the effectiveness of the intrusion detection systems including the interior and the perimeter sensors, CCTV surveillance devices and the exterior lighting. Two types of perimeter detectors are used at the sites, a fence disturbance sensor and an infrared barrier type detector. Infrared barrier type detectors have a higher probability of detection, especially in conjunction with dedicated CCTV cameras. The exterior lights satisfy the 0.2 footcandle illumination requirement. The interior intrusion detection systems included ultrasonic motion detectors, microwave motion detectors,balanced magnetic switches, and CCTV cameras. Entrance doors to the materials access areas and vital areas are protected with balanced magnetic switches. The interior intrusion detection systems at the three nuclear processing sites are considered satisfactory with the exception of the areas protected with ultrasonic motion detectors

  18. Nuclear reactors sited deep underground in steel containment vessels

    Energy Technology Data Exchange (ETDEWEB)

    Bourque, Robert [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States)

    2006-07-01

    Although nuclear power plants are certainly very safe, they are not perceived as safe by the general populace. Also, there are concerns about overland transport of spent fuel rods and other irradiated components. It is hereby proposed that the nuclear components of nuclear power plants be placed in deep underground steel vessels with secondary coolant fed from them to turbines at or near the surface. All irradiated components, including spent fuel, would remain in the chamber indefinitely. This general concept was suggested by the late Edward Teller, generated some activity 20-25 years ago and appears to be recently reviving in interest. Previous work dealt with issues of geologic stability of underground, possibly reinforced, caverns. This paper presents another approach that makes siting independent of geology by placing the reactor components in a robust steel vessel capable of resisting full overburden pressure as well as pressures resulting from accident scenarios. Structural analysis of the two vessel concepts and approximate estimated costs are presented. This work clears the way for the extensive discussions required to evaluate the advantages of this concept. (author)

  19. Design basis flood for nuclear power plants on river sites

    International Nuclear Information System (INIS)

    1983-01-01

    The Guide presents techniques for determining the design basis flood (DBF) to be used for siting nuclear power plants at or near non-tidal reaches of rivers and for protecting nuclear power plants against floods. Since flooding of a nuclear power plant can have repercussions on safety, the DBF is always chosen to have a very low probability of exceedance per annum. The DBF may result from one or more of the following causes: (1) Precipitation, snowmelt; (2) Failure of water control structures, either from seismic or hydrological causes or from faulty operation of these structures; (3) Channel obstruction such as landslide, ice effects, log or debris jams, and effects of vulcanism. Normally the DBF is not less than any recorded or historical flood occurrence. For flood evaluation two types of methods are discussed in this Guide: probabilistic and deterministic. Simple probabilistic methods to determine floods of such low exceedance probability have a great degree of uncertainty and are presented for use only during the site survey. However, the more sophisticated probabilistic methods, the so-called stochastic methods, may give an acceptable result, as outlined in this Guide. The preferred method of evaluating the component of the DBF due to precipitation, as described in this Guide, is the deterministic one, based on the concept of a limit to the probable maximum precipitation (PMP) and on the unit hydrograph technique. Dam failures may generate a flood substantially more severe than that due to precipitation. The methodology for evaluating these types of floods is therefore presented in this Guide. Making allowance for the possible simultaneous occurrence of two or more important flood-producing events is also discussed here. The Guide does not deal with floods caused by sabotage

  20. Used nuclear materials at Savannah River Site: asset or waste?

    International Nuclear Information System (INIS)

    Magoulas, Virginia

    2013-01-01

    The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ''assets'' to worthless ''wastes''. In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as ''waste'' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest.

  1. Modelling of nuclear explosions in hard rock sites

    International Nuclear Information System (INIS)

    Brunish, W.M.; App, F.N.

    1993-01-01

    This study represents part of a larger effort to systematically model the effects of differing source region properties on ground motion from underground nuclear explosions at the Nevada Test Site. In previous work by the authors the primary emphasis was on alluvium and both saturated and unsaturated tuff. We have attempted to model events on Pahute Mesa, where either the working point medium, or some of the layers above the working point, or both, are hard rock. The complex layering at these sites, however, has prevented us from drawing unambiguous conclusions about modelling hard rock. In order to learn more about the response of hard rock to underground nuclear explosions, we have attempted to model the PILEDRIVER event. PILEDRIVER was fired on June 2, 1966 in the granite stock of Area 15 at the Nevada Test Site. The working point was at a depth of 462.7 m and the yield was determined to be 61 kt. Numerous surface, sub-surface and free-field measurements were made and analyzed by SRI. An attempt was made to determine the contribution of spall to the teleseismic signal, but proved unsuccessful because most of the data from below-shot-level gauges was lost. Nonetheless, there is quite a bit of good quality data from a variety of locations. We have been able to obtain relatively good agreement with the experimental PILEDRIVER waveforms. In order to do so, we had to model the granodiorite as being considerably weaker than ''good quality'' granite, and it had to undergo considerable weakening due to shock damage as well. In addition, the near-surface layers had to be modeled as being weak and compressible and as have a much lower sound speed than the material at depth. The is consistent with a fractured and jointed material at depth, and a weathered material near the surface

  2. Contaminated site investigation using nuclear technique: a case study of temporary transformer storage sites in Ghana

    International Nuclear Information System (INIS)

    Sanu, J. K.

    2013-07-01

    Recent introduction of man-made toxic chemicals, and the massive relocation of natural materials to different environmental compartment like soil, ground water and atmosphere, has resulted in severe pressure on the self- cleansing capacity of recipient ecosystems. Various accomulated pollutants and contaminants such as polychlorinated biphenyls (PCBs) are of much concern relative to both human and ecosystemm exposure and potential health impact. PCBs which are resistant to degradation and bioremediation accumulated in different niches of the biosphere. This significantly affects the ecological balances and cause adverse health effect on both human and the environment. Temporal transformer storage sites at four locations in Ghana (Tema, Temale, Bolgatanga and Wa) were investigated for PCB contamination using nuclear techniques. Analysis of soil samples from four temporal transformer storage sites revealed that the soil samples from Tema, Tamale, Bolgatanga and Wa were generally sandy with pH and EC ranging between 6.24 - 7.29 and 44.60 - 188.30 respectively. The PCB levels detected in the soil samples from the various locations varied considerably with mean ranging between 7.69 and 51.92 mg/kg. The highest mean PCB level was recorded at the Tema temporal transformer storage site (51.92 mg/kg), whilst the least mean level of 7.69 mg/kg was recorded at Wa storage site. At Tamale the individual levels range between 3.57 mg/kg and 38.70 mg/kg while at Bolgatanga it was 6.85 - 16.30 mg/kg and Wa, 6.08 - 14.70mg/kg. About 9% of soil samples from temporal transformer storage sites analysed had total PCBs concentrations above the 25mg/kg and 33 mg/kg level recommended by the Canadian Council of Ministers of environment (CCME) and EPA Ghana respectively for the protection of environment and human health. Generally, the Levels of PCBs in soil samples were found to decrease with increasing depth at all the temporal transformer storage sites. Results obtained using the EPA's L

  3. Reassessment of selected factors affecting siting of Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Davis, R.E.; Hanson, A.L.; Mubayi, V.; Nourbakhsh, H.P.

    1997-02-01

    Brookhaven National Laboratory has performed a series of probabilistic consequence assessment calculations for nuclear reactor siting. This study takes into account recent insights into severe accident source terms and examines consequences in a risk based format consistent with the quantitative health objectives (QHOs) of the NRC`s Safety Goal Policy. Simplified severe accident source terms developed in this study are based on the risk insights of NUREG-1150. The results of the study indicate that both the quantity of radioactivity released in a severe accident as well as the likelihood of a release are lower than those predicted in earlier studies. The accident risks using the simplified source terms are examined at a series of generic plant sites, that vary in population distribution, meteorological conditions, and exclusion area boundary distances. Sensitivity calculations are performed to evaluate the effects of emergency protective action assumptions on the risk of prompt fatality and latent cancers fatality, and population relocation. The study finds that based on the new source terms the prompt and latent fatality risks at all generic sites meet the QHOs of the NRC`s Safety Goal Policy by margins ranging from one to more than three orders of magnitude. 4 refs., 17 figs., 24 tabs.

  4. Rehabilitation of former nuclear test sites in Australia

    International Nuclear Information System (INIS)

    1990-01-01

    A range of options with indicative cost estimates and timescale has been defined for clean-up of the former British nuclear test sites at Maralinga and Emu in South Australia. The situation at the former test sites on the Monte Bello Islands has been reported separately. The predominant contributor to potential radiation dose at the test sites is residual plutonium contamination of soil which may be incorporated into the body through inhalation of resuspended dust. Acceptable levels of radioactive soil contamination based upon organ doses from incorporated plutonium and the associated health detriment are proposed by the Technical Assessment Group for a series of land-use options ranging from fully unrestricted habitation by Aboriginals including the case of high dependence on local plants and animals for food: to casual access by Aboriginals assuming retained or, if necessary, extended fences. The area of land affected and the quantity of soil and other material with more than the proposed limit of contamination as well as a range of remedial measures for reduction of the contamination to a level acceptable for each of the land-use options has been assessed and methods proposed for safe disposal of the contaminated materials. The associated costs of these remedial measures and disposal methods have also been estimated. 28 refs., 71 tabs., 45 figs

  5. The subject deserving wide attention for nuclear power plant siting and environmental impact assessment

    International Nuclear Information System (INIS)

    Li Yong; Li Wenhui; Zhang Lingyan

    2009-01-01

    Based on siting work of nuclear power plant, the characteristics of nuclear power plant site selection and environmental impact assessment are analysed in accordance with laws and regulations of nuclear safety and environmental protection. Some subjects deserving attentions are put forward. (authors)

  6. Two citizen task forces and the challenge of the evolving nuclear waste siting process

    International Nuclear Information System (INIS)

    Peelle, E.B.

    1990-01-01

    Siting any nuclear waste facility is problematic in today's climate of distrust toward nuclear agencies and fear of nuclear waste. This study compares and contrasts the siting and public participation processes as two citizen task forces dealt with their difficult responsibilities. 10 refs., 3 tabs

  7. Studies of Health Effects from Nuclear Testing near the Semipalatinsk Nuclear Test Site, Kazakhstan

    Directory of Open Access Journals (Sweden)

    Bernd Grosche

    2015-05-01

    Full Text Available The nuclear bomb testing conducted at the Semipalatinsk nuclear test site in Kazakhstan is of great importance for today’s radiation protection research, particularly in the area of low dose exposures. This type of radiation is of particular interest due to the lack of research in this field and how it impacts population health. In order to understand the possible health effects of nuclear bomb testing, it is important to determine what studies have been conducted on the effects of low dose exposure and dosimetry, and evaluate new epidemiologic data and biological material collected from populations living in proximity to the test site. With time, new epidemiological data has been made available, and it is possible that these data may be linked to biological samples. Next to linking existing and newly available data to examine health effects, the existing dosimetry system needs to be expanded and further developed to include residential areas, which have not yet been taken into account. The aim of this paper is to provide an overview of previous studies evaluating the health effects of nuclear testing, including some information on dosimetry efforts, and pointing out directions for future epidemiologic studies.

  8. Studies of Health Effects from Nuclear Testing near the Semipalatinsk Nuclear Test Site, Kazakhstan.

    Science.gov (United States)

    Grosche, Bernd; Zhunussova, Tamara; Apsalikov, Kazbek; Kesminiene, Ausrele

    2015-01-01

    The nuclear bomb testing conducted at the Semipalatinsk nuclear test site in Kazakhstan is of great importance for today's radiation protection research, particularly in the area of low dose exposures. This type of radiation is of particular interest due to the lack of research in this field and how it impacts population health. In order to understand the possible health effects of nuclear bomb testing, it is important to determine what studies have been conducted on the effects of low dose exposure and dosimetry, and evaluate new epidemiologic data and biological material collected from populations living in proximity to the test site. With time, new epidemiological data has been made available, and it is possible that these data may be linked to biological samples. Next to linking existing and newly available data to examine health effects, the existing dosimetry system needs to be expanded and further developed to include residential areas, which have not yet been taken into account. The aim of this paper is to provide an overview of previous studies evaluating the health effects of nuclear testing, including some information on dosimetry efforts, and pointing out directions for future epidemiologic studies.

  9. The population distribution near the sites of nuclear facilities in the FRG

    International Nuclear Information System (INIS)

    Gutschmidt, W.D.

    1975-11-01

    This report is a compilation of relevant data concerning population distribution near the site of nuclear installations in the Federal Republic of Germany. The 'Site Evaluation Data', a guideline approved by the Laender Committee on Nuclear Energy, is dealt with, and a classification of German nuclear sites with respect to the population distribution is presented. In addition, German and US nuclear sites are compared with the aid of the Site Population Factor, and in respect to population density values as given in WASH-1400. (orig.) [de

  10. Continental margin neotectonics in South Africa: a nuclear siting approach

    International Nuclear Information System (INIS)

    Andreoli, M.A.G.; Hambleton-Jones, B.B.; Anderson, N.J.B.; Faurie, J.N.; Raubenheimer, E.; Antoine, L.; Von Veh, M.W.; McMillan, I.K.

    1990-01-01

    Neotectonic activity in South Africa has only recently received attention despite the fact that a rigorous knowledge of this phenomenon could have a major impact on industrial development within certain areas. Since the early 1980s the Atomic Energy Corporation of South Africa has addressed this specific problem in the process of detailed site investigations for the licensing of six facilities related to the nuclear industry. The data indicates that there is a general correspondence in five selected areas along the South African coast between the development of Quarternary joints/faults and the degree of seismic activity recorded in each geological domain. Finally, the results provide new data that may add to a recent survey of global tectonic stresses. 13 refs., 1 fig

  11. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    International Nuclear Information System (INIS)

    DeAnn Long; Michael Murphy

    2008-01-01

    Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program

  12. Ethical considerations surrounding nuclear waste repository siting and mitigation

    International Nuclear Information System (INIS)

    Peters, T.F.

    1983-01-01

    The potential long-term health and safety effects of the nuclear materials stored in repositories, the extremely long periods of time over which such materials may be dangerous, and the equity implications of the siting of a repository in any given area are unlike the issues involved in other large-scale projects. They involve major philosophical issues basic to human perspectives on social relationships and on insuring the future of mankind. Safety and permanence are the two basic criteria for determining whether a waste proposal is satisfactory. This chapter takes the approach of public (or micro) ethics, whose task is to 1) articulate and clarify public values relevant to a problem, 2) identify and evaluate public options, and 3) rank alternatives in some order of ethical preferability. It addresses the four major repository-related issues: uncertainty and risks, geographic equity, intergenerational ethics, and implementation ethics

  13. Radiation exposures from nuclear tests at the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Dunning, G M

    1958-12-01

    A summary of the pertinent data on radiation exposures from nuclear tests in Nevada is presented. The data are presented in categories of external ..gamma.. radiation, activity concentrations in air, and activity concentrations in water. Methods used to estimate exposure and to evaluate data are described. The data are tabulated. The maximum external exposure was 7 to 8 r for 15 persons involved. In terms of relatively large populations, the average exposure for the 1,000,000 people living nearest the site was at the rate of 1/2 r/30 yr. The highest concentration of fallout activity in the air was about 1.3 ..mu..c/m/sup 3/ averaged over the 30 hr that the activity was present in significant quantities. The highest concentration of fallout activity in a potential drinking water supply was about 1.4 x 10/sup -/ ..mu..c/me extrapolated to D + 3 days. Evaluation of these data is given.

  14. General guidelines for recommendation of sites for nuclear waste repositories

    International Nuclear Information System (INIS)

    1983-01-01

    These guidelines were developed in accordance with the requirements of Section 112(a) of the Nuclear Waste Policy Act of 1982 for use by the Secretary of Energy in evaluating the suitability of sites for the development of repositories. The guidelines will be used for suitability evaluations and determinations made pursuant to Section 112(b) and any preliminary suitability determinations required by Section 114(f). The guidelines set forth in this Part are intended to complement the requirements set forth in the Act, 10 CFR Part 60, and 40 CFR Part 191. In applying these guidelines, the DOE will resolve any inconsistencies between these guidelines and the above documents in a manner determined by the DOE to most closely agree with the intent of the Act

  15. Application of microearthquake surveys in nuclear power plant siting

    International Nuclear Information System (INIS)

    1985-06-01

    Earthquakes of magnitude less than 3 are generally referred to as microearthquakes. After an overview of the use of microearthquake survey in decisions related to the siting of nuclear power plants, the main aspects of a microearthquake survey network are discussed. The use of microearthquake surveys in investigating problems related to near-field (floating) earthquakes is also discussed. The discussion is centered on the practical application of such a survey leading from objectives and limitations over to planning, instrumentation, operation, maintenance, processing of the data, and interpretation and reporting of the results. An appendix entitled Earthquake Magnitude gives useful background information for definitions of different types of magnitude and their calculation using the records from microearthquake surveys

  16. Identifying suitable piercement salt domes for nuclear waste storage sites

    International Nuclear Information System (INIS)

    Kehle, R.; e.

    1980-08-01

    Piercement salt domes of the northern interior salt basins of the Gulf of Mexico are being considered as permanent storage sites for both nuclear and chemically toxic wastes. The suitable domes are stable and inactive, having reached their final evolutionary configuration at least 30 million years ago. They are buried to depths far below the level to which erosion will penetrate during the prescribed storage period and are not subject to possible future reactivation. The salt cores of these domes are themselves impermeable, permitting neither the entry nor exit of ground water or other unwanted materials. In part, a stable dome may be recognized by its present geometric configuration, but conclusive proof depends on establishing its evolutionary state. The evolutionary state of a dome is obtained by reconstructing the growth history of the dome as revealed by the configuration of sedimentary strata in a large area (commonly 3,000 square miles or more) surrounding the dome. A high quality, multifold CDP reflection seismic profile across a candidate dome will provide much of the necessary information when integrated with available subsurface control. Additional seismic profiles may be required to confirm an apparent configuration of the surrounding strata and an interpreted evolutionary history. High frequency seismic data collected in the near vicinity of a dome are also needed as a supplement to the CDP data to permit accurate depiction of the configuration of shallow strata. Such data must be tied to shallow drill hole control to confirm the geologic age at which dome growth ceased. If it is determined that a dome reached a terminal configuration many millions of years ago, such a dome is incapable of reactivation and thus constitutes a stable storage site for nuclear wastes

  17. Radiation exposure of inhabitants around Semipalatinsk nuclear weapon test site

    International Nuclear Information System (INIS)

    Takada, Jun; Hoshi, Masaharu

    1997-01-01

    This paper described and reviewed the data reported by Russia and Kazakhstan and authors' studies on the exposed doses as follows. History of nuclear explosion tests in Semipalatinsk: From 1949 to 1989 in old Russia, 459 explosion tests involving 26 on the ground, 87 in the air and 346 in underground were performed, of which TNT equivalence was 0.6 Mt, 6 Mt and 11 Mt, respectively. A mystery in the reports of radiation doses by Russia and Kazakhstan. Present status of the regions after the end of nuclear weapon tests: Environment radiation doses in μSv/h in following regions were 0.06 in Mostik, 0.1 in Dolon and Semipalatinsk, 0.07 in Izvyestka and Znamenka, 0.08 in Tchagan and 21 in Atomic Lake. Evaluation of external exposure dose of the living regions with thermoluminescence method: External exposure dose was estimated to be about 90 cGy in a certain village and 40 cGy in Semipalatinsk which being 150 km far from the test site. (K.H.)

  18. Remote controlled tool systems for nuclear sites have subsea applications

    International Nuclear Information System (INIS)

    Bath, B.; Yemington, C.; Kuhta, B.

    1995-10-01

    Remotely operated underwater tool systems designed to operate in Nuclear Fuel Storage Basins can be applied to deep water, subsea oilfield applications. Spent nuclear fuel rods re stored underwater in large indoor swimming pool-like facilities where the water cover shields the workers from the radiation. This paper describes three specialized tooling systems that were designed and built by Sonsub for work at the Department of Energy's Hanford site. The Door Seal Tool removed an existing seal system, cleaned a 20 ft. tall, carbon steel, underwater hatch and installed a new stainless steel gasket surface with underwater epoxy. The Concrete Sampling Tool was built to take core samples from the vertical, concrete walls of the basins. The tool has three hydraulic drills with proprietary hollow core drill bits to cut and retrieve the concrete samples. The Rack Saw remotely attached itself to a structure, cut a variety of steel shapes and pipes, and retained the cut pieces for retrieval. All of these systems are remotely operated with onboard video cameras and debris collection systems. The methods and equipment proven in this application are available to refurbish sealing surfaces and to drill or sample concrete in offshore oil field applications

  19. Some issues on radiological consequences analysis in site selection for nuclear power stations

    International Nuclear Information System (INIS)

    Chen Xiaoqiu; Yue Huiguo

    2006-01-01

    The three considerations, Site safety and environmental protection and emergency preparedness, are the focus of attention in the evaluation of the suitability of a site for nuclear power station. This paper summarized the basic regulatory requirements for the siting of nuclear power station, described the existing problems on radiological consequences analyses during the siting stage and discussed the is- sues that need to concern in the reviewing of the radiological consequences analyses in the siting appraisal stage. (authors)

  20. Information report on nuclear safety and radiation protection of the Tricastin AREVA site, 2010 edition

    International Nuclear Information System (INIS)

    2010-01-01

    This report presents the Tricastin site, the different arrangements concerning nuclear safety and radiation protection on this site, and recent nuclear events. It describes how site releases are managed and how the environment is controlled and monitored, how wastes are managed, and how other impacts are controlled. It finally presents the different actions regarding transparency and information

  1. The importante of physical and mathematical models for nuclear power plants site selection

    International Nuclear Information System (INIS)

    Rios, J.L.P.

    1989-01-01

    The importance of the release of effluents from nuclear installations for the site selection of nuclear power plants is discussed. The main available analysis methods, physical and mathematical, is presented [pt

  2. Coda Spectral Peaking for Nevada Nuclear Test Site Explosions

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, K R; Mayeda, K; Walter, W R

    2007-09-10

    We have applied the regional S-wave coda calibration technique of Mayeda et al. (2003) to earthquake data in and around the Nevada Test Site (NTS) using 4 regional broadband stations from the LLNL seismic network. We applied the same path and site corrections to tamped nuclear explosion data and averaged the source spectra over the four stations. Narrowband coda amplitudes from the spectra were then regressed against inferred yield based on the regional m{sub b}(Pn) magnitude of Denny et al. (1987), along with the yield formulation of Vergino and Mensing (1990). We find the following: (1) The coda-derived spectra show a peak which is dependent upon emplacement depth, not event size; (2) Source size estimates are stable for the coda and show a dependence upon the near-source strength and gas porosity; (3) For explosions with the same m{sub b}(Pn) or inferred yield, those in weaker material have lower coda amplitudes at 1-3 Hz.

  3. Site Specific Analyses of a Spent Nuclear Fuel Transportation Accident

    International Nuclear Information System (INIS)

    Biwer, B. M.; Chen, S. Y.

    2003-01-01

    The number of spent nuclear fuel (SNF) shipments is expected to increase significantly during the time period that the United States' inventory of SNF is sent to a final disposal site. Prior work estimated that the highest accident risks of a SNF shipping campaign to the proposed geologic repository at Yucca Mountain were in the corridor states, such as Illinois. The largest potential human health impacts would be expected to occur in areas with high population densities such as urban settings. Thus, our current study examined the human health impacts from the most plausible severe SNF transportation accidents in the Chicago metropolitan area. The RISKIND 2.0 program was used to model site-specific data for an area where the largest impacts might occur. The results have shown that the radiological human health consequences of a severe SNF rail transportation accident on average might be similar to one year of exposure to natural background radiation for those persons living a nd working in the most affected areas downwind of the actual accident location. For maximally exposed individuals, an exposure similar to about two years of exposure to natural background radiation was estimated. In addition to the accident probabilities being very low (approximately 1 chance in 10,000 or less during the entire shipping campaign), the actual human health impacts are expected to be lower if any of the accidents considered did occur, because the results are dependent on the specific location and weather conditions, such as wind speed and direction, that were selected to maximize the results. Also, comparison of the results of longer duration accident scenarios against U.S. Environmental Protection Agency guidelines was made to demonstrate the usefulness of this site-specific analysis for emergency planning purposes

  4. Management of Hanford Site non-defense production reactor spent nuclear fuel, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1997-03-01

    The US Department of Energy (DOE) needs to provide radiologically, and industrially safe and cost-effective management of the non-defense production reactor spent nuclear fuel (SNF) at the Hanford Site. The proposed action would place the Hanford Site's non-defense production reactor SNF in a radiologically- and industrially-safe, and passive storage condition pending final disposition. The proposed action would also reduce operational costs associated with storage of the non-defense production reactor SNF through consolidation of the SNF and through use of passive rather than active storage systems. Environmental, safety and health vulnerabilities associated with existing non-defense production reactor SNF storage facilities have been identified. DOE has determined that additional activities are required to consolidate non-defense production reactor SNF management activities at the Hanford Site, including cost-effective and safe interim storage, prior to final disposition, to enable deactivation of facilities where the SNF is now stored. Cost-effectiveness would be realized: through reduced operational costs associated with passive rather than active storage systems; removal of SNF from areas undergoing deactivation as part of the Hanford Site remediation effort; and eliminating the need to duplicate future transloading facilities at the 200 and 400 Areas. Radiologically- and industrially-safe storage would be enhanced through: (1) removal from aging facilities requiring substantial upgrades to continue safe storage; (2) utilization of passive rather than active storage systems for SNF; and (3) removal of SNF from some storage containers which have a limited remaining design life. No substantial increase in Hanford Site environmental impacts would be expected from the proposed action. Environmental impacts from postulated accident scenarios also were evaluated, and indicated that the risks associated with the proposed action would be small

  5. Explanation of procedure on site medical emergency response for nuclear accident

    International Nuclear Information System (INIS)

    Liu Yulong; Jiang Zhong

    2012-01-01

    National occupational health standard-Procedure on Site Medical Emergency Response for Nuclear Accident has been approved and issued by the Ministry of Health. This standard is formulated according to the Emergency Response Law of the People's Republic of China, Law of the People 's Republic of China on Prevention and Control of Occupational Diseases, Regulations on Emergency Measures for Nuclear Accidents at Nuclear Power Plants, and Health Emergency Plans for Nuclear and Radiological Accidents of Ministry of Health, supporting the use of On-site Medical Emergency Planning and Preparedness for Nuclear Accidents and Off-site Medical Emergency Planning and Preparedness for Nuclear Accidents. Nuclear accident on-site medical response procedure is a part of the on-site emergency plan. The standard specifies the basic content and requirements of the nuclear accident on-site medical emergency response procedures of nuclear facilities operating units to guide and regulate the work of nuclear accident on-site medical emergency response of nuclear facilities operating units. The criteria-related contents were interpreted in this article. (authors)

  6. Hypothesis of a nuclear accident to the nuclear power plant of Gravelines with important radioactive release out of the site: risks prevention, intervention strategies. Evaluation of the sensitization to the nuclear risk of the physician practicing near the site

    International Nuclear Information System (INIS)

    Mraovic, Th.

    1998-01-01

    This thesis has for hypothesis a nuclear accident at the nuclear power plant of Gravelines with radioactive release out of the site: the risks prevention and the strategies of intervention are studied. An evaluation of the sensitization to a nuclear risk is made for the general practitioner that practices near the site. (N.C.)

  7. Symposium on the development of nuclear waste policy: Siting the high-level nuclear waste repository

    International Nuclear Information System (INIS)

    Pijawka, K.D.; Mushkatel, A.H.

    1991-01-01

    The Nuclear Waste Policy Act of 1982 (NWPA) attempted to formulate a viable national policy for managing the disposal of high-level nuclear wastes. The NWPA authorized the selection of two repository sites: the first to be constructed in the West and a second site developed in the eastern United States. A detailed process for site selection was outlined in the NWPA. In addition, the NWPA authorized open-quotes the development of a waste transportation system; required the Department of Energy (DOE) to submit a proposal to construct a facility for monitored retrievable storage (MRS) after conducting a study of the need for, and feasibility of such a facility; and required the President to evaluate the use of the repositories ... for the disposal of high-level waste resulting from defense activitiesclose quotes (DOE, 1988, p. 1). A series of provisions granting oversight participation to states and Indian tribes, as well as a compensation package for the ultimate host state were also included. Responsibility for implementing the NWPA was assigned to DOE

  8. Sustainable land use planning at the Semipalatinsk Nuclear Test Site

    International Nuclear Information System (INIS)

    Coughtrey, P.J.; Ridgway, R.B.; Baumann, P.

    2001-01-01

    Full text: The UK Department for International Development (DFID) has recently agreed to support a project to develop a participatory sustainable land use plan for areas affected by nuclear weapons testing at Semipalatinsk. This three year project is expected to be initiated in April 2001 and will form one component of the United Nations Development Programme (UNDP) Semipalatinsk Rehabilitation Programme. The project will be undertaken by a combination of Kazakh organizations working with UK consultants and will meet its overall aim through the following main activities: Development of institutional capacity in data management and analysis; Provision of information and education on environmental contamination, hazards and risks; Development of a participatory land use planning process and piloting of the process in specific areas and communities around the test site; Integration of mineral resource extraction in the land planning process with a focus- on water resource and environmental protection and participatory approaches to resolving land use conflicts; Development of legislative tools to permit the implementation of environmental management of resource exploitation. The project will make use of both modern satellite-based imagery and more traditional methods to determine the potential for different land uses within the test site. The results obtained will be incorporated with additional information on land use. radiological and hydrological conditions at the test site through a geographical information system (GIS) provided by the project. The GIS will form the core component for collation and distribution of information on options available for use of different areas of the test site and its vicinity. A participatory rural appraisal, using tried and tested techniques, will identify local interest groups in land use planning and identify the details of their stake in the process. The groups will include owners-herders, employee-herders, and subsistence

  9. 76 FR 82201 - General Site Suitability Criteria for Nuclear Power Stations

    Science.gov (United States)

    2011-12-30

    ... guidelines in identifying suitable candidate sites for nuclear power stations. The decision that a station... combination and a cost-benefit analysis comparing it with alternative site-plant combinations, as discussed in...

  10. On-site and off-site emergency planning at Cekmece Nuclear Research and Training Centre

    International Nuclear Information System (INIS)

    Soyberk, O.A.

    1986-01-01

    An emergency plan was prepared for minimizing the consequences of any unforeseen radiation accident in Cekmece Nuclear Research and Training Centre (CNAEM) in Istanbul, Turkey. CNAEM is situated near Kucukcekmece Lake, which is about 30 km to the west of Istanbul. It includes two pool-type research reactors of 1 MW(th) and 5 MW(th). The population in the nearest inhabited areas varies from 1000 to 50,000. Accidents are classified, according to their severity, into three categories at CNAEM: (a) local emergency, (b) on-site emergency, (c) off-site emergency. During local emergency situations evacuation is not necessary. An on-site emergency situation requires the evacuation of personnel from the plant. Personnel hearing the emergency alarm should move directly to the preselected place as soon as possible. An off-site emergency is any accident that leads to widespread contamination outside the boundary. In this situation the Turkish Atomic Energy Authority and governmental authorities are notified immediately. The emergency organization group consists of: (a) Plant Superintendent, (b) Emergency Director, (c) Reactor Supervisor, (d) Senior Health Physicist, (e) Reactor Shift Operator, (f) Health Physicists. The administration building will be used as the Emergency Control Centre. The emergency teams working under the direction of the Emergency Director consist of: (a) Health Physics, (b) Fire and Rescue, (c) First Aid and Decontamination, (d) Transportation, (e) Security and Patrol. The emergency situation is evaluated in three phases at CNAEM. The first phase is the first few hours after the beginning of the accident. The second phase is between 8-10 hours or more following the first phase. The third phase is the recovery phase. The integrated doses over periods of two hours and two days are calculated according to the situation of the core, i.e. total or partial melting, and weather conditions. The results of the calculated parameters can be adapted to possible

  11. Radioactive survey of the environment of the nuclear sites of French Nuclear Board: an overview

    International Nuclear Information System (INIS)

    Robeau, D.; Montjoie, M.; Sauve, A.M.; Laporte, J.; Rahaplen, A.; Alphonse, L.; Huc, C.; Bensimon, C.; Cissoko, G.

    1992-01-01

    C.E.A. has set up a network of radioactive survey around its nuclear sites. This network involves terrestrial, atmospheric and marine results of radioactive measurements. This survey is structured in four levels. The level 0 homogenizes stations of measurements, level 1 centralizes real-time measurements of gross α and β measurements of atmospheric radioactivity, level 2 and 3 centralizes postponed α-β spectrometric measurements of radioactivity on water, deposition, grass, vegetables. People can have a squint at these results of measurements using popular MINITEL telephonic network. (author)

  12. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    International Nuclear Information System (INIS)

    Demick, L.E.

    2011-01-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  13. Next Generation Nuclear Plant Project Evaluation of Siting a HTGR Co-generation Plant on an Operating Commercial Nuclear Power Plant Site

    Energy Technology Data Exchange (ETDEWEB)

    L.E. Demick

    2011-10-01

    This paper summarizes an evaluation by the Idaho National Laboratory (INL) Next Generation Nuclear Plant (NGNP) Project of siting a High Temperature Gas-cooled Reactor (HTGR) plant on an existing nuclear plant site that is located in an area of significant industrial activity. This is a co-generation application in which the HTGR Plant will be supplying steam and electricity to one or more of the nearby industrial plants.

  14. Geological techniques used in the siting of South Africa's nuclear facilities

    International Nuclear Information System (INIS)

    Andersen, N.J.B.

    1990-01-01

    Nuclear site selection studies begin with an initial screening phase in order to pick regions which could be potentially suitable. When assessing a potential nuclear site from a structural geological point of view, the most important factors are the presence of 'capable faults', the seismicity of the area, and the existence of good foundation rock. A geological evaluation of a potential site involves a literature survey for all existing geological data on the site, geophysical investigations, structural domain analysis and geological mapping

  15. Design basis flood for nuclear power plants on coastal sites

    International Nuclear Information System (INIS)

    1983-01-01

    This Guide discusses the phenomena causing coastal floods (storm surge, seiche, tsunami and wind-wave) and gives a general description of the methods used and the critical factors involved in the evaluation of such floods and of their associated effects. In addition, some treatment is presented of the possible combinations of two or more of these phenomena to produce a DBF. Methods are also provided for evaluating the reference water levels, taking into account the effect of tides, sea level anomalies and changes in lake level and river flow. Sites vulnerable to coastal flooding are located on open coastal regions, semi-enclosed bodies of water and enclosed bodies of water. Open coastal regions are those portions of land directly exposed to and having a shore on a major body of water. Semi-enclosed bodies of water are lagoons, river estuaries, gulfs, fjords and rias. Enclosed bodies of water are lakes and reservoirs. The phenomena of the lowering of the water level at coastal sites caused by offshore winds, low tides, wave effects or of drawdown caused by tsunamis are discussed. The static and dynamic effects of floods resulting from the various combinations (independent and interdependent) of surface waves of varying frequency are also discussed. Consideration is also given to shoreline instabilities and to the effects of erosion. Estimated flood levels and related effects on the nuclear power plant, which will vary according to the method of analysis and the type of flooding considered, shall be compared with available historical data where this is relevant, to check the conservativeness of the evaluated results

  16. Preliminary Evaluation of Removing Used Nuclear Fuel From Nine Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul

    2013-04-30

    The Blue Ribbon Commission on America’s Nuclear Future identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses. In this report, a preliminary evaluation of removing used nuclear fuel from nine shutdown sites was conducted. The shutdown sites included Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion. At these sites a total of 7649 used nuclear fuel assemblies and a total of 2813.2 metric tons heavy metal (MTHM) of used nuclear fuel are contained in 248 storage canisters. In addition, 11 canisters containing greater-than-Class C (GTCC) low-level radioactive waste are stored at these sites. The evaluation was divided in four components: • characterization of the used nuclear fuel and GTCC low-level radioactive waste inventory at the shutdown sites • an evaluation of the onsite transportation conditions at the shutdown sites • an evaluation of the near-site transportation infrastructure and experience relevant to the shipping of transportation casks containing used nuclear fuel from the shutdown sites • an evaluation of the actions necessary to prepare for and remove used nuclear fuel and GTCC low-level radioactive waste from the shutdown sites. Using these evaluations the authors developed time sequences of activities and time durations for removing the used nuclear fuel and GTCC low-level radioactive waste from a single shutdown site, from three shutdown sites located close to each other, and from all nine shutdown sites.

  17. Off-site protective action selection for nuclear reactor accidents

    International Nuclear Information System (INIS)

    Weerakkody, S.D.

    1986-01-01

    A computer program based upon a model using a rational theoretical basis was developed to select appropriate off-site protective actions during nuclear reactor accidents. The special features of this program include (a) introduction of a precursor concept that uses the history of the accident progression to determine the spectrum of potential accident scenarios and estimates of the likelihoods of each accident scenario; (b) use of statistical decision theory and the concept of entropy of a spectrum to select the appropriate protective actions using either the minimax principle or the Bayes action method; and (c) introduction of methods to quantify evacuation travel risks. In order to illustrate the usefulness of the computer program, it was applied at three stages of the Three Mile Island accident scenario. Quantified non-radiological risks of evaluation have been used to establish dose thresholds below which evacuations are not justified. Using the Poisson analysis for evacuation risks and the absolute L-L BEIR model for radiation risk suggests 330 mrems as a reasonable value for this threshold. The usefulness of the program in developing a technical basis to select the size of the plume exposure pathway emergency planning zone (EPZ) is discussed. Quantified evacuation risks, cost, and the current rationale upon which the EPZ is based, justify an EPZ between 5-10 miles for WASH-1400 source-terms

  18. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    International Nuclear Information System (INIS)

    Mike Murphy

    2008-01-01

    In the past, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site has been performed by the Radiological Health Instrumentation Department. Calibration and performance tests on the PM-700 personnel portal monitor were performed but there was no test program for the VM-250 vehicle portal monitor because it had never been put into service. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no program in place to test them quarterly. In April of 2007, the Material Control and Accountability (MC and A) Manager at the time decided that the program needed to be strengthened and MC and A took over performance testing of all SNM portal monitoring equipment. This paper will discuss the following activities associated with creating a performance testing program: changing the culture, learning the systems, writing procedures, troubleshooting/repairing, validating the process, control of equipment, acquisition of new systems, and running the program

  19. Site of the First Spanish Nuclear Power Stations; Los Emplazamientos de las Primeras Centrales Nucleares Espanolas

    Energy Technology Data Exchange (ETDEWEB)

    Pascual, F.; Alonso, A.; Norena, S.; Sevilla, A. [Junta de Energia Nuclear, Madrid (Spain)

    1967-09-15

    The authors analyse and describe the sites of three Spanish nuclear power stations: the Zorita station (153 M W (e )) with a pressurized water reactor and single containment; the Santa Marfa de Garofia station (380 MW (e)), with a boiling water reactor and containment by steam condensation; and the Vandellos station (480 MW(e)), with a graphite-moderated gas-cooled reactor and integrated design of the EDF-4 type. The first two are located in the interior of the country and the third on the Mediterranean coast. The paper discusses the normal criteria and the safety considerations governing the choice of site, and points out the influence of Spanish orography on the transport of heavy equipment and hence its repercussions on the selection of power station sites. Reference is made to the experience acquired in transporting equipment for the Z-orita plant, and an analysis of the practical difficulties encountered in applying particular safety standards to the sites of stations of different types and designs is included. As the type of reactor and its containment system affect the practical value of applying particular standards which, moreover, have to be adapted to the special features of each country, safety standards for assessing power station sites should be applied in an appropriate and flexible manner. The paper describes the geological and meteorological features of the three sites and summarizes the studies carried out in these fields. It refers particularly to the hydrological studies carried out at Zorita and Santa Maria de Garofia and describes the weather stations set up at both sites, the diffusion experiments with neutcal-buoyancy balloons at Santa Maria de Garofia, and the results of these investigations. (author) [Spanish] Se analizan y describen los emplazamientos de tres centrales nucleares espanolas: la central de Zorita, de 153 MW(e), con reactor de agua a presion y sistema de contencion simple; la central de Santa Maria de Garofia, de 380 MW

  20. Magnox Electric plc's strategy for decommissioning its nuclear licensed sites

    International Nuclear Information System (INIS)

    2002-02-01

    The 1995 White Paper 'Review of Radioactive Waste Management Policy: Final Conclusions', Cm 2919, determined that the Government would ask all nuclear operators to draw up strategies for the decommissioning of their redundant plant and that the Health and Safety Executive (HSE) would review these strategies on a quinquennial basis in consultation with the environment agencies. This review has considered Magnox Electric pie (Magnox Electric) arrangements for the identification of its responsibilities for decommissioning and radioactive waste management, the quantification of the work entailed, the standards and timing of the work, and the arrangements to provide the financial resources to undertake the work. This is the second review by the HSE in response to Cm 2919 of Magnox Electric's nuclear power station decommissioning and radioactive waste management strategies and is based on the situation in April 2000. It reports the Nuclear Installations Inspectorate's (NIl) view that the strategies proposed by Magnox Electric are appropriate. The strategies are considered to be largely consistent with both national and international policy statements and guidance, and are potentially flexible enough to be able to accommodate lessons learned during ongoing decommissioning activities. During the review the Nil has considered whether Magnox Electric has identified all the tasks required to fully decommission its sites. Generally this has been found to be the case. Some additional tasks have been identified due, in part, to the reviewers' noting the changes which have recently taken place in environmental expectations. At this time, on the basis of the information presented, and with the provisos stated below, Magnox Electric's provisioning for final dismantling after 85 years is considered to be reasonable. The Nil expects Magnox Electric to further justify why a shorter timescale is not reasonably practicable before the next review. One of the purposes of this review

  1. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. Chapter 3 summarizes present knowledge of the regional and site hydrologic systems. The purpose of the information presented is to (1) describe the hydrology based on available literature and preliminary site-exploration activities that have been or are being performed and (2) provide information to be used to develop the hydrologic aspects of the planned site characterization program. Chapter 4 contains geochemical information about the Yucca Mountain site. The chapter references plan for continued collection of geochemical data as a part of the site characterization program. Chapter 4 describes and evaluates data on the existing climate and site meterology, and outlines the suggested procedures to be used in developing and validating methods to predict future climatic variation. 534 refs., 100 figs., 72 tabs.

  2. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 2

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. Chapter 3 summarizes present knowledge of the regional and site hydrologic systems. The purpose of the information presented is to (1) describe the hydrology based on available literature and preliminary site-exploration activities that have been or are being performed and (2) provide information to be used to develop the hydrologic aspects of the planned site characterization program. Chapter 4 contains geochemical information about the Yucca Mountain site. The chapter references plan for continued collection of geochemical data as a part of the site characterization program. Chapter 4 describes and evaluates data on the existing climate and site meterology, and outlines the suggested procedures to be used in developing and validating methods to predict future climatic variation. 534 refs., 100 figs., 72 tabs

  3. Surface Disturbances at the Punggye-ri Nuclear Test Site: Another Indicator of Nuclear Testing?

    Energy Technology Data Exchange (ETDEWEB)

    Pabian, Frank V. [Los Alamos National Laboratory; Coblentz, David [Los Alamos National Laboratory

    2017-02-03

    A review of available very high-resolution commercial satellite imagery (bracketing the time of North Korea’s most recent underground nuclear test on 9 September 2016 at the Punggye-ri Underground Nuclear Test Site) has led to the detection and identification of several minor surface disturbances on the southern flank of Mt. Mantap. These surface disturbances occur in the form of small landslides, either alone or together with small zones of disturbed bare rock that appear to have been vertically lofted (“spalled”) as a result of the most recent underground explosion. Typically, spall can be uniquely attributed to underground nuclear testing and is not a result of natural processes. However, given the time gap of up to three months between images (pre- and post-event), which was coincident with a period of heavy typhoon flooding in the area1, it is not possible to determine whether the small landslides were exclusively explosion induced, the consequence of heavy rainfall erosion, or some combination of the two.

  4. Independent verification in operations at nuclear power plants: Summaries of site visits

    International Nuclear Information System (INIS)

    Donderi, D.C.; Smiley, A.; Ostry, D.J.; Moray, N.P.

    1995-09-01

    A critical review of approaches to independent verification in operations used in nuclear power plant quality assurance programs in other countries was conducted and are detailed in volume 1. This paper is a compilation of the visits to nuclear power plant sites to study independent verification in operations at sites in Canada, USA, Japan, United Kingdom, France and Germany. 3 tabs., 22 figs

  5. Site selection and evaluation for nuclear power plants with respect to population distribution

    International Nuclear Information System (INIS)

    1980-01-01

    This safety guide, relating population distribution to site selection and evaluation, for nuclear power plants, forms part of the IAEA's programme, referred to as the NUSS programme (Nuclear Safety Standards). The guide presents population distribution data, requirements, examples of site screening methods, and an overview of radiological impact assessment with respect to population distribution

  6. From nuclear installation to greenfield site. SCK-CEN develops a new measurement method

    International Nuclear Information System (INIS)

    2014-01-01

    The article discusses a new measurement method that has been developed by the Belgian Nuclear Research Center SCK-CEN in conjunction with the decommissioning of nuclear facilities. This measurement technique is based on on-site gamma ray spectrometry in combination with modelling and is employed for directing the flow of demolition materials in the decommissioning of nuclear facilities.

  7. Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Fellows, W.S.; Sharp, J.M.; Benator, B.I.

    1978-06-01

    A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis.

  8. Nuclear Energy Center study. Phase II. Site suitability analysis. Final report

    International Nuclear Information System (INIS)

    Fellows, W.S.; Sharp, J.M.; Benator, B.I.

    1978-06-01

    A site screening study was conducted to identify a site or sites for detailed, site-specific study as a nuclear energy center. Using technical criteria of water requirements, geotechnical constraints, and projected load center and transmission considerations as well as environmental and institutional considerations, five potential study sites in the State of South Carolina were identified, evaluated against established criteria, and ranked according to their acceptability as potential nuclear energy center study sites. Consideration of what is ''representative'' of a site as well as the ranking score was factored into site recommendations, since the site deemed easiest to license and permit may not be the most desirable site for future study of the technical and institutional feasibility and practicality of a specific site. The sites near Lake Hartwell and the Savannah River Plant (SRP) of the Department of Energy were selected as potential study sites after consideration of the above criteria. Because the Lake Hartwell site offers the opportunity to consider institutional issues which may be more representative of other possible NEC sites, it is recommended that the Lake Hartwell site be studied to establish the feasibility and practicality of the nuclear energy concept on a site-specific basis

  9. Resettlement of Bikini Atoll: US nuclear test site

    International Nuclear Information System (INIS)

    Robison, W.; Conrado, C.; Stuart, M.; Stoker, A.; Hamilton, T.

    1999-01-01

    Bikini Atoll was one of two sites in the Marshall Islands that were used in the 1950's by the United States for testing nuclear weapons. The testing produced widespread radioactive contamination in Bikini and much of the Northern Marshall Islands. The Bikini people, relocated in 1946 before the test program began, have long desired to return to their homeland. Coral soil on Bikini Island makes cesium-137 ( 137 Cs) much more available for plant uptake than do soils of North America and Europe. Hence, when locally grown crops mature and become available for consumption, the resulting body burden of 137 Cs and the associated doses to humans exceeds federal guidelines. The dose from the terrestrial food ingestion pathway dominates all other pathways and contributes about 90% of the total dose to returning residents. We are, therefore, involved in cost-effective efforts to reduce the dose associated with resettlement. We have evaluated several measures, in addition to soil removal, to eliminate 137 Cs from the soil and to reduce its uptake into food crops. The most effective, and the easiest to implement, is the application of potassium to the atoll soils. A dramatic reduction in 137 Cs occurs in tropical fruits after applications of potassium-rich fertilizer to experimental soil plots. This treatment reduces the associated ingestion dose to about 5% of the pre-treatment levels, and this option avoids removal of the organic-rich surface soils. In addition, the added potassium increases plant productivity. We are now focusing on determining the duration of the effects of potassium treatment on 137 Cs uptake into plants, and the rate of environmental loss of 137 Cs in the atoll ecosystem. (author)

  10. Regulatory requirements for nuclear power plant site selection in Malaysia-a review.

    Science.gov (United States)

    Basri, N A; Hashim, S; Ramli, A T; Bradley, D A; Hamzah, K

    2016-12-01

    Malaysia has initiated a range of pre-project activities in preparation for its planned nuclear power programme. Clearly one of the first steps is the selection of sites that are deemed suitable for the construction and operation of a nuclear power plant. Here we outline the Malaysian regulatory requirements for nuclear power plant site selection, emphasizing details of the selection procedures and site characteristics needed, with a clear focus on radiation safety and radiation protection in respect of the site surroundings. The Malaysia Atomic Energy Licensing Board (AELB) site selection guidelines are in accord with those provided in International Atomic Energy Agency (IAEA) and United Stated Nuclear Regulatory Commission (USNRC) documents. To enhance the suitability criteria during selection, as well as to assist in the final decision making process, possible assessments using the site selection characteristics and information are proposed.

  11. Manual on quality assurance for the survey, evaluation and confirmation of nuclear power plant sites

    International Nuclear Information System (INIS)

    1987-04-01

    The present Manual on Quality Assurance for the Survey, Evaluation and Confirmation of Nuclear Power Plant Sites contains supporting material and illustrates examples for implementing the requirements contained in the Code of Practice on Quality Assurance for Safety in Nuclear Power Plants to the activities of survey, evaluation and confirmation of nuclear power plant sites. At the same time the Code of Practice for Safety in Nuclear Power Plant Siting, and Safety Guides in the siting series contain requirements and recommendations to implement a quality assurance programme in selected activities of the siting process. This manual is intended to provide guidance and illustrate examples on this implementation. During preparation and reviews of this Manual it was found out that the methodology of implementation of the quality assurance programme in siting activities is still under development. For these reasons it was considered appropriate to publish this Manual as a temporary publication for trial use

  12. Principles of off-site nuclear emergency exercises

    International Nuclear Information System (INIS)

    Miska, H.

    2011-01-01

    Due to high safety standards at nuclear power plants, no experience exits with nuclear emergencies in Western Europe. Thus, emergency exercises are the only possibility to assure effective protective measures should the very unlikely severe accident occur. The main objectives of exercises are generally the check of response plans for suitability, the test of the equipment's applicability and training of personnel for the unusual task to manage a nuclear emergency. After an introduction into the different types of exercises, this contribution focuses on offsite nuclear emergency exercises, explaining frame conditions to ensure good practice and, finally, reports some experience from exercises. (orig.)

  13. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 7

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Neavada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining hte geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare and environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed

  14. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 4

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package; and to present the plans for obtaining the geologic information necessary to demonstate the suitability of the site for a repository, to desin the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next; it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed

  15. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  16. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 7

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Neavada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining hte geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare and environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  17. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package; and to present the plans for obtaining the geologic information necessary to demonstate the suitability of the site for a repository, to desin the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next; it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  18. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in acordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and eveloping a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing prinicples, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed. 880 refs., 130 figs., 25 tabs.

  19. Demographic survey around proposed nuclear power plant site in Haryana covering 30 km radius area from the site

    International Nuclear Information System (INIS)

    Garg, V.K.

    2013-01-01

    This study was planned to have a demographic survey of the households living within 30 km radius of the proposed site. Objectives of the present study were to attain the quantitative baseline demographic data around (within 30 km radius) the proposed site of nuclear power plant, zone-wise and sector-wise distribution of the population around proposed site up to a distance of 30 km from the site, to obtain the data on socio-economic, cultural, and religious perspectives of the target populations, to obtain the data on disease/illness pattern in the target population, health status and mortality rate

  20. Characterization of Pu-contaminated soils from Nuclear Site 201 at the Nevada Test Site

    International Nuclear Information System (INIS)

    Lee, S.Y.; Tamura, T.; Larsen, I.L.

    1983-01-01

    Distribution and characteristics of Pu-bearing radioactive particles throughout five soil profiles from Nuclear Site (NS) 201 were investigated. Concentrations of 239 240 Pu and 241 Am decreased with depth and most of the contamination was contained in the top 5 cm except in profile 4 where it extended to 10 cm. The mean activity ratio of 239 240 Pu to 241 Am and its standard error were 5.8 +- 0.3 (N=42). Most of the total radioactivity of the soils was contributed by 0.25 to 2 mm sand size fraction which comprised 20 to 50% by weight of the soils. The radioactive particles in the 0.25 to 2 mm size fraction occurred as spherical glass particles or as glass coatings on sand particles. The glass coatings had gas voids in the matrix but were not as porous as the radioactive particles from NS 219. After impact grinding the >0.25-mm size fractions for one hour, 85% of the initial activity in a NS 201 sample remained with the particles on the 0.25 mm sieve, whereas in the NS 219 sample only 10% remained. The results show that the radioactive particles from NS 201 were much more stable against the impact grinding force than those from NS 219. Therefore, the NS 201 soils would be expected to have a lower probability of producing respirable-size radioactive particles by saltation during wind erosion. 19 references, 3 figures, 3 tables

  1. Review Article : Utilization of Environmental Radiochemistry Techniques for Selection and Evaluation of Nuclear Facility Sites

    International Nuclear Information System (INIS)

    Atta, E.R.; Madbouly, A.M.; Zakaria, Kh.M.

    2016-01-01

    This research review puts necessary considerations on the available environmental radiochemistry techniques for selection and evaluation of a nuclear facility sites.The main bjective in site evaluation for nuclear facilities in terms of nuclear safety is to protect the site workers, the public and the environment from the effects of ionizing radiation release from nuclear facilities due to accidents. The extreme sensitivity and speed of radiochemical methods make their applications of considerable importance in several fields and they have found many uses. Information about the existed radioactivity in the different nuclear facilities is an essential requirement for their environmental assessment. It is necessary to estimate the various radioactivity levels in the environment through qualitative and quantitative analytical techniques and to assess the potential effects of the nuclear facility in the region by considering the characteristics of sites.The siting and site evaluation requirements are discussed. Emphasis was given to types of radiochemical techniques used for characterization of the site parameters which determine the potential hazards of the site on the facility and the facility on the site. Emphasis has been also given to the quantitative and qualitative analysis of naturally occurring radionuclides for monitoring and control .There are some techniques employed such as radioactive tracer technique, liquid scintillation technique, gamma spectrometry technique, neutron activation analysis technique, fluorimetric technique and isotope hydrology technique.

  2. For Sale: Nuclear Waste Sites--Anyone Buying?

    Science.gov (United States)

    Hancock, Don

    1992-01-01

    Explores why the United States Nuclear Waste Program has been unable to find a volunteer state to host either a nuclear waste repository or monitored retrieval storage facility. Discusses the Department of Energy's plans for Nevada's Yucca Mountain as a repository and state and tribal responses to the plan. (21 references) (MCO)

  3. The role of visitors centres at nuclear facility sites

    International Nuclear Information System (INIS)

    Anderiz Cebrian, D.

    1993-01-01

    The Nuclear Safety Council is the agency within the Spanish State entrusted with nuclear safety and radiological protection. Its information activities are explained. The future creation of an information centre is being considered as part of its technical divulgation programme in matters of public information. (author)

  4. Review of Investigations on Site Selection for Nuclear Power Plants in Croatia

    International Nuclear Information System (INIS)

    Malbasa, N.

    2008-01-01

    A review of site investigation for nuclear facilities in the Republic of Croatia that had been performed from 1964, when investigation started for the first nuclear power plant, to 1994 when the activities were stopped, is presented therein. Brief results of the main investigation were presented including the Tanja site on the Danube upstream of Vukovar. It is the best of all the investigated locations for nuclear power plant in Croatia. The review of results for site selection of low and intermediate level of radioactive waste disposal is also given. The position of nuclear power plants in the strategic documents of the Republic of Croatia was analysed. It is concluded that the status of nuclear facilities in the main strategic documents must be improved because the energy future in Croatia - as almost in all European countries - could hardly be successful without any further development of nuclear energy.(author)

  5. Review of Investigations on Site Selection for Nuclear Power Plants in Croatia

    Energy Technology Data Exchange (ETDEWEB)

    Malbasa, N [Ekonerg, Zagreb (Croatia)

    2008-07-01

    A review of site investigation for nuclear facilities in the Republic of Croatia that had been performed from 1964, when investigation started for the first nuclear power plant, to 1994 when the activities were stopped, is presented therein. Brief results of the main investigation were presented including the Tanja site on the Danube upstream of Vukovar. It is the best of all the investigated locations for nuclear power plant in Croatia. The review of results for site selection of low and intermediate level of radioactive waste disposal is also given. The position of nuclear power plants in the strategic documents of the Republic of Croatia was analysed. It is concluded that the status of nuclear facilities in the main strategic documents must be improved because the energy future in Croatia - as almost in all European countries - could hardly be successful without any further development of nuclear energy.(author)

  6. Study of a conceptual nuclear energy center at Green River, Utah. Site selection

    International Nuclear Information System (INIS)

    1981-08-01

    The siting requirements are described for a NEC. The methodology used, primary and secondary screening criteria and the results and conclusions are also presented. Appended to the report are detailed discussions of two siting factors, and evaluation of Nuclear Regulatory Commission (NRC) demographic siting criteria and a fatal flaw analyses for terrestrial and aquatic ecology

  7. Study of a conceptual nuclear energy center at Green River, Utah. Site selection

    Energy Technology Data Exchange (ETDEWEB)

    1981-08-01

    The siting requirements are described for a NEC. The methodology used, primary and secondary screening criteria and the results and conclusions are also presented. Appended to the report are detailed discussions of two siting factors, and evaluation of Nuclear Regulatory Commission (NRC) demographic siting criteria and a fatal flaw analyses for terrestrial and aquatic ecology.

  8. Developing a Hierarchical Decision Model to Evaluate Nuclear Power Plant Alternative Siting Technologies

    Science.gov (United States)

    Lingga, Marwan Mossa

    A strong trend of returning to nuclear power is evident in different places in the world. Forty-five countries are planning to add nuclear power to their grids and more than 66 nuclear power plants are under construction. Nuclear power plants that generate electricity and steam need to improve safety to become more acceptable to governments and the public. One novel practical solution to increase nuclear power plants' safety factor is to build them away from urban areas, such as offshore or underground. To date, Land-Based siting is the dominant option for siting all commercial operational nuclear power plants. However, the literature reveals several options for building nuclear power plants in safer sitings than Land-Based sitings. The alternatives are several and each has advantages and disadvantages, and it is difficult to distinguish among them and choose the best for a specific project. In this research, we recall the old idea of using the alternatives of offshore and underground sitings for new nuclear power plants and propose a tool to help in choosing the best siting technology. This research involved the development of a decision model for evaluating several potential nuclear power plant siting technologies, both those that are currently available and future ones. The decision model was developed based on the Hierarchical Decision Modeling (HDM) methodology. The model considers five major dimensions, social, technical, economic, environmental, and political (STEEP), and their related criteria and sub-criteria. The model was designed and developed by the author, and its elements' validation and evaluation were done by a large number of experts in the field of nuclear energy. The decision model was applied in evaluating five potential siting technologies and ranked the Natural Island as the best in comparison to Land-Based, Floating Plant, Artificial Island, and Semi-Embedded plant.

  9. The siting of nuclear power stations in Britain

    International Nuclear Information System (INIS)

    Wright, H.A.

    1975-01-01

    It is a fundamental precept that all prudent precautions should be taken. The secondary contribution to public safety derived by a proper choice of site must therefore be utilised. A siting policy should limit the choice of site but give the Utility sufficient freedom of choice to enable the more remote sites to be available for the adoption of new reactor types. For a significant release few people should be affected sufficiently to require evacuation, and account must also be taken of population centres possibly up to 20 miles from the site. (orig.) [de

  10. Nuclear scaffold attachment sites within ENCODE regions associate with actively transcribed genes.

    Directory of Open Access Journals (Sweden)

    Mignon A Keaton

    2011-03-01

    Full Text Available The human genome must be packaged and organized in a functional manner for the regulation of DNA replication and transcription. The nuclear scaffold/matrix, consisting of structural and functional nuclear proteins, remains after extraction of nuclei and anchors loops of DNA. In the search for cis-elements functioning as chromatin domain boundaries, we identified 453 nuclear scaffold attachment sites purified by lithium-3,5-iodosalicylate extraction of HeLa nuclei across 30 Mb of the human genome studied by the ENCODE pilot project. The scaffold attachment sites mapped predominately near expressed genes and localized near transcription start sites and the ends of genes but not to boundary elements. In addition, these regions were enriched for RNA polymerase II and transcription factor binding sites and were located in early replicating regions of the genome. We believe these sites correspond to genome-interactions mediated by transcription factors and transcriptional machinery immobilized on a nuclear substructure.

  11. A proposal on siting counterplan of nuclear power plants

    International Nuclear Information System (INIS)

    Sasao, Hitoshi

    1980-01-01

    As for the nuclear power generation in Japan. 21 plants with 14.95 million kW capacity have started the operation in 14 years. It is equivalent to more than 12% of the total capacity of power stations. But the environment around the development of nuclear power generation becomes more and more strict recently, and the formation of the consensus of residents becomes a very large political problem. The lead time from the proposal of construction to the local community to the commencement of operation was 8 years and 1 month in the case of 10 nuclear power stations in operation, but it is extended to 15 years and 6 months in the case of 4 power stations under construction. The prefectures where nuclear power stations are located were seven at the end of 1970, and only three were added during 9 years thereafter. It shows the difficulty of the location of nuclear power stations in new prefectures. In order to attain 78 million kW of nuclear power generation by 1995, the location of 50 million kW must be decided in coming several years in view of the lead time. The progress of the studies in the Atomic Industrial Forum, the strengthening of security system in the sistricts concerned, the formation of open environment for informations, the improvement of the setup concerning the compensation to fishery and others, and the studies on the law concerning the special measures for the districts where nuclear facilities are located are discussed. (Kako, I.)

  12. Site characterization plan overview: reference repository location, Hanford Site, Washington: Consultation draft: Nuclear Waste Policy Act (Section 113)

    International Nuclear Information System (INIS)

    1988-01-01

    As part of the process for siting the nation's first geologic repository for radioactive waste, the Department of Energy (DOE) is preparing a site characterization plan for the Hanford site in Benton County, Washington. As a step in the preparation of that plan, the DOE has provided, for information and review, a consultation draft of the plan to the State of Washington, the affected Indian Tribes - the Confederated Tribes of the Umatilla Indian Reservation, the Nez Perce Indian Tribe, and the Yakima Indian Nation - and the US Nuclear Regulatory Commission. The Hanford site is one of three sites that the DOE currently plans to characterize;the other sites are the Deaf Smith County site in Texas and the Yucca Mountain site in Nevada. After site characterization has been completed and its results evaluated, the DOE will identify from among the three characterized sites the site that is preferred for the repository. The overview presented here consists of brief summaries of important topics covered in the consulation draft of the site characterization plan;it is not a substitute for the site characterization plan. The arrangement of the overview is similar to that of the plan itself, with breif descriptions of the dispoal system - the site, the repository, and the waste package - preceding the discussion of the characterization program to be carried out at the Hanford site. It is intended primarily for the management staff of organizations involved in the DOE's repository program or other persons who might wish to understand the general scope of the site-characterization program, the activities to be conducted, and the facilities to be constructed rather than the technical details of site characterization

  13. Nuclear Materials Management U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO)

    International Nuclear Information System (INIS)

    Jesse Schreiber

    2008-01-01

    In light of the changing Defense Complex mission, the high cost to storing and protecting nuclear materials, and in consideration of scarcity of resources, it is imperative that the U.S. Department of Energy (DOE) owned nuclear materials are managed effectively. The U.S. Department of Energy, National Nuclear Security Administration (NNSA) Strategic Action Plan outlines the strategy for continuing to meet America's nuclear security goals, meeting the overall mission challenges of DOE and NNSA as well as giving focus to local missions. The mission of the NNSA/NSO Nuclear Materials Management (NMM) Program is to ensure that nuclear material inventories are accurately assessed and reported, future material needs are adequately planned, and that existing Nevada Test Site (NTS) inventories are efficiently utilized, staged, or dispositioned. The NNSA/NSO understands that the NTS has unique characteristics to serve and benefit the nation with innovative solutions to the complex problems involving Special Nuclear Materials, hazardous materials, and multi-agency, integrated operations. The NNSA/NSO is defining infrastructure requirements for known future missions, developing footprint consolidation strategic action plans, and continuing in the path of facility modernization and improvements. The NNSA/NSO is striving for the NTS to be acknowledged as an ideal location towards mission expansion and growth. The NTS has the capability of providing isolated, large scale construction and development locations for nuclear power or alternate energy source facilities, expanded nuclear material storage sites, and for new development in 'green' technology

  14. CNN's evaluation of the radiological monitoring special programs at the sites of nuclear installations

    International Nuclear Information System (INIS)

    Lareyne, O.; Marugan Tovar, I.; Martinez Moreno, M.; Sanz Alduan, M. T.

    2011-01-01

    In 2008, occurred in the Spanish plants various events related to the existence on the sites of the Spanish nuclear facilities or areas dotted with radioactive contamination outside the buildings, events that were reported to the Nuclear Safety Council (CSN) in accordance with the provisions of the regulation, as a result of the analysis of those events, the CSN issued in July 2008, a complementary technique INSTRUCTIONAL requiring the implementation of environmental monitoring programs in outdoor areas within sites nuclear tacilities. First, the CSN nuclear facilities referred to the programs and methodologies intended to perform such monitoring, and, in late 2009, reports of program results.

  15. Draft environmental assessment: Cypress Creek Dome site, Mississippi. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Cypress Creek dome site in Mississippi as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Cypress Creek dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Cypress Creek dome site is not disqualified under the guidelines. The site is contained in the Gulf Interior Region of the Gulf Coastal Plain, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains two other potentially acceptable sites - the Richton dome site and the Vacherie dome site. Although the Cypress Creek dome site appears to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region and is proposing to nominate the Richton dome site rather than the Cypress Creek dome site as one of the three sites suitable for characterization

  16. Nuclear power plant site evaluation using site population-meterology factor

    International Nuclear Information System (INIS)

    Rho, B.H.; Kang, C.H.

    1982-01-01

    In this paper, as a site evaluation technique, SPNF(Site Population Neteorology Factor) which is modified from SPF(Site Population Factor) of the USNRC model, is defined from site population and meteorology data in order to consider the radiological impacts to the population at large from the atmospheric dispersion of the radioactive effluents released during routine plant operation as well as accidental conditions. The SPMF model proved its propriety from the comparison of SPMF and SPF for Kori site. The relative suitability of Korean sites to the U.S. sites have been also examined using SPF. (Author)

  17. Ecological studies of small mammals in a nuclear site on Nevada Test Site

    International Nuclear Information System (INIS)

    Bradley, W.G.; Moor, K.S.

    1978-01-01

    Ecological studies of small vertebrates in nuclear event sites in NTS began in spring 1977 with the establishment of a permanent live-trapping grid in Little Feller II. These study areas are located in Area 18, a relatively homogeneous area vegetatively and topographically. Most of the flora and fauna are typical of the Great Basin desert found in southern Nevada. Dominant vegetation includes Artemesia spp. and to a lesser extent Atriplex. Salsola is an abundant weed in areas that have been mechanically disturbed such as the vicinity of GZ. A 400-station live-trapping grid was established in Little Feller II, April 1977. Sixteen lines of live traps (25 traps per line, each trap 50 feet apart) comprise the 8.4 hectare grid encompassing GZ. Nine trapping periods have been completed to date totaling over 10,000 trap nights. Over 400 small vertebrates have been marked for permanent identification in the grid. Over 60 known residents (animals marked 3 months previously and recaptured in the same vicinity) have been collected and prepared for shipping; however, radioanalytical results were not available to include in this report. Both census and field note observations were used to develop an inventory of the vertebrates found in the study areas. Sufficient data have been generated from Little Feller II to estimate density of rodents. These data and comparative data from Area 5 (Mohave Desert), Area 11 (Transition), and Area 13 (Great Basin) are presented. It was readily apparent that rodents in general were more numerous in Little Feller II. In addition, Dipodomys ordii, a Great Basin species, was an important new addition to the rodent fauna

  18. Seismic Hazards in Site Evaluation for Nuclear Installations. Specific Safety Guide

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-08-15

    This Safety Guide was prepared under the IAEA programme for safety standards for nuclear installations. It supplements the Safety Requirements publication on Site Evaluation for Nuclear Installations. The present publication provides guidance and recommends procedures for the evaluation of seismic hazards for nuclear power plants and other nuclear installations. It supersedes Evaluation of Seismic Hazards for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.3 (2002). In this publication, the following was taken into account: the need for seismic hazard curves and ground motion spectra for the probabilistic safety assessment of external events for new and existing nuclear installations; feedback of information from IAEA reviews of seismic safety studies for nuclear installations performed over the previous decade; collective knowledge gained from recent significant earthquakes; and new approaches in methods of analysis, particularly in the areas of probabilistic seismic hazard analysis and strong motion simulation. In the evaluation of a site for a nuclear installation, engineering solutions will generally be available to mitigate, by means of certain design features, the potential vibratory effects of earthquakes. However, such solutions cannot always be demonstrated to be adequate for mitigating the effects of phenomena of significant permanent ground displacement such as surface faulting, subsidence, ground collapse or fault creep. The objective of this Safety Guide is to provide recommendations and guidance on evaluating seismic hazards at a nuclear installation site and, in particular, on how to determine: (a) the vibratory ground motion hazards, in order to establish the design basis ground motions and other relevant parameters for both new and existing nuclear installations; and (b) the potential for fault displacement and the rate of fault displacement that could affect the feasibility of the site or the safe operation of the installation at

  19. Draft environmental assessment: Vacherie Dome site, Louisiana. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Vacherie dome in Louisiana as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Vacherie dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Vacherie dome site is not disqualified under the guidelines. The site is contained in the Gulf Interior Region of the Gulf Coastal Plain, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains two other potentially acceptable sites - the Cypress Creek dome site and the Richton dome site. Although the Vacherie dome site appears to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region. On the basis of these findings, the DOE is proposing to nominate the Richton dome site rather than the Vacherie dome site as one of the five sites suitable for characterization

  20. Draft environmental assessment: Swisher County site, Texas. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified a location in Swisher County, Texas, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The potentially acceptable site was subsequently narrowed to an area of 9 square miles. To determine their suitability, the Swisher site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Swisher site is not disqualified under the guidelines. The site is contained in the Permian Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Deaf Smith site. Although the Swisher site appears to be suitable for site characterization, the DOE has concluded that the Deaf Smith site is the preferred site in the Permian Basin and is proposing to nominate the Deaf Smith site rather than the Swisher site as one of the five sites suitable for characterization

  1. Draft environmental assessment: Lavender Canyon site, Utah. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Lavender Canyon site in Utah, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Lavender Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Lavender Canyon site is not disqualified under the guidelines. The site is contained in the Paradox Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Davis Canyon site. Although the Lavender Canyon site appears to be suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. On the basis of these findings, the DOE is proposing to nominate the Davis Canyon site rather than the Lavender Canyon site as one of the five sites suitable for characterization

  2. Draft environmental assessment: Richton Dome site, Mississippi. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy identified the Richton dome site as one of the nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Richton dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Richton dome site is not disqualified under the guidelines. The site is in the Gulf Interior Region of the Gulf Coastal Plain. This setting contains two other potentially acceptable sites - the Cypress Creek dome site and the Vacherie dome site. Although these other two sites appear to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region. Furthermore, the DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Richton dome site as one of five sites suitable for characterization. Having compared the Richton dome site with the other four sites proposed for nomination, the DOE has determined that the Richton dome site is not one of the three preferred sites for recommendation to the President as candidates for characterization

  3. Around Semipalatinsk nuclear test site: Progress of dose estimations relevant to the consequences of nuclear tests

    International Nuclear Information System (INIS)

    Stepanenko, Valeriy F.; Hoshi, Masaharu; Bailiff, Ian K.

    2006-01-01

    The paper is an analytical overview of the main results presented at the 3rd Dosimetry Workshop in Hiroshima (9-11 of March 2005), where different aspects of the dose reconstruction around the Semipalatinsk nuclear test site (SNTS) were discussed and summarized. The results of the international intercomparison of the retrospective luminescence dosimetry (RLD) method for Dolon' village (Kazakhstan) were presented at the Workshop and good concurrence between dose estimations by different laboratories from 6 countries (Japan, Russia, USA, Germany, Finland and UK) was pointed out. The accumulated dose values in brick for a common depth of 10 mm depth of 10 mm depth obtained independently by all participating laboratories were in good agreement for all four brick samples from Dolon' village, Kazakhstan, with the average value of the local gamma dose due to fallout (near the sampling locations) being about 220 mGy (background dose has been subtracted). Furthermore, using a conversion factor of about 2 to obtain the free-in-air dose, a value of local dose ∼440 mGy is obtained, which supports the results of external dose calculations for Dolon': recently published soil contamination data, archive information and new models were used for refining dose calculations and the external dose in air for Dolon village was estimated to be about 500 mGy. The results of electron spin resonance (ESR) dosimetry with tooth enamel have demonstrated the notable progress in application of ESR dosimetry to the problems of dose reconstruction around the Semipalatinsk nuclear test site. At the present moment, dose estimates by the ESR method have become more consistent with calculated values and with retrospective luminescence dosimetry data, but differences between ESR dose estimates and RLD/calculation data were noted. For example mean ESR dose for eligible tooth samples from Dolon' village was estimated to be about 140 mGy (above background dose), which is less than dose values obtained

  4. Draft environmental assessment: Davis Canyon site, Utah. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Davis Canyon site in Utah, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Davis Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Davis Canyon site is not disqualified under the guidelines. The site is in the Paradox Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Lavender Canyon site. Although the Lavender Canyon site appears to be suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. Furthermore, the DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Davis Canyon site as one of five sites suitable for characterization. Having compared the Davis Canyon site with the other four sites proposed for nomination, the DOE has determined that the Davis Canyon site is not one of the three preferred sites for recommendation to the President as candidates for characterization

  5. Draft environmental assessment: Deaf Smith County site, Texas. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy identified a location in Deaf Smith County, Texas, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The potentially acceptable site was subsequently narrowed to an area of 9 square miles. To determine their suitability, the Deaf Smith site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment, which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Deaf Smith site is not disqualified under the guidelines. The site is in the Permian Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Swisher site. Although the Swisher site appears to be suitable for site characterization, DOE has concluded that the Deaf Smith site is the preferred site. The DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Deaf Smith site as one of five sites suitable for characterization. Having compared the Deaf Smith site with the other four sites proposed for nomination, the DOE has determined that the Deaf Smith site is one of the three preferred sites for recommendation to the President as candidates for characterization

  6. Residual radioactivity in the soil of the Semipalatinsk Nuclear Test Site in the former USSR

    International Nuclear Information System (INIS)

    Yamamoto, Masayoshi; Tsukatani, Tsuneo; Katayama, Yukio

    1996-01-01

    This paper deals with our efforts to survey residual readioactivity in the soil sampled at teh Semipalatinsk Nuclear Test Site and at off-site areas in Kazakhstan. The soil sampled at the hypocenter where the first Soviet nuclear explosion was carried out on 29 August 1949, and at the bank of the crater called open-quotes Bolapan,close quotes which was formed by an underground nuclear detonation on 15 January 1965 along the Shagan River. As a comparison, other soil was also sampled in the cities of Kurchatov and Almaty. These data have allowed a preliminary evaluation of the contemporary radioactive contamination of the land in and around the test site. At the first nuclear explosion site and at Bolapan, higher than background levels of 239,240 Pu with weapons-grade plutonium were detected together with fission and activation products such as 137 Cs, 60 Co, 152 Eu, and 154 Eu. 20 refs., 3 figs., 5 tabs

  7. Residual radioactivity in the soil of the Semipalatinsk Nuclear Test Site in the former USSR.

    Science.gov (United States)

    Yamamoto, M; Tsukatani, T; Katayama, Y

    1996-08-01

    This paper deals with our efforts to survey residual radioactivity in the soil sampled at the Semipalatinsk Nuclear Test Site and at off-site areas in Kazakhstan. The soil was sampled at the hypocenter where the first Soviet nuclear explosion was carried out on 29 August 1949, and at the bank of the crater called "Bolapan," which was formed by an underground nuclear detonation on 15 January 1965 along the Shagan River. As a comparison, other soil was also sampled in the cities of Kurchatov and Almaty. These data have allowed a preliminary evaluation of the contemporary radioactive contamination of the land in and around the test site. At the first nuclear explosion site and at Bolapan, higher than background levels of 239,240Pu with weapons-grade plutonium were detected together with fission and activation products such as 137Cs, 60Co, 152Eu, and 154Eu.

  8. Population Health in Regions Adjacent to the Semipalatinsk Nuclear Test Site

    National Research Council Canada - National Science Library

    1998-01-01

    ...) of the Union of Soviet Socialist Republics (USSR). Inhabitants of several Kazakhstan regions were contaminated in different years by radioactive fallout from atmospheric nuclear tests at the Semipalatinsk test site...

  9. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes

    Energy Technology Data Exchange (ETDEWEB)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This is part 2 of a bibliography on nuclear facility decommissioning and site remedial action. This report contains indexes on the following: authors, corporate affiliation, title words, publication description, geographic location, subject category, and key word.

  10. Canada's Deep Geological Repository for Used Nuclear Fuel - Geo-scientific Site Evaluation Process - 13117

    International Nuclear Information System (INIS)

    Blyth, Alec; Ben Belfadhel, Mahrez; Hirschorn, Sarah; Hamilton, Duncan; McKelvie, Jennifer

    2013-01-01

    The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management (APM), the approach selected by the Government of Canada for long-term management of used nuclear fuel generated by Canadian nuclear reactors. The ultimate objective of APM is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable rock formation at a depth of approximately 500 meters (m) (1,640 feet [ft]). In May 2010, the NWMO published a nine-step site selection process that serves as the road map to decision-making on the location for the deep geological repository. The safety and appropriateness of any potential site will be assessed against a number of factors, both technical and social in nature. The selected site will be one that can be demonstrated to be able to safely contain and isolate used nuclear fuel, protecting humans and the environment over the very long term. The geo-scientific suitability of potential candidate sites will be assessed in a stepwise manner following a progressive and thorough site evaluation process that addresses a series of geo-scientific factors revolving around five safety functions. The geo-scientific site evaluation process includes: Initial Screenings; Preliminary Assessments; and Detailed Site Evaluations. As of November 2012, 22 communities have entered the site selection process (three in northern Saskatchewan and 18 in northwestern and southwestern Ontario). (authors)

  11. Nuclear Waste Risk Perceptions and Attitudes in Siting a Final Repository for Spent Nuclear Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Sjoeberg, Lennart [Stockholm School of Economics (Sweden). Center for Risk Research

    2006-09-15

    The paper does the following: Describes the time trends between 2001 and 2005 in terms of policy intention, perceived risk, trust and attitude Analyzes the relationships between policy attitude - the major dependent variable - and the explanatory variables of perceived risk, trust and attitude. Determines whether policy attitude variation across time, municipalities and genders can be accounted for by variation in perceived risk, trust and attitude. Random samples of 2000 persons living in Oesthammar and Oskarshamn were approached with a mailed questionnaire in 2005 (as was done in 2005). After two reminders, 888 had returned filled out questionnaires, yielding a total response rate of 50 percent, taking into account that some persons had moved without giving a forwarding address to the post office, and that some were unable to answer due to illness or old age. (1). There was a substantially more positive attitude to a local SNF repository in 2005 than in 2001, after an intervening period of phase 2 site investigation. This was true for men and women, both municipalities and with all the response measures analyzed. Men were more positive than women, and had developed more strongly in the positive direction than women had. The attitude in Oskarshamn was somewhat more positive than in Oesthammar. (2). Policy intention was well accounted for by the explanatory variables used here, close to 64 percent of the variance. The most important explanatory variables were epistemic trust, attitude to the repository and social trust, in that order. The differences among these three variables were small with regard to explanatory power. (3) Variation in policy attitude across time, municipalities and gender was reduced in an analysis of covariance with risk, trust and attitude as controlling factors. Hence, these factors explain a large fraction of the variation in policy attitude as observed here. Yet, the time trend was not fully explained and gender variability remained to

  12. Nuclear Waste Risk Perceptions and Attitudes in Siting a Final Repository for Spent Nuclear Fuel

    International Nuclear Information System (INIS)

    Sjoeberg, Lennart

    2006-01-01

    The paper does the following: Describes the time trends between 2001 and 2005 in terms of policy intention, perceived risk, trust and attitude Analyzes the relationships between policy attitude - the major dependent variable - and the explanatory variables of perceived risk, trust and attitude. Determines whether policy attitude variation across time, municipalities and genders can be accounted for by variation in perceived risk, trust and attitude. Random samples of 2000 persons living in Oesthammar and Oskarshamn were approached with a mailed questionnaire in 2005 (as was done in 2005). After two reminders, 888 had returned filled out questionnaires, yielding a total response rate of 50 percent, taking into account that some persons had moved without giving a forwarding address to the post office, and that some were unable to answer due to illness or old age. (1). There was a substantially more positive attitude to a local SNF repository in 2005 than in 2001, after an intervening period of phase 2 site investigation. This was true for men and women, both municipalities and with all the response measures analyzed. Men were more positive than women, and had developed more strongly in the positive direction than women had. The attitude in Oskarshamn was somewhat more positive than in Oesthammar. (2). Policy intention was well accounted for by the explanatory variables used here, close to 64 percent of the variance. The most important explanatory variables were epistemic trust, attitude to the repository and social trust, in that order. The differences among these three variables were small with regard to explanatory power. (3) Variation in policy attitude across time, municipalities and gender was reduced in an analysis of covariance with risk, trust and attitude as controlling factors. Hence, these factors explain a large fraction of the variation in policy attitude as observed here. Yet, the time trend was not fully explained and gender variability remained to

  13. Nuclear Energy Center Site Survey, 1975. Part II. The U.S. electric power system and the potential role of nuclear energy centers

    International Nuclear Information System (INIS)

    1976-01-01

    Information related to Nuclear Energy Centers (NEC) in the U.S. is presented concerning the U.S. electric power system today; electricity demand history and forecasts; history and forecasts of the electric utility industry; regional notes; the status, history, and forecasts of the nuclear role; power plant siting problems and practices; nuclear facilities siting problems and practices; origin and evolution of the nuclear energy center concept; conceptualized description of nuclear energy centers; potential role of nuclear energy centers; assumptions, criteria, and bases; typical evolution of a nuclear energy center; and the nuclear fuel cycle

  14. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended by the Secretary of Energy and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared by the US Department of Energy (DOE) in accordance with the requirements of the Nulcear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of the site characterization plan are oulined, and compliance with applicable regulations is discussed

  15. Consultation draft: Site characterization plan overview, Deaf Smith County Site, Texas: Nuclear Waste Policy Act (Section 113)

    International Nuclear Information System (INIS)

    1988-01-01

    The Department of Energy (DOE) is preparing a site characterization plan for the candidate site in Deaf Smith County, Texas. The DOE has provided, for information and review, a consultation draft of the plan to the State of Texas and the US Nuclear Regulatory Commission. The site characterization plan is a lengthy document that describes in considerable detail the program that will be conducted to characterize the geologic, hydrologic, and other conditions relevant to the suitability of the site for a repository. The overview presented here consists of brief summaries of important topics covered in the consultation draft of the site characterization plan; it is not a substitute for the site characterization plan. The arrangement of the overview is similar to that of the plan itself, with brief descriptions of the repository system - the site, the repository, and the waste package - preceding the discussion of the characterization program to be carried out at the Deaf Smith County site. It is intended primarily for the management staff of organizations involved in the DOE's repository program or other persons who might wish to understand the general scope of the site-characterization program, the activities to be conducted, and the facilities to be constructed rather than the technical details of site characterization. 15 figs., 1 tab

  16. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended by the Secretary of Energy and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared by the US Department of Energy (DOE) in accordance with the requirements of the Nulcear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of the site characterization plan are oulined, and compliance with applicable regulations is discussed.

  17. [Study on Tritium Content in Soil at Sites of Nuclear Explosions on the Territory of Semipalatinsk Test Site].

    Science.gov (United States)

    Timonova, L V; Lyakhova, O N; Lukashenko, S N; Aidarkhanov, A O

    2015-01-01

    As a result of investigations carried out on the territory of Semipalatinsk Test Site, tritium was found in different environmental objects--surface and ground waters, vegetation, air environment, and snow cover. The analysis of the data obtained has shown that contamination of environmental objects at the Semipalatinsk Test Site with tritium is associated with the places where underground nuclear tests were performed. Since tritium can originate from an activation reaction and be trapped by pock particles during a test, it was decided to examine the soil in the sites where surface and excavation tests took place. It was found that the concentration of tritium in soil correlates with the concentration of europium. Probably, the concentration of tritium in the soil depends on the character and yield of the tests performed. Findings of the study have revealed that tritium can be found in soil in significant amounts not only in sites where underground nuclear tests took place but also in sites where surface and excavation nuclear tests were carried out.

  18. The environment of the nuclear test sites on Novaya Zemlya

    International Nuclear Information System (INIS)

    Skorve, J.

    1995-01-01

    A Norwegian study of the effects of Soviet nuclear testing on the arctic island of Novaya Zemlya is underway. The study has used aerial photographs and satellite images and has revealed major rockslides and crater features that may be attributable to testing. It has been claimed that underground testing carries little risk of post-explosion contaminant release, as the explosion vitrifies and seals the surrounding rock mass. Some experts doubt the validity of this claim, and elucidation of the hydrogeological aspects of such nuclear testing is one of the aims of the study

  19. Resettlement of Bikini Atoll U.S. Nuclear Test Site

    International Nuclear Information System (INIS)

    Robinson, W.L.; Conrado, C.L.; Stuart, M.L.; Stoker, A.C.; Hamilton, T.F.

    1999-01-01

    The US conducted a nuclear testing program at Bikini and Enewetak Atolls in the Marshall Islands from 1946 through 1958. Several atolls, including Bikini, were contaminated as a result of the nuclear detonations. Since 1974 the authors have conducted an extensive research and monitoring program to determine the radiological conditions at the atolls, identify the critical radionuclides and pathways, estimate the radiological dose to current or resettling populations, and develop remedial measures to reduce the dose to atoll populations. This paper describes exposure pathways and radionuclides; composition of atoll soils; radionuclide transport and dose estimates; remedial measures; and reduction in dose from a combined option

  20. Climate change research methods and its significance in the study of choosing candidate site in nuclear waste disposal sites

    International Nuclear Information System (INIS)

    Zhao Yong; Zhang Zhanshi

    2008-01-01

    A high-level nuclear waste is the inevitable product accompanies the development of the nuclear power station. How to dispose it properly has become focused by all over the world. Some of the important progresses have been achieved in the fields of site setting, performance assessment and underground laboratory recently. Palaeoclimate patter and the tendency of climate change are very important aspects for the site setting This paper discussed some of the important progresses on the disposal of unclear wastes, the influence of the climate change on the site setting and main methods such as lake sediments, marine sediment, loess, ancient soil and ice core deal with palaeoclimate and palaeo environment study. (authors)

  1. Siting of nuclear power plants in densely populated countries

    International Nuclear Information System (INIS)

    Togo, Y.

    1981-01-01

    In evaluating the safety of reactor siting, three typical approaches can be applied; the deterministic approach, the probabilistic approach and the combined approach. In regard to a risk associated with siting, the design of a reactor has to do with both individual and societal risk, while exclusion distance mainly has to do with individual risk, and surrounding population primarily has to do with societal risk. Consequently, in a densely populated area, more attention should be paid to societal risk. There are many reactor sites in the world which can be described as concentrated siting. Although concentrated siting has a lot of merits, such as reducing the construction cost or maintenance cost of reactors, more careful consideration should be paid to safety-related matters of such concentrated reactors because the risk to the individual from accidents caused by concentrated reactors is larger than that from a single reactor. As for the recent controversial issue concerning siting criteria, it appears that the present international consensus on siting philosophy is still valid after the TMI accident. (author)

  2. On-site storage of spent nuclear fuel assemblies in German nuclear power plants

    International Nuclear Information System (INIS)

    Banck, J.

    1999-01-01

    The selection of back-end strategies for spent fuel assemblies is influenced by a number of different factors depending on the given situation in any specific country. In Germany, the back-end strategy implemented in the past was almost exclusively reprocessing. This strategy was required by the German Atomic Energy Act. Since 1994, when the Atomic Energy Act was amended, the option of direct final disposal has been granted the equivalent status by law to that afforded to reprocessing (and reuse of valuable materials). As a result, German utilities may now choose between these two alternatives. Another important condition for optimizing the back-end policy is the fact that fuel cycle costs in Germany are directly dependent on spent fuel volumes (in contrast to the US, for example, such costs are related to the amount of power generated). Another boundary condition for German utilities with respect to spent fuel management is posed by the problems with militant opponents of nuclear energy during transportation of spent fuel to interim storage sites. These facts have given rise to a reconsideration of the fuel cycle back-end, which has resulted in a change in strategy by most German utilities in favour of the following: Preference for long-term storage and maximized use of on-site storage capacity; Reduction in the amount of spent fuel by increasing burnup as much as possible. These decisions have also been driven by the deregulation of energy markets in Europe, where utilities are now permitted to sell electric power to consumers beyond their original supply network and must therefore offer electric power on a very cost competitive basis. (author)

  3. Evaluation of regulatory processes affecting nuclear power plant early site approval and standardization

    International Nuclear Information System (INIS)

    1983-12-01

    This report presents the results of a survey and evaluation of existing federal, state and local regulatory considerations affecting siting approval of power plants in the United States. Those factors that may impede early site approval of nuclear power plants are identified, and findings related to the removal of these impediments and the general improvement of the approval process are presented. A brief evaluation of standardization of nuclear plant design is also presented

  4. Radiation effects issues related to US DOE site remediation and nuclear waste storage

    International Nuclear Information System (INIS)

    Weber, W.J.; Ewing, R.C.

    1994-10-01

    Site restoration activities at DOE facilities and the permanent disposal of nuclear waste generated at the same DOE facilities involve working with and within various types and levels of radiation fields. Radionuclide decay and the associated radiation fields lead to physical and chemical changes that can degrade or enhance material properties. This paper reviews the impact of radiation fields on site restoration activities and on the release rate of radionuclides to the biosphere from nuclear waste forms

  5. Study of seismic design bases and site conditions for nuclear power plants

    International Nuclear Information System (INIS)

    1980-04-01

    This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches

  6. Study of seismic design bases and site conditions for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    1980-04-01

    This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches.

  7. Factors relating to the selection of sites for nuclear power stations in certain industrial countries

    International Nuclear Information System (INIS)

    1979-08-01

    The subject is discussed under the following headings: framework conditions of energy supply (energy supply in general (economics, planning); supply of nuclear energy (objectives, national nuclear industry, technology, development, public conflict)); environmental planning (legal foundations, planning levels, public site-provision investigations, electrical utilities); general and statutory atomic licensing procedure, criteria. (U.K.)

  8. Site and feasibility studies of a first nuclear power plant in Morocco

    International Nuclear Information System (INIS)

    Righi, M.

    1988-11-01

    Basing on the estimated studies related to the evaluation of future needs of electrical energy, the launching of a nuclear power program in Morocco is confirmed necessary. A complete study of sites and feasibility has been carried out. Taking into account the site selection factors two sites: BIR ELHAR and SIDI BOULBRA have been kept as candidate sites. The evaluation of seismic and geotechnical risks of the power plant impact on the environment and risks related to human activities has led to privilege the SIDI BOULBRA site. The studies for confirming this site are summarized. 4 figs. (F.M.)

  9. Blasting jobs on the building site of the Temelin nuclear power plant

    International Nuclear Information System (INIS)

    Voda, J.; Podel, R.

    1984-01-01

    The problems are discussed of the preparation and implementation on the Temelin nuclear power plant building site of blasting, the volume of drilling and the choice of the drill hammer - all based on experience gained during the construction of the Mochovce nuclear power plant. The amount of explosives used on the Temelin site will be 1400 t. The use of mechanical charging may shorten the preparation of the site by 20 to 30%. Explosive emulsion slurries are being developed from home raw materials whose application will reduce the volume of drilling by 15%. The method of controlled breaking secures adequate quality of peripheral walls and bottom chink but special explosives will have to be used. Seismic effects are discussed of blasting on dwellings, agricultural and industrial buildings in the vicinity of the site, on-site buildings, underground mains and special structures of the nuclear power plant. (E.S.)

  10. Changing concepts of geologic structure and the problem of siting nuclear reactors: examples from Washington State

    International Nuclear Information System (INIS)

    Tabor, R.W.

    1986-01-01

    The conflict between regulation and healthy evolution of geological science has contributed to the difficulties of siting nuclear reactors. On the Columbia Plateau in Washington, but for conservative design of the Hanford reactor facility, the recognition of the little-understood Olympic-Wallowa lineament as a major, possibly still active structural alignment might have jeopardized the acceptability of the site for nuclear reactors. On the Olympic Peninsula, evolving concepts of compressive structures and their possible recent activity and the current recognition of a subducting Juan de Fuca plate and its potential for generating great earthquakes - both concepts little-considered during initial site selection - may delay final acceptance of the Satsop site. Conflicts of this sort are inevitable but can be accommodated if they are anticipated in the reactor-licensing process. More important, society should be increasing its store of geologic knowledge now, during the current recess in nuclear reactor siting

  11. Information report on nuclear safety and radiation protection of the Tricastin AREVA site - Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Published in compliance with the French code of the environment, this report first presents different aspects of the Areva's Tricastin site which comprises five basic nuclear installations or INBs, and seven ICPE (installation classified for the protection of the environment). The activities are dedicated to uranium conversion, uranium enrichment, uranium chemistry, industrial services, and fuel manufacturing. The report presents this important industrial site, describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which occurred on this site and had to be declared, reports the management of releases by this site and the control of the environment. The next part addresses the management of the various wastes produced by the different installations present on this site. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information

  12. Possible sites for future nuclear power plants in Israel

    Energy Technology Data Exchange (ETDEWEB)

    Yaar, Ilan, E-mail: ilany@energy.gov.il [Ministry of National Infrastructure, Energy and Water Resources, Chief Scientist Office, 14 Hartum St., POB 36148, Jerusalem 9136002 (Israel); Walter, Ayelet [Ministry of National Infrastructure, Energy and Water Resources, Chief Scientist Office, 14 Hartum St., POB 36148, Jerusalem 9136002 (Israel); Sanders, Yovav [Sysnet Group, Habarzel St. 32, Tel Aviv 69710 (Israel); Felus, Yaron [Survey of Israel, 1 Lincoln St., POB 14171, Tel-Aviv 61141 (Israel); Calvo, Ran; Hamiel, Yariv [Geological Survey of Israel, 30 Malkhe Israel St., Jerusalem 95501 (Israel)

    2016-03-15

    A preliminary work aimed at allocating suitable new sites for possible NPPs in Israel is presented. The work is based on Israel's present NPP siting criteria, supported by selected procedure performed by various countries that conducted similar process. The site selection process was conducted in two stages: first, a selection procedure using demographic analysis was conducted; second, a seismological and geological analysis process was performed in the remaining area. From the combined two screening processes results, an overall new area of 569 km{sup 2} was located as a possible area for future construction of NPPs in Israel. Further and more comprehensive work, based on the IAEAs site selection guidelines, has to be performed in the future, in order to verify the preliminary findings presented in this work.

  13. Nuclear electronic equipment for control and monitoring panel. Procedure guide for on-site tests of nuclear reactor instruments

    International Nuclear Information System (INIS)

    1975-10-01

    By the use of a procedure for on-site testing of nuclear reactor instruments it should be possible to judge their ability to guarantee the reactor safety and availability at the moment of divergence or during operation. Such a procedure must therefore be created as a work implement for the quick and reliable installation of electronic devices necessary for nuclear reactor control and supervision. A standard document is proposed for this purpose, allowing a ''test programme'' to be set up before the equipment is installed on the site [fr

  14. The technical-economic problems concerning the search for sites for nuclear electricity generation facilities

    International Nuclear Information System (INIS)

    Zimmer, H.J.

    1976-01-01

    An outline of technical-physical fundamentals, of the design and the mode of operation of LWR reactors is followed by a brief description of the licensing procedure. It is pointed out that safety cannot be a criterion for a site because nuclear power plants have to be safe on every site. The problem of nuclear power plants in the vicinity of towns or densely populated areas is dealt with briefly, too. A method is proposed which allows to find a possible site while investing little time on search and evaluation and which stores this site in a site provision plan. The choice of possible sites is made on three levels which are independent of each other. Possible nuclear power plant sites, on the first level, are considered on the basis of the dominating influence of waste heat discharge and network integration. On the second level, macro-sites are determined by examining the realizability of these possible sites by looking at negative criteria, and, on the third level, the 'fine points' planning stage, a pool of potential micro-sites is determined by applying the 'measure of value' analysis. This is followed by citing an analytical method with which the order of priority amongst 8 possible sites in the USA was determined. (orig./HP) [de

  15. A regulatory view of nuclear containment on UK licensed sites

    International Nuclear Information System (INIS)

    Bradford, P.M.; McNair, I.J.

    1997-01-01

    Members of the UK regulatory body, HM Nuclear Installations Inspectorate (NII) have previously presented conference papers and official reports which have dealt separately with either reactor applications or chemical plant applications. The objective of this paper is to draw together a brief overview of the role of containment in protecting against potential radiological and related hazards, and to describe the factors which influence the NII's assessment of containment safety cases. It draws upon the NII's experience of regulating many types of nuclear facility, from those designed in the late 1940s through to the modern plants, such as Sizewell 'B' and THORP. The paper reviews the legislative and regulatory background within which the facilities exist and are operated. Finally, the paper reviews recent, ongoing and planned research in the field of containment, which has been designed to behave under challenge. (author)

  16. Countermeasures for siting and environment of nuclear power plant

    International Nuclear Information System (INIS)

    Kawakami, Koichi

    1976-01-01

    Though the requests to urge the construction of nuclear power plants increased since the oil crisis, it is clear that it is necessary to take some countermeasures without delay at present because the location problems are in deadlock. Drastic change of the way of thinking should be made first if the social and political extensions of the problem are considered. It must require the persevering effort based on long-range outlook. Accordingly, emphasis is put on the introduction of the environmental administration in U.S. which seems to have many respects to be referred to in the following description. Then National Environmental Policy Act and the permission and approval procedures for nuclear power stations in U.S. are described, and the details of environmental disputes are listed. It reveals the discrepancy of the actual circumstances in Japan and the United States, and that the important portion of the U.S. experience and concept is not learned by Japanese. The Government lacks the recognition that the public acceptance of safety is not obtained till the report of safety investigation and environmental assessment by the governmental organizations are entrusted to people's judgement. That is, the procedures to win the public acceptance are omitted in Japan. The thoroughness of environmental protection is first of all necessary for achieving the target of nuclear power development. Since it seems to be nothing but the countermeasures for the public acceptance of nuclear power generation to cope with ''60 mens' testimony'', the main points of the ''Sixty mens' testimony'' in Fukushima public hearing are cited at the end, which is supposed to include almost all opposite opinions. (Wakatsuki, Y.)

  17. Health survey on cancers about the Tricastin nuclear site

    International Nuclear Information System (INIS)

    2010-01-01

    This survey aims at describing the health status of the population around the Tricastin site, and more particularly at determining whether there is a difference between death or cancer occurrence frequencies observed around this site with respect to reference frequencies. It does not aim at assessing the health impact of the site industrial installations. Cancer mortality data, cancer diagnosis data, demographic data, child cancer data, data related to hospital stays in relationship with cancer, long duration hospital stay data, and mortality data are used. Several indicators are defined and used: standardised mortality ratio, standardised hospitalisation ratio. Data are also analysed in terms of location, and socio-demographic categories. It appears that there is no specific health situation for the considered area, except for pancreas cancer for women

  18. Care of personnel on the building site of the Dukovany nuclear power plant

    International Nuclear Information System (INIS)

    Kurial, P.

    1984-01-01

    The accommodation is described of workers on the building site of the Dukovany nuclear power plant. The quality is appraised of accommodation, catering and refreshments. There is a health care unit on site and 15 beds are reserved at the Trebic hospital for emergency cases. Trade union and youth organizations look after sports and cultural activities. (E.S.)

  19. Selection of sites for nuclear power plants in The Netherlands. Pt. C

    International Nuclear Information System (INIS)

    1986-01-01

    This advice is concerned with the question where possible new nuclear power plants can at best be sited in the Netherlands. Safety risks of power plants are considered (sourceterm analysis, meteorologic aspects). A site analysis is presented on the base of criteria like population density, possible emergency provisions, contamination of agricultural areas etc. Reports of several committees are included. (Auth.)

  20. Nuclear event time histories and computed site transfer functions for locations in the Los Angeles region

    Science.gov (United States)

    Rogers, A.M.; Covington, P.A.; Park, R.B.; Borcherdt, R.D.; Perkins, D.M.

    1980-01-01

    This report presents a collection of Nevada Test Site (NTS) nuclear explosion recordings obtained at sites in the greater Los Angeles, Calif., region. The report includes ground velocity time histories, as well as, derived site transfer functions. These data have been collected as part of a study to evaluate the validity of using low-level ground motions to predict the frequency-dependent response of a site during an earthquake. For this study 19 nuclear events were recorded at 98 separate locations. Some of these sites have recorded more than one of the nuclear explosions, and, consequently, there are a total of 159, three-component station records. The location of all the recording sites are shown in figures 1–5, the station coordinates and abbreviations are given in table 1. The station addresses are listed in table 2, and the nuclear explosions that were recorded are listed in table 3. The recording sites were chosen on the basis of three criteria: (1) that the underlying geological conditions were representative of conditions over significant areas of the region, (2) that the site was the location of a strong-motion recording of the 1971 San Fernando earthquake, or (3) that more complete geographical coverage was required in that location.

  1. Social impact mitigation and nuclear waste repository siting

    International Nuclear Information System (INIS)

    Peelle, E.

    1980-01-01

    Some aspects of the socioeconomic impacts of siting, constructing, and operating radioactive waste repositories in rural areas are discussed. These include public perceptions of high risk and uncertainty; limited benefits and no incentives; dissociations of costs and benefits; remoteness and inaccessibility of the decision making process for large energy facilities; no institutions to provide protection and accountability for those who may be affected by the siting; the fact that not all risks or impacts are fully mitigable; and constraints on DOE's present ability or authority to mitigate impacts

  2. General siting study 95. Siting of a deep repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    1995-10-01

    General Siting Study 95 is a detailed description of the work carried out to put the siting of a deep repository in a national and regional context. The report is based on SKB's siting factors, which have been applied on a national scale. Different factors of importance or of possible importance for the long-term radiological safety, technology, land and environment as well as society are described and evaluated. This report is the overall description on general siting studies which the government considered that SKB should report in connection with the RD and D Programme 95. 121 refs, 40 figs

  3. General siting study 95. Siting of a deep repository for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    General Siting Study 95 is a detailed description of the work carried out to put the siting of a deep repository in a national and regional context. The report is based on SKB`s siting factors, which have been applied on a national scale. Different factors of importance or of possible importance for the long-term radiological safety, technology, land and environment as well as society are described and evaluated. This report is the overall description on general siting studies which the government considered that SKB should report in connection with the RD and D Programme 95. 121 refs, 40 figs.

  4. Safety Considerations in the Selection of Nuclear Power Plant Candidate Sites in Johor State, Malaysia

    International Nuclear Information System (INIS)

    Ramli, A.T.; Basri, N.A.; Abu Hanifah, N.Z.H.

    2014-01-01

    Nuclear power is considered as one of the best options for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation / production, commissioning the first nuclear power plant needs tremendous effort in various aspects. The most obvious challenges are to ensure the nation’s safety and to handle security issues that may arise from a nuclear power plant site. This paper aims to propose a site for nuclear power plant in Johor State, Malaysia as well as listing the possible safety challenges in the process. The site selection uses the Malaysian Atomic Energy Licensing Board (AELB) guideline document as the main reference, supported by documents from International Atomic Energy Agency (IAEA) and from various countries. Only five site characteristics are chosen as study parameters – geological features and seismic data, air dispersion analysis using meteorological data, population distribution, safety zones and emergency supports. This paper concluded that site number 2 (CS2) at Tanjung Tenggaroh, Mersing is the most suitable area for nuclear power plant in Johor state. It has the least possible risks, safety and security issues. (author)

  5. Safety Considerations in the Selection of Nuclear Power Plant Candidate Sites in Johor State, Malaysia

    Energy Technology Data Exchange (ETDEWEB)

    Ramli, A. T.; Basri, N. A.; Abu Hanifah, N. Z.H., [Department of Physics, Faculty of Science Universiti Teknologi Malaysia Johor (Malaysia)

    2014-10-15

    Nuclear power is considered as one of the best options for future energy development in Malaysia. Since Malaysia has no experience in nuclear energy generation / production, commissioning the first nuclear power plant needs tremendous effort in various aspects. The most obvious challenges are to ensure the nation’s safety and to handle security issues that may arise from a nuclear power plant site. This paper aims to propose a site for nuclear power plant in Johor State, Malaysia as well as listing the possible safety challenges in the process. The site selection uses the Malaysian Atomic Energy Licensing Board (AELB) guideline document as the main reference, supported by documents from International Atomic Energy Agency (IAEA) and from various countries. Only five site characteristics are chosen as study parameters – geological features and seismic data, air dispersion analysis using meteorological data, population distribution, safety zones and emergency supports. This paper concluded that site number 2 (CS2) at Tanjung Tenggaroh, Mersing is the most suitable area for nuclear power plant in Johor state. It has the least possible risks, safety and security issues. (author)

  6. Status of University of Cincinnati reactor-site nuclear engineering graduate programs

    International Nuclear Information System (INIS)

    Anno, J.N.; Christenson, J.M.; Eckart, L.E.

    1993-01-01

    The University of Cincinnati (UC) nuclear engineering program faculty has now had 12 yr of experience in delivering reactor-site educational programs to nuclear power plant technical personnel. Currently, with the sponsorship of the Toledo-Edison Company (TED), we are conducting a multiyear on-site graduate program with more than 30 participants at the Davis-Besse nuclear power plant. The program enables TED employees with the proper academic background to earn a master of science (MS) degree in nuclear engineering (mechanical engineering option). This paper presents a brief history of tile evolution of UC reactor-site educational programs together with a description of the progress of the current program

  7. Public attitudes to nuclear and coal power in site selection for a future energy centre

    International Nuclear Information System (INIS)

    Baril, R.G.; Dobson, J.K.

    This paper discusses the results of a 1977 public attitude survey carried out as part of an Ontario Hydro generating site selection program along the North Channel of Lake Huron. The results of the survey are compared with those of two similar surveys conducted in 1974 and 1975. The main topics discussed include local citizen attitudes to a generating site in the area, nuclear power, attitude changes over three years, differences in attitudes to nuclear and to coal fired generation and the underlying reasons given for favouring or opposing nuclear power. The results of other surveys which have been conducted recently in Canada and internationally are discussed and compared with this survey. Most longitudinal studies point to a trend of declining public acceptance regarding nuclear power. If this trend continues, there are important implications for the nuclear power industry: they are discussed from a sociological and political perspective. (author)

  8. Selection of sites for nuclear power plants in The Netherlands. Pt. A

    International Nuclear Information System (INIS)

    1985-01-01

    In this report a policy proposal is presented concerning the selection of location sites for new nuclear power plants in the Netherlands. Firstly it is investigated which of the 29 already selected location sites are not to be taken into further account because of obvious obstructions (close vicinity of a big city etc.). The remaining sites are judged on the base of local population magnitude. The sites that pass the last criteria are relatively compared from a large number of viewpoints. To round off the selection procedure the government will explain why they consider the finally selected sites to be suitable for location of new nuclear power plants. Steps are indicated to prevent the decrease of planologic suitability of the selected location sites. (Auth.)

  9. On-site emergency intervention plan for nuclear accident situation at SCN-Pitesti TRIGA Reactor

    International Nuclear Information System (INIS)

    Margeanu, S.; Oprea, I.

    2008-01-01

    A 14 MW TRIGA research reactor is operated on the Institute for Nuclear Research site. In the event of a nuclear accident or radiological emergency that may affect the public the effectiveness of protective actions depends on the adequacy of intervention plans prepared in advance. Considerable planning is necessary to reduce to manageable levels the types of decisions leading to effective responses to protect the public in such an event. The essential structures of our on-site, off-site and county emergency intervention plan and the correlation between emergency intervention plans are presented. (authors)

  10. The potential environmental impacts and the siting of proposed nuclear power plants in China

    International Nuclear Information System (INIS)

    Shi Zhongqi

    1986-01-01

    This paper reviews briefly the methodology of assessing environmental impacts from the nuclear power plants and analyses the potential radiological impacts on the environment from proposed nuclear power plants in China. Preliminary studies show that the environmental impacts of the effluents of routine release from PWRs to the proposed sites are extremely small, even if nuclear power plants are constructed either on the Bohai Sea shore with a narrow mouth or in the densely populated regions of Sunan. Thus, the suitability of sites depends mainly on the acceptability of possible exposure to the residents following postulated accidental release of radioactive materials. The paper also discusses relations between the nuclear plant siting and population distribution around the site and compares the distribution of the proposed sites in China with that of other countries sites in according to China actual situation, it is reasonable to adopt a prudent policy that the first series of nuclear power plants in China should be built in relatively low population areas

  11. Tsunami hazard assessment on nuclear power plant site evaluation accordance on DS 417

    International Nuclear Information System (INIS)

    Akhmad Khusyairi

    2011-01-01

    Nuclear power plant site evaluation should conduct the hazard evaluation on tsunami. Global climate changes and particularly extreme meteorology and hydrology phenomena have an impact on the structure, systems and important components related to safety. Therefore, IAEA makes efforts to revise the IAEA Safety Standard Series NS-G 3.4, Meteorological Events in Site Evaluation for Nuclear Power Plants and IAEA safety standard series NS-G 3.5 Flood Hazard For Nuclear Power Plants On Coastal And River Sites, in order to provide protection against the public and the environment safety due to operation of nuclear power plants. There are two methods used in assessing tsunami hazard, probabilistic and deterministic methods. In the tsunami hazard assessment, some necessary information and data should be obtained to determine the basic design of tsunami hazard during designing nuclear power plants, especially the cooling system design. Flooding caused tsunami must be evaluated to determine the site protection system. Furthermore, There must be an evaluation on either coincident event or meteorological simultaneously tsunami event that caused the worst effect on the site. Therefore, the protection of the site from extreme tsunami can be planned. (author)

  12. The knowledge-based off-site emergency response system for a nuclear power plant

    International Nuclear Information System (INIS)

    Ho, L.W.; Loa, W.W.; Wang, C.L.

    1987-01-01

    A knowledge-based expert system for a nuclear power plant off-site emergency response system is described. The system incorporates the knowledge about the nuclear power plant behaviours, site environment and site geographic factors, etc. The system is developed using Chinshan nuclear power station of Taipower Company, Taiwan, ROC as a representative model. The objectives of developing this system are to provide an automated intelligent system with functions of accident simulation, prediction and with learning capabilities to supplement the actions of the emergency planners and accident managers in order to protect the plant personnel and the surrounding population, and prevent or mitigate property damages resulting from the plant accident. The system is capable of providing local and national authorities with rapid retrieval data from the site characteristics and accident progression. The system can also provide the framework for allocation of available resources and can handle the uncertainties in data and models

  13. Comparison between dispersed nuclear power plants and a nuclear energy center at a hypothetical site on Kentucky Lake, Tennessee. Volume I. Summary

    International Nuclear Information System (INIS)

    Burwell, C.C.; Reister, D.B.; Rosemarin, C.S.; Sisman, O.; Suffern, J.S.

    1976-05-01

    A brief summary is presented of the surrogate site concept used to compare the Nuclear Energy Center (NEC) concept with the present method of dispersed siting of nuclear power plants. Included are data on power transmission, environmental considerations, and a discussion of a site selection methodology

  14. On-site inspection: A brief overview and bibliography of techniques pertinent to assessing suspected nuclear test sites

    International Nuclear Information System (INIS)

    Carrigan, C.R.

    1993-03-01

    The purpose of this report is to provide a brief overview and bibliography of those techniques that may have application for the evaluation of a site to determine if a high energy release event is nuclear in nature. This effort is motivated by recognition of the changing world political climate and the perception that low yield and non-proliferation issues will grow in importance as countries become increasingly involved as signators to treaties that are intended to limit the development and testing of nuclear weapons. Along with an increasing interest in such issues is the awareness of the need to implement improved capabilities for treaty monitoring programs that must deal with assessing suspicious occurrences of high energy release events. In preparing this report, it is recognized that monitoring can take two main forms. The first involves the resolution of unidentified events detected by seismic and satellite National Technical Means. Events of an indeterminate nature could occur world-wide and could induce tension in neighboring countries. If an on-site measurement capability were available, a monitoring team could be sent to the suspected site of an event to take measurements that could confirm or disprove the occurrence of a clandestine nuclear test. The second monitoring form is the confirmation that a clandestine event is not masked by a declared event. For example, a large mining explosion could mask a decoupled nuclear explosion. On-site measurements before and during the test could confirm that a clandestine event did not occur and could provide assurance that the party carrying out the explosion is not taking advantage of clandestine testing opportunities. 48 refs

  15. Mobile radiological monitoring around Nuclear Power Plant site at Tarapur

    International Nuclear Information System (INIS)

    Patil, S.S.; Saindane, S.S.; Sharma, R.; Suri, M.M.K.; Pradeepkumar, K.S.; Sharma, D.N.; Rao, D.D.

    2008-01-01

    Real time mobile radiological monitoring around nuclear facilities is required for establishing background radiation dose rate data and to detect any increase in the radiation level which is attributable to the atmospheric releases from Nuclear facilities. Mobile radiation survey using mobile monitoring systems was carried out in the Emergency Planning Zone around Tarapur Atomic Power station during plant operation, taking the wind direction also into consideration. For identifying the potential difficulties during an emergency scenario and to understand the variation of the measured values several systems/instruments were used simultaneously for mapping the dose rates. As demonstrated during this monitoring programme, 40mm x 40mm NaI(Tl) detector based Portable Mobile Gamma Spectrometry System (PMGSS) which is attached with a GPS can acquire and store large amount of gamma spectra tagged with positional coordinates and can enhance the capacity of decision makers during any accidental situation. The average of dose rates measured from various locations around Tarapur Atomic Power Station is 70 - 80 nGy.h -1 . The higher dose rate in the range of 110-125 nGy.h -1 measured at one of the location is due to higher concentration of natural radioactivity mainly by 40 K which was confirmed by the gamma spectrometric measurement. (author)

  16. Rehabilitation of the former nuclear test sites at Maralinga

    International Nuclear Information System (INIS)

    Costello, J.M.; Davoren, P.J.

    1994-01-01

    The Department of Primary Industries and Energy, Canberra, has commenced tendering procedures for appointment of a Project Management Organisation for the Rehabilitation of the former British atomic weapon test sites at Maralinga and Emu in South Australia. This paper gives a historical background to the atomic tests, and reports scientific and engineering studies conducted by the Technical Assessment Group (TAG) to define practical and economic options for rehabilitation of the former test sites. The rehabilitation option preferred by the Australian Government will focus on removal and burial of soil and fragments highly contaminated with plutonium oxide, and erection of warning fences around areas where permanent residence will not be permitted. The application of in-situ vitrification is under investigation for stabilisation of twenty one disposal pits containing up to twenty kilograms of plutonium at Taranaki. 3 refs., 2 tabs., 3 figs

  17. How to solve the problem of siting nuclear waste

    International Nuclear Information System (INIS)

    Inhaber, H.

    1990-01-01

    Over the past decades, attempts to site new low-level and high-level radioactive wastes (LLRW and HLRW) have been almost universally frustrated. The twin goals of finding a volunteer site and, at the same time, retaining environmental and safety standards and specifications can be achieved by using a reverse Dutch auction (RDA). This apparently is the only extant system that allows these two aims to be achieved simultaneously. The RDA adds an economic dimension to the already existent risk factors. At the same time, it is not a bribe, since any payments made will be public. A bribe is performed in secret and to attain an illegal purpose. The RDA has neither feature. In a standard (or English) auction, the price rises, and these are multiple bids. In a Dutch auction, the price drops, and there is only one bid. Since an RDA deals with a facility generally regarded as undesirable, its price rises, but there is still only one bid. The RDA would work as follows. A list of environmental criteria would be circulated to all counties at the start of the process. In this discussion, it is assumed that a state is attempting to site LLRW, but the principle is also applicable to interstate compacts or HLRW. These criteria should remain fixed. Past siting proposals have often seen the alteration - or attempted alteration - of criteria in mid-stream, leading to loss of confidence in the system's scientific credibility. These alternatives have often had the purpose of excluding or including certain regions

  18. Cooling water in the study of nuclear power plants sites

    International Nuclear Information System (INIS)

    Martinez, J.J.C.

    1990-01-01

    The location of an electric power plant has its limitations as regards the availability of apt sites. The radiosanitary risk, seismic risk and the overload capacity of the ground can be generically enumerated, being the cooling water availability for an electric power plant a basic requirement. Diverse cooling systems may be employed but the aim must always be that thermal contamination in the immediate environment be the least possible. (Author) [es

  19. Electrokinetic remediation of plutonium-contaminated nuclear site wastes: Results from a pilot-scale on-site trial

    International Nuclear Information System (INIS)

    Agnew, Kieran; Cundy, Andrew B.; Hopkinson, Laurence; Croudace, Ian W.; Warwick, Phillip E.; Purdie, Philip

    2011-01-01

    This paper examines the field-scale application of a novel low-energy electrokinetic technique for the remediation of plutonium-contaminated nuclear site soils, using soil wastes from the Atomic Weapons Establishment (AWE) Aldermaston site, Berkshire, UK as a test medium. Soils and sediments with varying composition, contaminated with Pu through historical site operations, were electrokinetically treated at laboratory-scale with and without various soil pre-conditioning agents. Results from these bench-scale trials were used to inform a larger on-site remediation trial, using an adapted containment pack with battery power supply. 2.4 m 3 (ca. 4 tonnes) of Pu-contaminated soil was treated for 60 days at a power consumption of 33 kW h/m 3 , and then destructively sampled. Radiochemical data indicate mobilisation of Pu in the treated soil, and migration (probably as a negatively charged Pu-citrate complex) towards the anodic compartment of the treatment cell. Soil in the cathodic zone of the treatment unit was remediated to a level below free-release disposal thresholds (1.7 Bq/g, or <0.4 Bq/g above background activities). The data show the potential of this method as a low-cost, on-site tool for remediation of radioactively contaminated soils and wastes which can be operated remotely on working sites, with minimal disruption to site infrastructure or operations.

  20. Geomorphologic specificities of selected sites for nuclear power plants in Czechoslovakia

    International Nuclear Information System (INIS)

    Kalvoda, J.; Demek, J.

    1991-01-01

    The contribution of geomorphology to the complex evaluation of properties of sites for the construction and operation of nuclear facilities is demonstrated. The unique manifestation of the present geodynamics at the Jaslovske Bohunice nuclear power plant locality and the spatial correlations of annals of the specific morphotectonic development of georeliefs of that nuclear power plant with the location of the epicentral earthquake zones are shown. The results of the geomorphological survey in the surroundings of the Temelin nuclear power plant construction site are described and a drawing is reproduced showing how the georelief of this locality divides into areas with different categories of occurrence of morpho-structural formations. For the Tetov locality, where the construction of a nuclear power plant is planned, the changes in the course of the Labe (Elbe) river which occurred in the Pleistocene are of importance in the assessment of the intensity of geodynamic processes. The geomorphological and geotectonic complexity of the planned Blahutovice nuclear power plant construction site is demonstrated. A drawing shows the morphotectonic situation in the surroundings of that construction site. (Z.S.). 4 figs

  1. 78 FR 56749 - Site Characteristics and Site Parameters for Nuclear Power Plants

    Science.gov (United States)

    2013-09-13

    ..., ``Geologic Characterization Information,'' (currently titled as ``Basic Geologic and Seismic Information... Ensuring Hazard- Consistent Seismic Input for Site Response and Soil Structure Interaction Analyses,'' NUREG-2115 and NUREG-2117; (2) adding information concerning the Geologic Mapping License Condition; (3...

  2. Perspectives on nuclear material safety management methods at DOE sites

    International Nuclear Information System (INIS)

    Hyder, M.L.

    1997-01-01

    The management of nuclear materials, and fissile materials in particular, at the USDOE facilities is undergoing significant changes. These result in large part from decreasing requirements for these materials in the US weapons program. Not only is new production no longer required, but returns must be handled and safely stored. Eventually surplus fissile material will be used for power production, or else put into a form suitable for long term disposition. In the meanwhile concentrates must be stored with protection against releases of radioactive material to the environment, and also against theft or deliberate dispersion. In addition, cleaning up large volumes of materials contaminated with fissile isotopes will be a major activity, and there will also be some quantity of spent fuel containing enriched uranium that cannot readily be processed. All these activities pose safety problems, some of which are addressed here

  3. Migration of tritium from a nuclear waste burial site

    International Nuclear Information System (INIS)

    Hawkins, R.H.

    1975-09-01

    The Savannah River Plant (SRP) has routinely and continuously monitored the local environment (land, water, air, flora, and fauna) since 1951. As part of this intensive program, a three-part study was made to assess the tritium migration from an onsite burial ground for solid nuclear wastes and the resulting dose-to-man. A major source of tritium is buried, massive, Li-Al residues (referred to as melts) from the thermal extraction step in the SRP tritium production process. A melt with its extraction crucible and lid were immersed in water to measure the amounts of tritium released as HTO and HT to the water and to air. The result was a rapid release of 23 curies, of which approximately 99 percent was HTO that remained in the immersion water, and 1 percent was HT that passed into the air. (auth)

  4. Nuclear criticality project plan for the Hanford Site tank farms

    Energy Technology Data Exchange (ETDEWEB)

    Bratzel, D.R., Westinghouse Hanford

    1996-08-06

    The mission of this project is to provide a defensible technical basis report in support of the Final Safety Analysis Report (FSAR). This technical basis report will also be used to resolve technical issues associated with the nuclear criticality safety issue. The strategy presented in this project plan includes an integrated programmatic and organizational approach. The scope of this project plan includes the provision of a criticality technical basis supporting document (CTBSD) to support the FSAR as well as for resolution of the nuclear criticality safety issue. Specifically, the CTBSD provides the requisite technical analysis to support the FSAR hazard and accident analysis as well as for the determination of the required FSAR limits and controls. The scope of The CTBSD will provide a baseline for understanding waste partitioning and distribution phenomena and mechanistics for current operational activities inclusive of single-shell tanks, double-shell tanks, double-contained receiver tanks, and miscellaneous underground storage tanks.. Although the FSAR does not include future operational activities, the waste partitioning and distribution phenomena and mechanistics work scope identified in this project plan provide a sound technical basis as a point of departure to support independent safety analyses for future activities. The CTBSD also provides the technical basis for resolution of the technical issues associated with the nuclear criticality safety issue. In addition to the CTBSD, additional documentation will be required to fully resolve U.S. Department of Energy-Headquarters administrative and programmatic issues. The strategy and activities defined in this project plan provide a CTBSD for the FSAR and for accelerated resolution of the safety issue in FY 1996. On April 30, 1992, a plant review committee reviewed the Final Safety Analysis Reports for the single-shell, double-shell, and aging waste tanks in light of the conclusions of the inadequate waste

  5. Atmospheric Dispersion Simulation for Level 3 PSA at Ulchin Nuclear Site using a PUFF model

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Seung Jun; Han, Seok-Jung; Jeong, Hyojoon; Jang, Seung-Cheol [KAERI, Daejeon (Korea, Republic of)

    2015-05-15

    Air dispersion prediction is a key in the level 3 PSA to predict radiation releases into the environment for preparing an effective strategy for an evacuation as a basis of the emergency preparedness. To predict the atmospheric dispersion accurately, the specific conditions of the radiation release location should be considered. There are various level 3 PSA tools and MACSS2 is one of the widely used level 3 PSA tools in many countries including Korea. Due to the characteristics of environmental conditions in Korea, it should be demonstrated that environmental conditions of Korea nuclear sites can be appropriately illustrated by the tool. In Korea, because all nuclear power plants are located on coasts, sea and land breezes might be a significant factor. The objectives of this work is to simulate the atmospheric dispersion for Ulchin nuclear site in Korea using a PUFF model and to generate the data which can be used for the comparison with that of PLUME model. A nuclear site has own atmospheric dispersion characteristics. Especially in Korea, nuclear sites are located at coasts and it is expected that see and land breeze effects are relatively high. In this work, the atmospheric dispersion at Ulchin nuclear site was simulated to evaluate the effect of see and land breezes in four seasons. In the simulation results, it was observed that the wind direction change with time has a large effect on atmospheric dispersion. If the result of a PLUME model is more conservative than most severe case of a PUFF model, then the PLUME model could be used for Korea nuclear sites in terms of safety assessment.

  6. Geologic surface effects of underground nuclear testing, Yucca Flat, Nevada Test Site, Nevada; TOPICAL

    International Nuclear Information System (INIS)

    Grasso, D.N.

    2000-01-01

    This report presents a new Geographic Information System composite map of the geologic surface effects caused by underground nuclear testing in the Yucca Flat Physiographic Area of the Nevada Test Site, Nye County, Nevada. The Nevada Test Site (NTS) was established in 1951 as a continental location for testing nuclear devices (Allen and others, 1997, p.3). Originally known as the ''Nevada Proving Ground'', the NTS hosted a total of 928 nuclear detonations, of which 828 were conducted underground (U.S. Department of Energy, 1994). Three principal testing areas of the NTS were used: (1) Yucca Flat, (2) Pahute Mesa, and (3) Rainier Mesa including Aqueduct Mesa. Underground detonations at Yucca Flat and Pahute Mesa were typically emplaced in vertical drill holes, while others were tunnel emplacements. Of the three testing areas, Yucca Flat was the most extensively used, hosting 658 underground tests (747 detonations) located at 719 individual sites (Allen and others, 1997, p.3-4). Figure 1 shows the location of Yucca Flat and other testing areas of the NTS. Figure 2 shows the locations of underground nuclear detonation sites at Yucca Flat. Table 1 lists the number of underground nuclear detonations conducted, the number of borehole sites utilized, and the number of detonations mapped for surface effects at Yucca Flat by NTS Operational Area

  7. Comparison between dispersed nuclear power plants and a nuclear energy center at a hypothetical site on Kentucky Lake, Tennessee. Vol. IV. A site selection methodology

    International Nuclear Information System (INIS)

    Rosemarin, C.S.; Yaffee, S.L.

    1976-09-01

    A methodology has been developed for selecting suitable sites for development as nuclear energy centers. First, the forty-eight contiguous states were screened on the basis of four variables: (1) seismic stability; (2) distance from projected population centers; (3) adequate water supply; and (4) noninterference with scenic and reserved lands. After location of a surrogate area in north central Tennessee, further screening was performed using 22 variables to find a suitable 75-sq-mile surrogate site within this 1500-sq-mile area. A computer method for screening the surrogate area is presented, and the use of the data for the 22 variables is illustrated

  8. Decommissioning Planning for Nuclear Units at the Oskarshamn Site

    International Nuclear Information System (INIS)

    Rannemalm, Thom; Eriksson, Joergen; Bergh, Niklas

    2016-01-01

    This paper will describe the process that OKG is now in and how the regulatory framework in Sweden is set out with EIA preparation, SAR updates, decommissioning plans etc. and how OKG plans to meet some of the challenges that need to be considered in front of the decommissioning. There will be a discussion on which strategic decisions will have priority and why. The paper will also discuss some of the difficulties with having a site with two units in decommissioning and one unit in power operation. (authors)

  9. Preparation of off-site emergency preparedness plans for nuclear installations

    International Nuclear Information System (INIS)

    1999-10-01

    Safety of public, occupational workers and the protection of environment should be assured while activities for economic and social progress are pursued. These activities include the establishment and utilisation of nuclear facilities and use of radioactive sources. This document is issued as a lead document to facilitate preparation of specific site manuals by the Responsible Organisation for emergency response plans at each site to ensure their preparedness to meet any eventuality due to site emergency in order to mitigate its consequences on the health and safety of site personnel. It takes cognizance of an earlier AERB publication on the subject: Safety Manual on Off-Site Emergency Plan for Nuclear Installations, AERB/SM/NISD-2, 1988 and also takes into consideration the urgent need for promoting public awareness and drawing up revised emergency response plans, which has come out in a significant manner after the accidents at Chernobyl and Bhopal

  10. The part played by applied geology in nuclear power plant site studies

    International Nuclear Information System (INIS)

    Giafferi, J.L.

    1994-01-01

    Site-related geological problems are one of the constraints affecting the environment of nuclear power plants. The natural features (soil and subsoil) at the nuclear power plant site affect numerous factors in the design, construction and operation of the civil engineering structures. The site geological criteria are not solely restricted to the soil as a static support for the structures. Earth tremors in France are of moderate intensity but the likelihood of their occurrence must nevertheless be taken into account for each site. Studies must concern the geological and seismic features of the region as well as the soil and subsoil configurations and composition in the immediate vicinity of the site in order to determine the physical characteristics of the earthquakes so that the safety of the plant can be guaranteed; in many cases, water tables have also to be taken into consideration. Geologic survey techniques are discussed. 13 figs., 7 refs

  11. Development of SKI's Regulatory Approach to the Siting of a Spent Nuclear Fuel Repository

    International Nuclear Information System (INIS)

    Westerlind, Magnus

    2003-01-01

    Since the beginning of the 1990s the Swedish Nuclear Fuel and Waste Management Co., SKB, is actively working with the siting of a spent nuclear fuel repository. Feasibility studies have been completed in a total of eight municipalities, and in December 2000 three municipalities (Oskarshamn, Tierp and Oesthammar) were proposed for further investigations. These site investigations include surface based site characterisation from deep bore holes but also further studies of infrastructure, land use, transportation etc. SKB's proposal was reviewed by SKI and about 60 other organisations, including municipalities, NGOs, government agencies etc. during the winter/spring 2000/2001. In June 2001 SKI reported the review findings to the Government. In parallel with SKI also the Swedish Council for Nuclear Waste (KASAM) reviewed SKB's proposal and reported to the Government. In its decision in November 2001 the Government supported SKB's proposal to continue with site investigations. Based on SKB's material, the reviews and the Government's decision the municipalities of Oesthammar and Oskarshamn have agreed to site investigations while Tierp have decided no to continue. The site investigations in Oesthammar and Oskarshamn started during 2002. The siting process has meant that several new actors have been engaged in nuclear waste management in general and disposal of spent nuclear fuel in particular. This has meant that 'old' actors, particularly SKB, the regulators (the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI) have had to evaluate, develop and clarify their roles and strategies for dialogue. This paper presents reflections on the impacts on some of SKI's regulatory activities

  12. Evaluation of environmental data relating to selected nuclear power plant sites: the Three Mile Island Nuclear Station Site

    International Nuclear Information System (INIS)

    Murarka, I.P.

    1976-08-01

    Environmental monitoring data for the years 1973 and 1974 pertaining to the Three Mile Island Nuclear Station Unit 1, which began operation in early 1974, were analyzed by the most practical qualitative and quantitative methods. Terrestrial biotic resources were considered for this plant. The effects of the operation of Unit 1 on the local terrestrial organisms were found to be undetectable. Although the plant has not operated long enough to reveal long-term deleterious effects, the present indications do not lead to a concerned prediction that any are developing. The data acquired, method of analysis, and results obtained are presented in detail along with recommendations for improving monitoring techniques

  13. Evaluation of environmental data relating to selected nuclear power plant sites. Prairie Island Nuclear Generating Plant site

    International Nuclear Information System (INIS)

    Murarka, I.P.

    1976-11-01

    Environmental monitoring data for 1973 through 1975 pertaining to the Prairie Island Nuclear Generating Station (which began commercial operation in December 1973) were analyzed by the most practical qualitative and quantitative methods. Evaluations of aquatic and terrestrial biotic data are presented in this report. The data indicate no significant immediate deleterious effects on the biota from plant operation, thus confirming preoperational predictions. Although the station has not operated long enough to reveal long-term deleterious effects, present indications do not lead to a concerned prediction that any are developing. Recommendations are suggested for improving monitoring techniques

  14. Problems in Siting Nuclear Power Plants in Japan and Efforts to Solve Them

    Energy Technology Data Exchange (ETDEWEB)

    Inouye, T. [Ministry of International Trade and Industry, Tokyo (Japan)

    1967-09-15

    The rapidly growing demand for energy in Japan will require a total capacity of 30 to 40 thousand MW(e) in nuclear power by 1985. Materialization of this development programme must naturally be supported by securing the requisite sites for the nuclear power plants. The following factors make siting of nuclear power plants more difficult in Japan than in any other country: a small, densely populated territory with little level land, that is already completely utilized for agricultural and/or industrial purposes; small rivers and an active marine-product industry developed along most of the seacoasts, both of which create difficult cooling-water problems; frequent earthquakes; and the fear of possible radioactivity, which prevails in the only nation in the world to have suffered from the atomic bomb. There are at present four nuclear power plants in operation or under construction in Japan with a total capacity of about 1.3 thousand MW(e). However, the plants in these construction programmes have been sited on the basis of taking the easiest course available although there were several possible solutions to choose from. It is pointed out here that the long-range nuclear power development programme will call for a fundamental solution to enable siting a large number of power plants under the adverse conditions in Japan. Accordingly, a study was made, which included quantitative analyses of reactor siting factors and suggested measures for solving the siting problems. The analyses were based on nuclear power plant sites assumed to be located on the seacoast and characterized by low-population density, desirable geology and favourable topography. It was assumed that seacoast siting was more economical than inland siting. Although the study was made by a general survey using maps, it was shown that approximately 10% of the total coastline areas would be eligible for reactor siting, but most of these areas in this case are located in the northern part of Japan, far from

  15. Off-site preparedness and nuclear-power-plant licensing

    International Nuclear Information System (INIS)

    Perry, S.W.

    1983-01-01

    The first year and a half in which off-site emergency preparedness issues have been litigated before the Atomic Safety and Licensing Boards of the NRC have surfaced unique problems of proof for the applicant as well as the staff. These problems seem to be abating as the boards and the parties become more comfortable with the field and its issues, and as FEMA-NRC emergency management expertise gains credibility. Emergency preparedness presentations have also improved as the parties have become more sensitive to the seasonality of the preparedness case, and have increasingly attempted to raise it at a time when a fully developed set of facts is available for the record. Off-site preparedness issues are only now beginning to be raised on appeal to the NRC appeals board, the full commission, and the courts. Helpful guidance on what constitutes an adequate record in this area will undoubtedly be forthcoming in decisions handed down by these bodies in the months ahead

  16. ISC origin times for announced and presumed underground nuclear explosions at several test sites

    International Nuclear Information System (INIS)

    Rodean, H.C.

    1979-01-01

    Announced data for US and French underground nuclear explosions indicate that nearly all detonations have occurred within one or two tenths of a second after the minute. This report contains ISC origin-time data for announced explosions at two US test sites and one French test site, and includes similar data for presumed underground nuclear explosions at five Soviet sites. Origin-time distributions for these sites are analyzed for those events that appeared to be detonated very close to the minute. Particular attention is given to the origin times for the principal US and Soviet test sites in Nevada and Eastern Kazakhstan. The mean origin times for events at the several test sites range from 0.4 s to 2.8 s before the minute, with the earlier mean times associated with the Soviet sites and the later times with the US and French sites. These times indicate lower seismic velocities beneath the US and French sites, and higher velocities beneath the sites in the USSR 9 figures, 8 tables

  17. Nuclear safety criteria applied in site selection - the practice in France

    International Nuclear Information System (INIS)

    Candes, P.; Aussourd, Ph.

    1975-01-01

    In France, the safety of nuclear facilities is the responsibility of the Ministry for Industry and Research (Central Department for the Safety of Nuclear Facilities). The first part of the paper deals with the conception and contents of the site studies which are included in a safety report with the object of obtaining authorization to go ahead with work on the establishment of a facility. The conception is governed by the following two considerations: (a) the site is a place where the natural elements and living organisms occur and which is characterized by the permanent presence of the human factor, while the proposed nuclear facility will - like any industrial facility - present risks and have an impact on the site, particularly through the discharge of radioactive effluent and potentially in consequence of a nuclear accident; (b) the site exercises an influence - in fact, it even imposes constraints - on the nuclear facility. The site study as submitted by the operators to the authorities responsible for the safety evaluation traditionally consists of six sections, covering: (I) description and history of the site; (II) meteorological conditions; (III) hydrology of the area; (IV) geological and seismological conditions; (V) ecological factors; (VI) natural and/or previous radioactivity at the site. These six sections contain the data which serve as a basis for applying the two considerations spelled out above. However, the two corresponding directions of study and analysis do not settle the fundamental problem of the distribution of the population around the site. Methods for dealing with this problem are suggested in the second part of the paper; they take into account the efforts made so far at the international level. The authors consider that limiting criteria should not be based solely on the radioactive effluent discharges associated with normal operation but on the radioactivity releases associated with accidents. The methods proposed by them constitute

  18. Radiation doses to local populations near nuclear weapons test sites worldwide.

    Science.gov (United States)

    Simon, Steven L; Bouville, André

    2002-05-01

    Nuclear weapons testing was conducted in the atmosphere at numerous sites worldwide between 1946 and 1980, which resulted in exposures to local populations as a consequence of fallout of radioactive debris. The nuclear tests were conducted by five nations (United States, Soviet Union, United Kingdom, France, and China) primarily at 16 sites. The 16 testing sites, located in nine different countries on five continents (plus Oceania) contributed nearly all of the radioactive materials released to the environment by atmospheric testing; only small amounts were released at a fewother minor testing sites. The 16 sites discussed here are Nevada Test Site, USA (North American continent), Bikini and Enewetak, Marshall Islands (Oceania); Johnston Island, USA (Oceania), Christmas and Malden Island, Kiribati (Oceania); Emu Field, Maralinga, and Monte Bello Islands, Australia (Australian continent); Mururoa and Fangataufa, French Polynesia (Oceania), Reggane, Algeria (Africa), Novaya Zemlya and Kapustin Yar, Russia (Europe), Semipalatinsk, Kazakhstan (Asia), and Lop Nor, China (Asia). There were large differences in the numbers of tests conducted at each location and in the total explosive yields. Those factors, as well as differences in population density, lifestyle, environment, and climate at each site, led to large differences in the doses received by local populations. In general, the tests conducted earliest led to the highest individual and population exposures, although the amount of information available for a few of these sites is insufficient to provide any detailed evaluation of radiation exposures. The most comprehensive information for any site is for the Nevada Test Site. The disparities in available information add difficulty to determining the radiation exposures of local populations at each site. It is the goal of this paper to summarize the available information on external and internal doses received by the public living in the regions near each of the

  19. Institutional aspects of siting nuclear waste disposal facilities in the United States

    International Nuclear Information System (INIS)

    Stewart, J.C.; Prichard, W.C.

    1987-01-01

    This paper has dealt with the institutional issues associated with disposal of nuclear waste in the US. The authors believe that these institutional problems must be resolved, no matter how technologically well suited a site may be for disposal, before site selection may take place. The authors have also pointed out that the geography of the US, with its large arid regions of very low population density, contributes to the institutional acceptability of nuclear waste disposal. Economic factors, especially in sparsely populated areas where the uranium mining and milling industry has caused operation, also weigh on the acceptability of nuclear waste to local communities. This acceptability will be highest where there are existing nuclear facilities and/or facilities which are closed - thus creating unemployment especially where alternative economic opportunities are few

  20. Comprehensive study of temperature anomalies on of the former Semipalatinsk nuclear test site territory

    International Nuclear Information System (INIS)

    Subbotin, S.B.; Lukashenko, S.N.; Dmitropavlenko, V.N.; Ajdarkhanov, A.O.; Duchkov, A.D.; Kazantsev, S.A.

    2005-01-01

    In 1997 by the space images data in the Semipalatinsk test site area a mysterious anomaly thermal zone with square about 20 thousand sq. km. with soil temperature 10-15 degrees above than on the adjacent areas was found. The results of 1996-1999 observation confirm the presence of steady temperature anomalies. A number of scientists are suggesting that the increased temperature zones are related with conducted nuclear tests. These temperature anomalies related with objects of nuclear explosions conduction and its have limited distribution the spatially attached to nuclear explosions cavities. Anomalies are the sequent of residual manifestation of long-time geothermal activity in the underground nuclear explosions epicenters. In 2001 in the frameworks of joint program 'Comprehensive study of thermal anomalies on the territory of the former Semipalatinsk test site' the direct measurements of soils on the five sections which were selected by the results of space images

  1. Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2014

    International Nuclear Information System (INIS)

    2013-01-01

    Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2014, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  2. Information report on nuclear safety and radiation protection of La Hague AREVA site. Issue 2013

    International Nuclear Information System (INIS)

    2014-01-01

    Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basic nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2013, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  3. Information report on nuclear safety and radiation protection of the La Hague AREVA site- Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    Published in compliance with the French code of the environment, this report first presents the Areva's La Hague site which comprises several basis nuclear installations (INB), is dedicated to several activities related to the nuclear fuel cycle, is submitted to a constraining legal and regulatory framework, and implements a policy for a sustainable development and continuous progress. The document describes the various measures regarding nuclear safety and radiation protection, reports nuclear events which are classified according to the INES scale and occurred and had to be declared in 2012, describes the management of effluents by the different installations present on this site and the control of the environment. It addresses the waste management and the management of other impacts. It gives an overview of actions undertaken regarding information and transparency. Recommendations of the CHSCT are reported

  4. Canada's deep geological repository for used nuclear fuel - the geoscientific site evaluation process

    Energy Technology Data Exchange (ETDEWEB)

    Belfadhel, M.B.; Blyth, A.; Desroches, A.; Hirschorn, S.; Mckelvie, J.; Sanchez-Rico Castejon, M.; Parmenter, A.; Urrutia-Bustos, A.; Vorauer, A., E-mail: mbenbelfadhel@nwmo.ca [Nuclear Waste Management Organization, Toronto, ON (Canada)

    2014-07-01

    The Nuclear Waste Management Organization (NWMO) is responsible for implementing Adaptive Phased Management (APM), the approach selected by the Government of Canada for the long-term management of used nuclear fuel generated by Canadian nuclear reactors. The ultimate objective of APM is the centralized containment and isolation of Canada's used nuclear fuel in a Deep Geological Repository in a suitable crystalline or sedimentary rock formation. In May 2010, the NWMO initiated a nine-step site selection process to find an informed and willing community to host the project. This paper describes the approach, methods and criteria being used to assess the geoscientific suitability of communities currently involved in the site selection process. The social, cultural and economic aspects of the assessment are discussed in a companion paper. (author)

  5. Radiological investigations at the 'Taiga' nuclear explosion site: Site description and in situ measurements

    Energy Technology Data Exchange (ETDEWEB)

    Ramzaev, V., E-mail: V.Ramzaev@mail.ru [Institute of Radiation Hygiene, Mira str. 8, 197101 St.-Petersburg (Russian Federation); Repin, V.; Medvedev, A.; Khramtsov, E.; Timofeeva, M.; Yakovlev, V. [Institute of Radiation Hygiene, Mira str. 8, 197101 St.-Petersburg (Russian Federation)

    2011-07-15

    In the summer of 2009, we performed a field survey of the 'Taiga' peaceful underground nuclear explosion site, the Perm region, Russia (61.30{sup o} N, 56.60{sup o} E). The explosion was carried out by the USSR in 1971. This paper provides an extended summary of the available published data on the 'Taiga' experiment. A detailed description of the site is illustrated by original aerial and ground-level photos. A large artificial lake (700 m long and 350 m wide) currently occupies the central area of the experimental site. The ground lip surrounding the lake is covered by a newly grown mixed forest. In situ measurements, performed in August 2009, revealed elevated levels of the {gamma}-ray dose rate in air on the banks of the lake 'Taiga'. Two hot spots were detected on the eastern bank of the lake. The excess of the {gamma}-ray radiation is attributable to the man-made radionuclides {sup 60}Co and {sup 137}Cs. The current external {gamma}-ray dose rate to a human from the contaminations associated with the 'Taiga' experiment was between 9 and 70 {mu}Sv per week. Periodic monitoring the site is recommended. - Highlights: > We studied a radiation anomaly at the 'Taiga' underground nuclear explosion site. > The anomaly currently has an area of approximately 1 km{sup 2}. > The excess of {gamma}-ray radiation at the site is mainly attributable to {sup 60}Co and {sup 137}Cs. > The external effective dose may currently exceed the negligible value of 10 {mu}Sv y{sup -1}.

  6. 76 FR 79228 - Combined Licenses at William States Lee III Nuclear Station Site, Units 1 and 2; Duke Energy...

    Science.gov (United States)

    2011-12-21

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 52-018 and 52-019; NRC-2008-0170] Combined Licenses at William States Lee III Nuclear Station Site, Units 1 and 2; Duke Energy Carolinas, LLC AGENCY: Nuclear.... SUMMARY: Notice is hereby given that the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Army Corps...

  7. Environmental radiation monitoring of nuclear sites by thermoluminescent dosimeters (TLD)

    International Nuclear Information System (INIS)

    Duftschmid, K.E.; Strachotinsky, Ch.

    1978-04-01

    The measurement of environmental radiation doses around nuclear facilities requires the detection of few mrem/year. The properties of the automatic TLD-system Harshaw Mod. 2271 for such measurements have been evaluated under practical conditions and optimized techniques derived. The automatic TLD-system is based on LiF dosimeter cards with two crystals providing gamma and beta dose values. Limit of detection defined as three standard deviations of residuel dose is 1,2 mR. Automatic readout combined with electronic data evaluation are especially useful for large monitoring networks. Practical intercomparisons of this dosimeter with bulb-type CaF 2 detectors have been performed showing good agreement of both detector. Although bulb-dosimeters proved to be extremely sensitive with a limit of detection at 0,012 mR which makes them very suitable for very short exposure times, the automatic LiF system is superior in regards of man power requirement if monthly monitoring periods are sufficient. The system has been tested in practice during two international intercomparisons performed by the US Department of Energy - Health and Safety Laboratory New York and the Physikalisch Technische Bundesanstalt Braunschweig, Germany, showing excellent agreement. Furthermore a routine monitoring network consisting of 12 measurement positions around the Research Center Seibersdorf has been operated with this technique since more than two years. (author)

  8. Risk-based prioritization at Hanford Nuclear Site

    International Nuclear Information System (INIS)

    Hesser, W.A.; Mosely, M.T.

    1995-11-01

    This paper describes the method used to incorporate risk-based decision making into the Hanford resource allocation process. This method, the Revised Priority Planning Grid, is used as a tool to calculate benefits and benefit-to-cost ratios for comparison of environmental cleanup activities. The tool is based on Hanford Site objectives. Benefits are determined by estimating the impact on those objectives resulting from funding specific environmental management activities. Impacts are also a function of the weights associated with the objectives. These weights in the Revised Priority Planning Grid reflect US Development of Energy management values, which were obtained through a formal value-elicitation process. With modification to the objectives and weights, the Revised Priority Planning Grid could be used in different situations. By factoring in environmental, safety, and health risk and assigning higher scores to those activities that provide the most benefit, the Revised Priority Planning Grid is a reproducible, scientific way of scoring competing activities or interests

  9. Present radiological situation at the Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Stegar, P.

    1996-01-01

    The corroboration of environmental contamination levels obtained by independent equipment and measurements of the team was generally good, the best being with recent Russian and Kazakh data using gamma dose rate measurements. Acceptable corroboration was observed for gamma emitting radionuclides in food and environmental samples. The preliminary results on plutonium levels in soil samples from contaminated sites in the polygon showed values comparable with the data reported by Russian scientists.The major sites selected for field work by the team were the settlements around the polygon of Kainar(population of about 10,000) in the south, Sharzhal (2000) and Karaul (5000) in the east, and Dolon (2000 just north of the Irtysh. Akzhar, within the polygon just south of the river, was used as a reference site. Inside the polygon the efforts were concentrated in the Lake Balapan area including the semipermanent farm around Ground Zero, and a selection of sampling sites along the plume paths of atmospheric and above ground explosions. The operations carried out in the field included: gamma dose rate measurements; in situ gamma spectrometry; and the collection of samples of grass, meat, milk, offal, vegetables and soil, as well as biological indicators such as animal bones, mushrooms and moss. The levels of contamination in the soil at the locations specified are shown. The contamination by ' S r in milk, drinking water and the lake water was also measured, together with results for 137 Cs in meat. The external gamma dose rates in settlements and in the polygon, excluding the Lake Balapan and Ground Zero areas, were around 0.1 uGy per hour, against rates of up to 40 uGy per hour around Lake Balapan and Ground Zero. The dose assessment included consideration of all relevant pathways, of which the most important were external gamma exposure from material on or in the ground, inhalation of material resuspended from the ground and consumption of contaminated foods. These

  10. Development of a Online Nuclear Emergency Response System (ONERS) for Kalpakkam site - the design aspects

    Energy Technology Data Exchange (ETDEWEB)

    Raja Shekhar, S. S.; Bhatawadekar, Shantanu; Krishna Murthy, Y. V.N., [Regional Remote Sensing Service Centre, Department of Space, Nagpur (India); Srinivas, C. V.; Venkatesan, [Radiological Safety Division, Radiological Safety and Environmental Group, Indira Gandhi Centre for Atomic Research, Kalapakkam (India)

    2012-07-01

    An Online Nuclear Emergency Response System (ONERS) is developed for the nuclear power plant site at Kalpakkam as part of the Department of Atomic Energy (DAE) initiative. ONERS is a GIS based spatial analysis system designed indigenously to provide decision support in the event of a radioactive leak or accident from any of the nuclear facilities by assessing the dispersion and deposition patterns of the atmospheric releases, integrate with spatial geographical database for impact assessment and guidance for mitigation. The system is designed with open software tools (UMN Map server, MYSQL, PHP, Java scripts) and its main features include assessment of dose, short and long term forecast, counter measure support, impact assessment to minimize potential threat to man and environment during radiological emergencies. The system is implemented in live mode with integration of numerical models and spatial data base for the site region and is presently operational for the Kalpakkam site. (author)

  11. Development of a Online Nuclear Emergency Response System (ONERS) for Kalpakkam site - the design aspects

    International Nuclear Information System (INIS)

    Raja Shekhar, S.S.; Bhatawadekar, Shantanu; Krishna Murthy, Y.V.N.; Srinivas, C.V.; Venkatesan

    2012-01-01

    An Online Nuclear Emergency Response System (ONERS) is developed for the nuclear power plant site at Kalpakkam as part of the Department of Atomic Energy (DAE) initiative. ONERS is a GIS based spatial analysis system designed indigenously to provide decision support in the event of a radioactive leak or accident from any of the nuclear facilities by assessing the dispersion and deposition patterns of the atmospheric releases, integrate with spatial geographical database for impact assessment and guidance for mitigation. The system is designed with open software tools (UMN Map server, MYSQL, PHP, Java scripts) and its main features include assessment of dose, short and long term forecast, counter measure support, impact assessment to minimize potential threat to man and environment during radiological emergencies. The system is implemented in live mode with integration of numerical models and spatial data base for the site region and is presently operational for the Kalpakkam site. (author)

  12. Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

    International Nuclear Information System (INIS)

    Elder, J.C.; Graf, J.M.; Dewart, J.M.; Buhl, T.E.; Wenzel, W.J.; Walker, L.J.; Stoker, A.K.

    1986-01-01

    This guide was prepared to provide the experienced safety analyst with accident analysis guidance in greater detail than is possible in Department of Energy (DOE) Orders. The guide addresses analysis of postulated serious accidents considered in the siting and selection of major design features of DOE nuclear facilities. Its scope has been limited to radiological accidents at nonreactor nuclear facilities. The analysis steps addressed in the guide lead to evaluation of radiological dose to exposed persons for comparison with siting guideline doses. Other possible consequences considered are environmental contamination, population dose, and public health effects. Choices of models and parameters leading to estimation of source terms, release fractions, reduction and removal factors, dispersion and dose factors are discussed. Although requirements for risk analysis have not been established, risk estimates are finding increased use in siting of major nuclear facilities, and are discussed in the guide. 3 figs., 9 tabs

  13. Selection of sites for nuclear power plants in The Netherlands. Pt. B

    International Nuclear Information System (INIS)

    1986-01-01

    In this report the headlines are presented of the participation of the Dutch people in the policy resolution with regard to the selection of sites of nuclear power plants. In Ch. 1 it is indicated how this participation is organized and the quantitative results are given. In the other chapters the results of the people's participation are treated qualitatively with restriction to the headlines. In Ch. 3 the remarks about the procedure and its precedents are reported. Ch. 4 reflects the public opinion with regard to the (nuclear) energy problem. In Ch. 5 finally the problems concerning the sites of nuclear power plants are treated. The criteria are discussed used by the participants in the judgement of the locations on their aptitude, in general as well as by possible site. (Auth.)

  14. On-site storage of high level nuclear waste: attitudes and perceptions of local residents.

    Science.gov (United States)

    Bassett, G W; Jenkins-Smith, H C; Silva, C

    1996-06-01

    No public policy issue has been as difficult as high-level nuclear waste. Debates continue regarding Yucca Mountain as a disposal site, and-more generally-the appropriateness of geologic disposal and the need to act quickly. Previous research has focused on possible social, political, and economic consequences of a facility in Nevada. Impacts have been predicted to be potentially large and to emanate mainly from stigmatization of the region due to increased perceptions of risk. Analogous impacts from leaving waste at power plants have been either ignored or assumed to be negligible. This paper presents survey results on attitudes of residents in three counties where nuclear waste is currently stored. Topics include perceived risk, knowledge of nuclear waste and radiation, and impacts on jobs, tourism, and housing values from leaving waste on site. Results are similar to what has been reported for Nevada; the public is concerned about possible adverse effects from on-site storage of waste.

  15. The perception of nuclear risks on French sites: social actors and rumors

    International Nuclear Information System (INIS)

    Timbal-Duclaux, L.

    1983-01-01

    This study summarizes the main French researchs on people living close to nuclear plants and their perception of nuclear risks. The ethnological approach was utilized, consisting in an observer living long periods of time on the site. It shows the existence of a ''psychogeographical'' zone in which people fell concerned by the building of the plant. This event reinforce the existing tensions between the social actors in the field of the site. The plant is seen as a ''big work'' ''eating'' land from agriculture and recreation, mixed with a nuclear thing mysterious and dangerous. Perceptions and rumors are greatly varying depending time and space. These results may be applied to a better siting of the plants [fr

  16. Nuclear Waste Policy Act of 1982; proposed general guidelines for recommendation of sites for nuclear waste repositories

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    In accordance with the requirements of the Nuclear Waste Policy Act of 1982 (Pub. L. 97-425), hereinafter referred to as the Act, the Department of Energy is proposing general guidelines for the recommendation of sites for repositories for disposal of high-level radioactive waste and spent nuclear fuel in geologic formations. These guidelines are based on the criteria that the Department has used in its National Waste Terminal Storage program, the criteria proposed by the Nuclear Regulatory Commission (NRC), and the environmental standards proposed by the Environmental Protection Agency. These guidelines establish the performance requirements for a geologic repository system, specify how the Department will implement its site-selection program, and define the technical qualifications that candidate sites must meet in the various steps of the site-selection process mandated by the Act. After considering comments from the public; consulting with the Council on Environmental Quality, the Administrator of the Environmental Protection Agency, the Director of the Geological Survey, and interested Governors; and obtaining NRC concurrence, the Department will issue these guidelines in final form as a new Part 960 to Title 10 of the Code of Federal Regulations (10 CFR Part 960)

  17. Valuation procedure for supra-regional siting of nuclear power plants

    International Nuclear Information System (INIS)

    Volwahsen, A.

    1977-01-01

    The entwinement of area planning and power policies is explained and conceivable effects of the selection of site for nuclear power stations on the regional economic and social structure as well as the housing development are discussed. A research project and its purposes are presented here, the project having been initiated in order to examine the siting concepts emerging from the discussion of deverging interests, and in order to elaborate a variety of concrete requirements to be made with regard to site examination and site selection. Large-scole valuation indicators and procedures are expected to lead to solutions acceptable for all parties concerned. (HP) 891 HP [de

  18. Multiattribute utility analysis of alternative sites for the disposal of nuclear waste

    International Nuclear Information System (INIS)

    Merkhofer, M.W.; Keeney, R.L.

    1987-01-01

    Five potential sites nominated for the Nation's first geologic repository for disposing of nuclear waste are evaluated using multiattribute utility analysis. The analysis was designed to aid the Department of Energy in its selection of 3 sites for characterization, a detailed data-gathering process that will involve the construction of exploratory shafts for underground testing and that may cost as much as $1 billion per site. The analysis produced insights into the relative advantages and disadvantages of the nominated sites and clarified current uncertainties regarding repository performance

  19. Sites with nuclear facilities in the state of dismantling and their future from the public perspective

    International Nuclear Information System (INIS)

    Kretz, Simon Philipp

    2015-01-01

    The thesis on the public perspective at sites of nuclear facility dismantling covers the following issues: the change of German energy landscapes under social and political points of view, theoretical frame of the work, combination of empirical studies and the theoretical approaches in a space concept, action model and hypotheses on the situation and development in communities with nuclear facilities in the state of dismantling, description of the interviewees, and the empirical results of the interviews.

  20. Analysis of external flooding events occurred in foreign nuclear power plant sites

    International Nuclear Information System (INIS)

    Li Dan; Cai Hankun; Xiao Zhi; An Hongzhen; Mao Huan

    2013-01-01

    This paper screens and studies 17 external flooding events occurred in foreign NPP sites, analysis the characteristic of external flooding events based on the source of the flooding, the impact on the building, systems and equipment, as well as the threat to nuclear safety. Furthermore, based on the experiences and lessons learned from Fukushima nuclear accident relating to external flooding and countermeasures carried out in the world, some suggestions are proposed in order to improve external flooding response capacity for Chinese NPPs. (authors)

  1. Techniques to eliminate nuclear weapons testing infrastructure at former Semipalatinsk test site

    International Nuclear Information System (INIS)

    Erofeev, I.E.; Kovalev, V.V.

    2003-01-01

    It was at the former Semipalatinsk Test Site where for the first time in the world the nuclear weapons testing infrastructure elimination was put into practice. Fundamentally new procedures for blasting operations have been developed by specialists of the Kazakh State Research and Production Center of Blasting Operations (KSCBO), National Nuclear Center of the Republic of Kazakhstan (NNC) and Degelen Enterprise to enhance reliability and provide safety during elimination of various objects and performance of large-scale experiments. (author)

  2. Limited site review for the San Joaquin Nuclear Project. Project No. 499

    International Nuclear Information System (INIS)

    1977-06-01

    This report is the Nuclear Regulatory Commission's (Commission) safety evaluation of a proposed site near Bakersfield, California, on which the Los Angeles Department of Water and Power (applicant) in association with a number of other organizations proposes to build a nuclear facility at a future date. A construction permit application has not been filed but the applicant has informed us of its intention to submit an Environmental Report during February 1980 and a Preliminary Safety Analysis Report during May 1980

  3. Meteorological events in site evaluation for nuclear power plants. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    This Safety Guide provides recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. It is of interest to safety assessors and regulators involved in the licensing process as well as to designers of nuclear power plants. This Safety Guide was prepared under the IAEA programme for safety standards for nuclear power plants. It supplements the IAEA Safety Requirements publication on Site Evaluation for Nuclear Facilities which is to supersede the Code on the Safety of Nuclear Power Plants: Siting, Safety Series No. 50-C-S (Rev. 1), IAEA, Vienna (1988). The present Safety Guide supersedes two earlier Safety Guides: Safety Series No. 50-SG-S11A (1981) on Extreme Meteorological Events in Nuclear Power Plant Siting, Excluding Tropical Cyclones and Safety Series No. 50-SG-S11B (1984) on Design Basis Tropical Cyclone for Nuclear Power Plants. The purpose of this Safety Guide is to provide recommendations and guidance on conducting hazard assessments of extreme and rare meteorological phenomena. This Safety Guide provides interpretation of the Safety Requirements publication on Site Evaluation for Nuclear Facilities and guidance on how to fulfil these requirements. It is aimed at safety assessors or regulators involved in the licensing process as well as designers of nuclear power plants, and provides them with guidance on the methods and procedures for analyses that support the assessment of the hazards associated with extreme and rare meteorological events. This Safety Guide discusses the extreme values of meteorological variables and rare meteorological phenomena, as well as their rates of occurrence, according to the following definitions: (a) Extreme values of meteorological variables such as air temperature and wind speed characterize the meteorological or climatological environment. And (b) Rare meteorological phenomena

  4. Rock siting of nuclear power plants from a reactor safety standpoint. Status report October 1974

    International Nuclear Information System (INIS)

    1975-01-01

    The aim of this study is to clearify the advantages and disadvantages of an underground nuclear power plant from a reactor safety point of view, compared to a plant above ground. Principles for the technical design of a rock sited BWR nuclear power plant is presented. Also questions of sabotage and closing down the plant at the end of the operational period are treated. (K.K.)

  5. Ongoing research experiments at the former Soviet nuclear test site in eastern Kazakhstan

    Science.gov (United States)

    Leith, William S.; Kluchko, Luke J.; Konovalov, Vladimir; Vouille, Gerard

    2002-01-01

    Degelen mountain, located in EasternKazakhstan near the city of Semipalatinsk, was once the Soviets most active underground nuclear test site. Two hundred fifteen nuclear tests were conducted in 181 tunnels driven horizontally into its many ridges--almost twice the number of tests as at any other Soviet underground nuclear test site. It was also the site of the first Soviet underground nuclear test--a 1-kiloton device detonated on October 11, 1961. Until recently, the details of testing at Degelen were kept secret and have been the subject of considerable speculation. However, in 1991, the Semipalatinsk test site became part of the newly independent Republic of Kazakhstan; and in 1995, the Kazakhstani government concluded an agreement with the U.S. Department of Defense to eliminate the nuclear testing infrastructure in Kazakhstan. This agreement, which calls for the "demilitarization of the infrastructure directly associated with the nuclear weapons test tunnels," has been implemented as the "Degelen Mountain Tunnel Closure Program." The U.S. Defense Threat Reduction Agency, in partnership with the Department of Energy, has permitted the use of the tunnel closure project at the former nuclear test site as a foundation on which to support cost-effective, research-and-development-funded experiments. These experiments are principally designed to improve U.S. capabilities to monitor and verify the Comprehensive Test Ban Treaty (CTBT), but have provided a new source of information on the effects of nuclear and chemical explosions on hard, fractured rock environments. These new data extends and confirms the results of recent Russian publications on the rock environment at the site and the mechanical effects of large-scale chemical and nuclear testing. In 1998, a large-scale tunnel closure experiment, Omega-1, was conducted in Tunnel 214 at Degelen mountain. In this experiment, a 100-ton chemical explosive blast was used to test technologies for monitoring the

  6. Correlation of Neutron Data Taken at Commercial Nuclear Sites

    Energy Technology Data Exchange (ETDEWEB)

    Rathbun, L. A.; Endres, G. W.R.

    1983-10-01

    In this report, data from neutron measurement and dosimetry studies performed by Pacific Northwest Laboratory, the Environmental Measurements Laboratory, and Rensselaer Polytechnic Institute are examined and compared. The purpose of this data correlation effort is to determine whether useful relationships exist between the actual neutron dose equivalent in a typical commercial nuclear power reactor and various measurement parameters, such as ratios of the response of 9-in. to 3-in. spheres, neutron/gamma ratios, albedo dosimeter response and neutron spectrometer readings. In most neutron radiation fields found in the reactors visited, the response of albedo dosimeters can be brought into reasonable agreement with dose equivalents measured with multispheres, tissue equivalent proportional counters (TEPCs) or remmeters. Because the responses of the remmeters, like the responses of albedo dosimeters, are energy dependent, it is preferable to correct the responses of the albedo dosimeters to agree with dose equivalents measured with either TEPCs or multispheres. If one of these laboratory systems has been used to measure neutron dose equivalents at a specific pressurized water reactor, a calculated average albedo dosimeter correction factor can be used for most locations at that reactor. However, if the measured 9-in. to 3-in. remmeter ratio is greater than 0.20, it is advisable to use a plot of 9-in. to 3-in. remmeter ratios versus albedo dosimeter correction factors to obtain an albedo dosimeter correction factor. Because 9-in. to 3-in. remmeter ratios at boiling water reactors are typically greater than 0.20, the latter approach applies to this type of reactor.

  7. Brazilian nuclear power plants decommissioning plan for a multiple reactor site

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R., E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas. Programa de Pos-Graduacao em Energia e Engenharia da Energia

    2015-07-01

    Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

  8. Brazilian nuclear power plants decommissioning plan for a multiple reactor site

    International Nuclear Information System (INIS)

    Monteiro, Deiglys B.; Moreira, Joao M.L.; Maiorino, Jose R.

    2015-01-01

    Actually, Brazil has two operating Nuclear Power Plants and a third one under construction, all at Central Nuclear Almirante Alvaro Alberto - CNAAA. To comply with regulatory aspects the power plants operator, Eletronuclear, must present to Brazilian Nuclear Regulatory Agency, CNEN, a decommissioning plan. Brazilian experience with decommissioning is limited because none of any nuclear reactor at the country was decommissioned. In literature, decommissioning process is well described despite few nuclear power reactors have been decommissioned around the world. Some different approach is desirable for multiple reactors sites, case of CNAAA site. During the decommissioning, a great amount of wastes will be produced and have to be properly managed. Particularly, the construction of Auxiliary Services on the site could be a good choice due to the possibility of reducing costs. The present work intends to present to the Eletronuclear some aspects of the decommissioning concept and decommissioning management, storage and disposal de wastes, based on the available literature, regulatory standards of CNEN and international experience as well as to suggest some solutions to be implemented at CNAAA site before starts the decommissioning project in order to maximize the benefits. (author)

  9. Assessment of 222Rn occupational exposure at IPEN nuclear materials storage site, SP, Brazil

    International Nuclear Information System (INIS)

    Caccuri, Lilian Saueia

    2007-01-01

    In this study it was assessed the occupational exposure to 222 Rn at IPEN, SP, Brazil, nuclear materials storage site through the committed effective dose received by workers exposed to this radionuclide. The radiation dose was calculated through the radon concentrations at nuclear materials storage site. Radon concentrations were determined by passive detection method with solid state nuclear detectors (SSNTD). The SSNTD used in this study was the polycarbonate Makrofol E; each detector is a small square plastic of 1 cm 2 , placed into a diffusion chamber type KFK. It was monitored 14 points at nuclear materials storage site and one external point, over a period of 21 months, changing the detectors every three months, from December 2004 to September 2006. The 222 Rn concentrations varied from 196 ± 9 and 2048 ± 81 Bq·m -3 . The committed effective dose due to radon inhalation at IPEN nuclear materials storage site was obtained from radon activity incorporated and dose conversion factor, according to International Commission on Radiological Protection procedures. The effective committed dose received by workers is below 20 mSv·y -1 . This value is suggested as an annual effective dose limit for occupational exposure by ICRP 60. (author)

  10. Application of RASCAL code for multiunit accident in domestic nuclear sites

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sang Hyun; Jeong, Seung Young [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-10-15

    All of domestic nuclear power plant sites are multiunit site (at least 5 - 6 reactors are operating), so this capability has to be quickly secured for nuclear licensee and institutes responsible for nuclear emergency response. In this study, source term and offsite dose from multiunit event were assessed using a computer code, RASCAL. An emergency exercise scenario was chosen to verify applicability of the codes to domestic nuclear site accident. Employing tools and new features of the code, such as merging more than two individual source terms and source term estimate for long term progression accident, main parameters and information in the scenario, release estimates and dose projections were performed. Radiological releases and offsite doses from multiunit accident were calculated using RASCAL.. A scenario, in which three reactors were damaged coincidently by a great natural disaster, was considered. Surrogate plants were chosen for the code calculation. Source terms of each damaged unit were calculated individually first, and then total source term and integrated offsite dose assessment data was acquired using a source term merge function in the code. Also comparison between LTSBO and LOCA source term estimate options was performed. Differences in offsite doses were caused by release characteristics. From LTSBO option, iodines were released much higher than LOCA. Also LTSBO source term release was delayed and the duration was longer than LOCA. This option would be useful to accidents which progress with much longer time frame than LOCA. RASCAL can be useful tool for radiological consequence assessment in domestic nuclear site accidents.

  11. Seismic stability evaluation using 2-D FEM analysis for modeling nuclear power plants sited on gravel soil

    International Nuclear Information System (INIS)

    Iba, T.; Konno, T.; Irino, K.; Hama, I.; Oguro, E.; Iizuka, S.; Enami, A.

    1995-01-01

    Throughout Europe and the United States, many nuclear power plants have been built on Quaternary deposit sites. While in Japan, all nuclear power plants have been built at rock sites primarily to maintain a high seismic resistivity. However, as more nuclear power plants are planned for the future, it has become necessary to develop new siting technology from the stand point of expanding the available range of site selection and effective utilization of land. A draft on guidelines of the seismic design for siting on Quaternary deposits is being carried out with a purpose to ensure proper design and construction for such sites. (author). 10 figs., 2 tabs

  12. Preliminary results on food consumption rates for off-site dose calculation of nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Gab Bock; Chung, Yang Geun; Bang, Sun Young; Kang, Duk Won

    2005-01-01

    The Internal dose by food consumption mostly account for radiological dose of public around nuclear power plants(NPP). But, food consumption rate applied to off-site dose calculation in Korea which is the result of field investigation around Kori NPP by the KAERI in 1988. is not reflected of the latest dietary characteristics. The Ministry of Health and Welfare Affairs has investigated the food and nutrition of nations every 3 years based on the Law of National Health Improvement. To update the food consumption rates of the maximum individual, the analysis of the national food investigation results and field surveys around nuclear power plant sites have been carried out

  13. The use of on-site Project Officers by a nuclear regulatory body

    International Nuclear Information System (INIS)

    Beare, J.W.

    1977-01-01

    In Canada consideration of applications for licensing nuclear installations is entrusted to the Reactor Safety Advisory Committee within the Atomic Energy Control Board (AECB). The licensing procedure is conducted in three stages (site approval, construction licence, operating licence). In order to control construction and operation of nuclear installations Project Officers are assigned to each particular installation. The policy of AECB is to send these officers on site several months before the reactor reaches criticality; and during reactor operation. This system clearly provides great practical advantages. (NEA) [fr

  14. Early site reviews for nuclear power facilities: procedures and possible technical review options. Draft

    International Nuclear Information System (INIS)

    1978-02-01

    The document provides guidance for utility companies, State and other governmental agencies, and others who may request or may wish to participate in an early review of site suitability issues related to a site proposed for a nuclear power or test reactor. Although the emphasis of this document is on a nuclear electric generating station, the guidance provided can be used for a test reactor or other kinds of reactors. The procedures to be followed by applicants for construction permits and by others are described and the possible significant areas of technical review are delineated

  15. Earthquakes and associated topics in relation to nuclear power plant siting

    International Nuclear Information System (INIS)

    1991-01-01

    This Safety Guide was prepared as part of the Agency's programme for establishing Codes and Safety Guides relating to nuclear power plants. The main purpose of the text is to provide guidance on the determination of the design basis ground motions for a nuclear power plant at a chosen site and on the determination of the potential for surface faulting at that site. Additionally, the Guide discusses other permanent displacement phenomena (liquefaction, slope instability, subsidence and collapse) and introduces the topic of seismically induced flooding. Volcanic activity is not dealt with except in connection with tsunamis. 55 refs

  16. The Choice of Sites for the First Nuclear Power Plants in Brazil

    International Nuclear Information System (INIS)

    Cintra do Prado, L.

    1966-01-01

    In selecting the sites for nuclear power plants a decision has to be taken as to (1) which area of the country is best suited for the purpose - e.g. the area of Recife, Rio or Sao Paulo, etc. - given the trend in energy requirements and the availability of resources, and (2) where to site the plant or plants within that area. In this paper I shall concentrate on the first of these problems and shall be concerned with assessing the merits and demerits of installing nuclear power plants in certain regions of Brazil which seem particularly well suited for the purpose

  17. Impact of offshore nuclear generating stations on recreational behavior at adjacent coastal sites. Technical report

    International Nuclear Information System (INIS)

    Baker, E.J.; Moss, D.J.; West, S.G.; Weyant, J.K.

    1977-12-01

    A multi-faceted investigation was undertaken to project the impact of offshore nuclear power plants on beach visitation at adjacent beaches. 1. Related literature was reviewed concerning human adjustment to natural hazards, risk-taking behavior, and public attitudes toward nuclear power. 2. Approximately 2400 people were interviewed at beaches in three states with respect to: (a) intended avoidance of beaches near a hypothetical floating nuclear plant (FNP), (b) relative importance of proximity to a FNP, when compared to other beach attributes, (c) onshore-offshore preference for coastal nuclear plant location, (d) behavioral impact of NRC licensing of FNP's, (e) relative tourism impact of coastal nuclear plant compared to coastal coal-fired plant, (f) public concerns about nuclear safety, (g) public attitudes toward alternative energy sources, (h) public confidence in sources of information about nuclear power, (i) visual impact of a FNP, and (j) knowledge about nuclear power. 3. Four beach areas near currently operating coastal nuclear power plants were studied to assess impacts on tourism resulting from plant construction. Data suggest that proximity of a FNP is less important than other beach attributes in determining beach attractiveness, probably no more than (and perhaps less than) 5% to 10% of current beach patrons would avoid a beach after FNP siting three miles directly offshore, and impact of a FNP would decrease exponentially as distance away increased

  18. Impact of offshore nuclear generating stations on recreational behavior at adjacent coastal sites

    International Nuclear Information System (INIS)

    Baker, E.J.; West, S.G.; Moss, D.J.; Weyant, J.K.

    1977-10-01

    A multi-faceted investigation was undertaken to project the impact of offshore nuclear power plants on beach visitation at adjacent beaches. Related literature was reviewed concerning human adjustment to natural hazards, risk-taking behavior, and public attitudes toward nuclear power. Approximately 2400 people were interviewed at beaches in three states with respect to: intended avoidance of beaches near a hypothetical floating nuclear plant (FNP), relative importance of proximity to a FNP, when compared to other beach attributes, onshore-offshore preference for coastal nuclear plant location, behavioral impact of NRC licensing of FNPs, relative tourism impact of coastal nuclear plant compared to coastal coal-fired plant, public concerns about nuclear safety, public attitudes toward alternative energy sources, public confidence in sources of information about nuclear power, visual impact of a FNP, and knowledge about nuclear power. Four beach areas near currently operating coastal nuclear power plants were studied to assess impacts on tourism resulting from plant construction. Data suggest that proximity of a FNP is less important than other beach attributes in determining beach attractiveness, probably no more than (and perhaps less than) 5% to 10% of current beach patrons would avoid a beach after FNP siting three miles directly offshore, and impact of a FNP would decrease exponentially as distance away increased

  19. Procedures for evaluation of vibratory ground motions of soil deposits at nuclear power plant sites

    International Nuclear Information System (INIS)

    1975-06-01

    According to USNRC requirements set forth in Appendix A, 10 CFR, Part 100, vibratory ground motion criteria for a nuclear plant must be based on local soil conditions, as well as on the seismicity, geology, and tectonics of the region. This report describes how such criteria can be developed by applying the latest technology associated with analytical predictions of site-dependent ground motions and with the use of composite spectra obtained from the current library of strong motion records. Recommended procedures for defining vibratory ground motion criteria contain the following steps: (1) geologic and seismologic studies; (2) site soils investigations; (3) site response sensitivity studies; (4) evaluation of local site response characteristics; (5) selection of site-matched records; and (6) appraisal and selection of seismic input criteria. An in-depth discussion of the engineering characteristics of earthquake ground motions including parameters used to characterize earthquakes and strong motion records, geologic factors that influence ground shaking, the current strong motion data base, and case histories of the effects of past earthquake events is presented. Next, geotechnical investigations of the seismologic, geologic, and site soil conditions required to develop vibratory motion criteria are briefly summarized. The current technology for establishing vibratory ground motion criteria at nuclear plant sites, including site-independent and site-dependent procedures that use data from strong motion records and from soil response analyses is described. (auth)

  20. Site-specific parameter values for the Nuclear Regulatory Commission's food pathway dose model

    International Nuclear Information System (INIS)

    Hamby, D.M.

    1992-01-01

    Routine operations at the Savannah River Site (SRS) in Western South Carolina result in radionuclide releases to the atmosphere and to the Savannah River. The resulting radiation doses to the off-site maximum individual and the off-site population within 80 km of the SRS are estimated on a yearly basis. These estimates are currently generated using dose models prescribed for the commercial nuclear power industry by the Nuclear Regulatory Commission (NRC). The NRC provides default values for dose-model parameters for facilities without resources to develop site-specific values. A survey of land- and water-use characteristics for the Savannah River area has been conducted to determine site-specific values for water recreation, consumption, and agricultural parameters used in the NRC Regulatory Guide 1.109 (1977) dosimetric models. These site parameters include local characteristics of meat, milk, and vegetable production; recreational and commercial activities on the Savannah River; and meat, milk, vegetable, and seafood consumption rates. This paper describes how parameter data were obtained at the Savannah River Site and the impacts of such data on off-site dose. Dose estimates using site-specific parameter values are compared to estimates using the NRC default values

  1. Different methods of informing the public on projected sites of nuclear generating stations. Results in France

    International Nuclear Information System (INIS)

    Taccoen, L.B.C.

    1977-01-01

    The situation in France of local public opinion concerning nuclear power stations is very different, according to the region in question. It seems that in industrialized regions, where the inhabitants are already familiar with nuclear energy, public opinion is much more open to the installation of new reactors. In regions which are only slightly industrialized, however, the prejudices of the population against nuclear energy can be very strong. This situation is quite serious because it could lead to an even greater widening of the development gap between various regions in France. Electricite de France has thus been led to develop a program of public information concerning the problems of nuclear energy. In practice, this program consists of: a policy of active presence in meeting and debates as well as at the actual site; eventual opening of information centers; and organization of visists of existing nuclear power stations [fr

  2. Siting studies for an asymptotic U.S. energy supply system based primarily on nuclear energy

    International Nuclear Information System (INIS)

    Burwell, C.C.

    1977-01-01

    The nuclear energy center (NEC) concept is an approach to siting wherein nuclear facilities would be clustered in and delimited to a relatively small number of locations throughout the United States. These designated centers would be concurrently developed to their full capability over several decades, at which time, they would be several times larger than the largest nuclear power stations in existence today. The centers would be permanently dedicated to nuclear operations including the future decommissioning of functionally obsolescent facilities as well as the commissioning of their replacements. The criteria for and characteristics of an acceptable nuclear energy system that could supply most of the U.S. energy requirements in the distant future are discussed. The time period is unspecified but occurs when fossil-fuel resources are depleted to such an extent that their use is economic only in special situations, and is not economic, in general, for use as fuel

  3. The public visits a nuclear waste site: Survey results from the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    Hoffman, W.D.

    1987-01-01

    This paper discusses the results of the 1986 survey taken at the West Valley Demonstration Project Open House where a major nuclear waste cleanup is in progress. Over 1400 people were polled on what they think is most effective in educating the public on nuclear waste. A demographic analysis describes the population attending the event and their major interests in the project. Responses to attitudinal questions are examined to evaluate the importance of radioactive waste cleanup as an environmental issue and a fiscal responsibility. Additionally, nuclear power is evaluated on its public perception as an energy resource. The purpose of the study is to find out who visits a nuclear waste site and why, and to measure their attitudes on nuclear issues

  4. A Preliminary Assessment of Daily Weather Conditions in Nuclear Site for Development of Effective Emergency Plan

    International Nuclear Information System (INIS)

    Han, Seok Jung; Ahn, Kwang Il

    2012-01-01

    A radiological emergency preparedness for nuclear sites is recognized as an important measure against anticipated severe accidents with environmental releases of radioactive materials. While there are many individual means in the emergency preparedness for nuclear accidents, one of most important means is to make a decision of evacuation or shelter of the public residents with the emergency plan zone (EPZ) of a nuclear site. In order to prepare an effective strategy for the evacuation as a basis of the emergency preparedness, it may need the understanding of atmospheric dispersion characteristics of radiation releases to the environment, mainly depending upon the weather conditions of a radiation releases location, i.e., a nuclear site. As a preliminary study for the development of an effective emergency plan, the basic features of the weather conditions of a specific site were investigated. A main interest of this study is to identify whether or not the site weather conditions have specific features helpful for a decision making of evacuation of the public residents

  5. Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

    International Nuclear Information System (INIS)

    Elder, J.; Graf, J.M.

    1984-01-01

    DOE Office of Nuclear Safety has sponsored preparation of a guidance document to aid field offices and contractors in their analyses of consequences of postulated major accidents. The guide addresses the requirements of DOE Orders 5480.1A, Chapter V, and 6430.1, including the general requirement that DOE nuclear facilities be sited, designed, and operated in accordance with standards, codes, and guides consistent with those applied to comparable licensed nuclear facilities. The guide includes both philosophical and technical information in the areas of: siting guidelines doses applied to an offsite reference person; consideration also given to an onsite reference person; physical parameters, models, and assumptions to be applied when calculating doses for comparison to siting criteria; and potential accident consequences other than radiological dose to a reference person which might affect siting and major design features of the facility, such as environmental contamination, population dose, and associated public health effects. Recommendations and/or clarifications are provided where this could be done without adding new requirements. In this regard, the guide is considered a valuable aid to the safety analyst, especially where requirements have been subject to inconsistent interpretation or where analysis methods are in transition, such as use of dose model (ICRP 2 or ICRP 30) or use of probabilistic methods of risk analysis in the siting and design of nuclear facilities

  6. Study of the legal problems raised by the siting of nuclear power stations in artificial islands

    International Nuclear Information System (INIS)

    Hebert, J.; Guieze, J.L.

    1975-01-01

    The creation and operation of a nuclear power station on an artificial island in French waters are governed by domestic law and are subject to two types of procedure: the first concerns erection of the artificial island and the second the control of the public authorities over creation and operation of the nuclear power station. At administrative level, the setting up of an artificial island requires that it be attached to a commune as well as permission for occupancy from the maritime authorities. Furthermore, setting up of a nuclear power station on an artificial island is subject to the licensing procedure for large nuclear installations and to delivery of the licenses required for release of gaseous and liquid radioactive effluents. Given the proximity of the high seas and eventually, the borders of other States, siting of a nuclear power station on an artificial island imposes obligations at international level. These requirements, which concern prevention of transfrontier pollution, stem from the London (1972) and Paris (1974) Conventions on marine pollution. The third party liability regime for a nuclear incident caused by an installation sited in territorial seas is that of the 1960 Paris Convention on third party liability in the nuclear field and the 1963 Brussels Supplementary Convention. Another problem likely to be raised is that of the right of innocent passage of ships near such installations [fr

  7. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requirements of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs.

  8. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    1988-01-01

    Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requiremenrs of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs

  9. Treatment and final disposal of nuclear waste. Siting of a deep repository

    International Nuclear Information System (INIS)

    1992-09-01

    Systems and facilities in the program for demonstration deposition of nuclear waste are presented. The siting process is described, from the general studies to the ultimate goal, where a permit to start demonstration deposition has been obtained. National and foreign experiences of siting issues are accounted for. Finally, the structure and plan for work for 1993-98 are outlined. 46 refs, 15 figs, 5 tabs

  10. Methodology to evaluate the site standard seismic motion for a nuclear facility

    International Nuclear Information System (INIS)

    Soares, W.A.

    1983-03-01

    An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic priciples of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; avalable methodologies and recommended procedures to evaluate the site standard seismic motion. (E.G.) [pt

  11. Alternative off-site power supply improves nuclear power plant safety

    International Nuclear Information System (INIS)

    Gjorgiev, Blaže; Volkanovski, Andrija; Kančev, Duško; Čepin, Marko

    2014-01-01

    Highlights: • Additional power supply for mitigation of the station blackout event in NPP is used. • A hydro power plant is considered as an off-site alternative power supply. • An upgrade of the probabilistic safety assessment from its traditional use is made. • The obtained results show improvement of nuclear power plant safety. - Abstract: A reliable power system is important for safe operation of the nuclear power plants. The station blackout event is of great importance for nuclear power plant safety. This event is caused by the loss of all alternating current power supply to the safety and non-safety buses of the nuclear power plant. In this study an independent electrical connection between a pumped-storage hydro power plant and a nuclear power plant is assumed as a standpoint for safety and reliability analysis. The pumped-storage hydro power plant is considered as an alternative power supply. The connection with conventional accumulation type of hydro power plant is analysed in addition. The objective of this paper is to investigate the improvement of nuclear power plant safety resulting from the consideration of the alternative power supplies. The safety of the nuclear power plant is analysed through the core damage frequency, a risk measure assess by the probabilistic safety assessment. The presented method upgrades the probabilistic safety assessment from its common traditional use in sense that it considers non-plant sited systems. The obtained results show significant decrease of the core damage frequency, indicating improvement of nuclear safety if hydro power plant is introduced as an alternative off-site power source

  12. Main phases of siting for nuclear power plants with review of required investigations

    International Nuclear Information System (INIS)

    Malbasa, N.

    1984-01-01

    The purpose of the article is a short description of the main phases in the process of siting for nuclear power plants as interpreted and applied by the Institut za elektroprivredu, Zagreb in the screening, comparison and evaluation of the sites for NPPs in the SR of Croatia. The scope and purpose, as well as review of required data and investigations for each particular phase are given. Common used methods for the comparison of sites are described and example of rejection criteria applicable for early phases of the siting is proposed. It is given a list of the most important activities which detailed analysis id indispensable for ending of the evaluation and getting a site permit from the regulatory body. A legal and regulatory basis for carrying out the siting process is also described. (author)

  13. NWTS program criteria for mined geologic disposal of nuclear wasite: site performance criteria

    International Nuclear Information System (INIS)

    1981-02-01

    This report states ten criteria governing the suitability of sites for mined geologic disposal of high-level radioactive waste. The Department of Energy will use these criteria in its search for sites and will reevaluate their use when the Nuclear Regulatory Commission issues radioactive waste repository rules. These criteria encompass site geometry, geohydrology, geochemistry, geologic characteristics, tectonic environment, human intrusion, surface characteristics, environment, and potential socioeconomic impacts. The contents of this document include background discussion, site performance criteria, and appendices. The background section describes the waste disposal system, the application of the site criteria, and applicable criteria from NWTS-33(1) - Program Objectives, Functional Requirements and System Performance Criteria. Appendix A, entitled Comparison with Other Siting Criteria compares the NWTS criteria with those recommended by other agencies. Appendix B contains DOE responses to public comments received on the January 1980 draft of this document. Appendix C is a glossary

  14. Quantitative comparison of the nuclear power plant sites in the United Kingdom

    Energy Technology Data Exchange (ETDEWEB)

    Shaw, J; Sina, A M [Queen Mary Coll., London (UK). Dept. of Nuclear Engineering

    1976-01-01

    A probabilistic method is described for a comparison of nuclear power plant sites in the United Kingdom, which evaluates quantitatively the sites in terms of favourability, by taking into account the real term meteorological conditions, i.e. wind direction, wind speed, and stability distributions, and also the population distribution around the cities. A 'site safety quality factor' is obtained for each site and is used to compare the favourability of each site with respect to releases of radioactivity. The quality factor corresponds to the average number of persons that would be exposed to the specified relative concentration averaged over all weather conditions. The sites compared are Berkeley, Bradwell, Dungeness, Hartlepool, Heysham, Oldbury, Sizewell, and Wylfa.

  15. Should high-level nuclear waste be disposed of at geographically dispersed sites?

    International Nuclear Information System (INIS)

    Bassett, G.W. Jr.

    1992-01-01

    Consideration of the technical feasibility of Yucca Mountain in Nevada as the site for a high-level nuclear waste repository has led to an intense debate regarding the economic, social, and political impacts of the repository. Impediments to the siting process mean that the nuclear waste problem is being resolved by adhering to the status quo, in which nuclear waste is stored at scattered sites near major population centers. To assess the merits of alternative siting strategies--including both the permanent repository and the status quo- we consider the variables that would be included in a model designed to select (1) the optimal number of disposal facilities, (2) the types of facilities (e.g., permanent repository or monitored retrievable facility), and (3) the geographic location of storage sites. The objective function in the model is an all-inclusive measure of social cost. The intent of the exercise is not to demonstrate the superiority of any single disposal strategy; uncertainties preclude a conclusive proof of optimality for any of the disposal options. Instead, we want to assess the sensitivity of a variety of proposed solutions to variations in the physical, economic, political, and social variables that influence a siting strategy

  16. Safeguards for final disposal of spent nuclear fuel. Methods and technologies for the Olkiluoto site

    International Nuclear Information System (INIS)

    Okko, O.

    2003-05-01

    The final disposal of the nuclear material shall introduce new safeguards concerns which have not been addressed previously in IAEA safeguards approaches for spent fuel. The encapsulation plant to be built at the site will be the final opportunity for verification of spent fuel assemblies prior to their transfer to the geological repository. Moreover, additional safety and safeguards measures are considered for the underground repository. Integrated safeguards verification systems will also concentrate on environmental monitoring to observe unannounced activities related to possible diversion schemes at the repository site. The final disposal of spent nuclear fuel in geological formation will begin in Finland within 10 years. After the geological site investigations and according to legal decision made in 2001, the final repository of the spent nuclear fuel shall be located at the Olkiluoto site in Eurajoki. The next phase of site investigations contains the construction of an underground facility, called ONKALO, for rock characterisation purposes. The excavation of the ONKALO is scheduled to start in 2004. Later on, the ONKALO may form a part of the final repository. The plans to construct the underground facility for nuclear material signify that the first safeguards measures, e.g. baseline mapping of the site area, need to take prior to the excavation phase. In order to support the development and implementation of the regulatory control of the final disposal programme, STUK established an independent expert group, LOSKA. The group should support the STUK in the development of the technical safeguards requirements, in the implementation of the safeguards and in the evaluation of the plans of the facility operator. This publication includes four background reports produced by this group. The first of these 'NDA verification of spent fuel, monitoring of disposal canisters, interaction of the safeguards and safety issues in the final disposal' describes the new

  17. Evolution of the Business Environment Surrounding the UK's Nuclear Site Cleanup Program

    International Nuclear Information System (INIS)

    Miskimin, P.A.; Lees, P.M.; Wall, C.E.E.

    2006-01-01

    In April 2005 twenty civil nuclear sites in the United Kingdom became the responsibility of the Nuclear Decommissioning Authority (NDA), a new organization created by the British Government to manage the cleanup of these sites. As a key part of this transition, the NDA became the owner and manager of these sites, which formerly were owned by the site operators, British Nuclear Fuels Limited plc (BNFL) and the United Kingdom Atomic Energy Authority (UKAEA). This was one of the most significant events in the history of the United Kingdom's nuclear industry and represented a true sea change, affecting many aspects of life and business on and around these sites as well as nationally. The NDA's budget for the cleanup of the twenty sites and the management of the overall cleanup program is approximately pounds 2 Billion per annum, almost $4 Billion. It is important to note that approximately half of this amount is spent with the supply chains which serve the management and operations contractors, including pounds 500 million at Sellafield alone. Additionally, the site management and operations contractors receive most of the pounds 2 Billion through contracts between the NDA and the various site management companies. This represents a lot of government money moving through contracts between entities, which invokes procurement and contracting rules and regulations, that while not new, have not previously been this broadly applied to nuclear site cleanup activities throughout the UK. The current estimate for the total life cycle cleanup costs for all twenty civil nuclear sites is pounds 56 Billion, a figure that is likely to increase further. The first rules to mention are the European Union Procurement Guidelines, which are designed to help ensure that procurements involving government funds are conducted in an open, fair, and transparent environment. While it is difficult to argue with the intent of these rules, at least for now they are having a slowing down effect on

  18. Childhood cancer incidence in relation to distance from the former nuclear testing site in Semipalatinsk, Kazakhstan.

    Science.gov (United States)

    Zaridze, D G; Li, N; Men, T; Duffy, S W

    1994-11-15

    Rates of childhood cancer between 1981 and 1990 in the 4 administrative zones of Kazakhstan were studied to assess the relationship, if any, with distance from nuclear testing sites. Risk of various cancers among children aged 14 years or younger were estimated in relation to distance from (1) a site where testing in air was performed before 1963, (2) a site where underground testing took place thereafter, and (3) a reservoir, known as "Atom Lake," created by 4 nuclear explosions in 1965. Risk of acute leukaemia rose significantly with increasing proximity of residence to the testing areas, although the absolute value of the risk gradient was relatively small. The relative risk for those living less than 200 km from the air-testing site was 1.76 compared with those living 400 km or more away from the site. Similar relative risks were observed for the underground site and "Atom Lake." There was also some evidence of increased risk of brain tumours in association with proximity to the test sites. In 2 of the 4 zones studied, there was substantial regional variation in acute leukaemia rates which was not attributable to distance from the test site. The findings may be affected by potential confounders, notably urban/rural status and ethnic factors.

  19. Site infrastructure as required during the construction and erection of nuclear power plants

    International Nuclear Information System (INIS)

    Haas, K.F.; Wagner, H.

    1978-01-01

    In general, in an exchange of experience on constructing nuclear power plants priority is given to design and lay-out, financing, quality assurance etc., but in this paper an attempt has been made to describe range and type of site infrastructure required during construction and erection. Site infrastructure will make considerable demands on the planning, supply of material and maintenance that may result from the frequently very isolated location of power plant sites. Examples for specific values and experiences are given for a nuclear power plant with two units on the 1300-MW type at present under construction of the Persian Gulf in Iran. Data concerning the site infrastructure, including examples, are given and explained on the basis of graphs. The site is split up into a technical and a social infrastructure. The main concern of the technical site infrastructure is the timely provision and continuous availability of electric energy, water, communication grids, workshops, warehouses, offices, transport and handling facilities, as well as the provision of heavy load roads, harbour facilities, etc. The social site infrastructure in general comprises accommodation, food supplies and the care and welfare of all site personnel, which includes a hospital, school, self-service shop, and sport and recreation facilities. (author)

  20. In Situ Analytical Characterization of Contaminated Sites Using Nuclear Spectrometry Techniques. Review of Methodologies and Measurements

    International Nuclear Information System (INIS)

    2017-01-01

    Past and current human activities can result in the contamination of sites by radionuclides and heavy metals. The sources of contamination are various. The most important sources for radionuclide release include global fallout from nuclear testing, nuclear and radiological accidents, waste production from nuclear facilities, and activities involving naturally occurring radioactive material (NORM). Contamination of the environment by heavy metals mainly originates from industrial applications and mineralogical background concentration. Contamination of sites by radionuclides and heavy metals can present a risk to people and the environment. Therefore, the estimation of the contamination level and the identification of the source constitute important information for the national authorities with the responsibility to protect people and the environment from adverse health effects. In situ analytical techniques based on nuclear spectrometry are important tools for the characterization of contaminated sites. Much progress has been made in the design and implementation of portable systems for efficient and effective monitoring of radioactivity and heavy metals in the environment directly on-site. Accordingly, the IAEA organized a Technical Meeting to review the current status and trends of various applications of in situ nuclear spectrometry techniques for analytical characterization of contaminated sites and to support Member States in their national environmental monitoring programmes applying portable instrumentation. This publication represents a comprehensive review of the in situ gamma ray spectrometry and field portable X ray fluorescence analysis techniques for the characterization of contaminated sites. It includes papers on the use of these techniques, which provide useful background information for conducting similar studies, in the following Member States: Argentina, Australia, Brazil, Czech Republic, Egypt, France, Greece, Hungary, Italy, Lithuania

  1. Rock siting of nuclear power plants from a reactor safety standpoint

    International Nuclear Information System (INIS)

    1975-11-01

    The study has aimed at surveying the advantages and disadvantages of a rock sited nuclear power plant from a reactor safety standpoint. The studies performed are almost entirely concentrated on the BWR alternative. The design of a nuclear power plant in rock judged most appropriate has been studied in greater detail, and a relatively extensive safety analysis has been made. It is found that the presented technical design of the rock sited alternative is sufficiently advanced to form a basis for further projecting treatment. The chosen technical design of the reactor plant demands a cavern with a 45-50 metre span. Caverns without strengthening efforts with such spans are used in mines, but have no previously been used for industrial plants. Studies of the stability of such caverns show that a safety level is attainable corresponding to the safety required for the other parts of the nuclear power plant. The conditions are that the rock is of high quality, that necessary strengthening measures are taken and that careful studies of the rock are made before and during the blasting, and also during operation of the plant. When locating a rock sited nuclear power plant, the same criteria must be considered as for an above ground plant, with additional stronger demands for rock quality. The presented rock sited nuclear power plant has been assessed to cost 20 % more in total construction costs than a corresponding above ground plant. The motivations for rock siting also depend on whether a condensing plant for only electricity production, or a plant for combined power production and district heating, is considered. The latter would under certain circumstances make rock siting look more attractive. (author)

  2. Peculiarities of radionuclide contamination of different Semipalatinsk nuclear test site (SNTS) zones

    International Nuclear Information System (INIS)

    Kadyrzhanov, K.K.; Khazhekber, S.; Lukashenko, S.N.; Solodukhin, V.P.; Kazachevskij, I.V.; Poznyak, V.L.; Knyazev, B.B.; Rofer, Ch.

    2002-01-01

    The Semipalatinsk Nuclear Test Site occupies about 18500 km 2 . There are 3 basic test zones in this territory including various test platforms where different character nuclear explosions were carried out. On the test platforms of the 'Opytnoe Pole' zone air and ground tests were performed, including nuclear and hydronuclear (without nuclear reaction) explosions. On the other zones (the Degelen mountains and Balapan valley) the underground tests including camouflaged and excavation nuclear explosions were carried out. Each kind of these tests can be characterised by the quantity and composition of radionuclides which were formed during the nuclear explosion, by the area of their distribution, localisation of the radionuclides at various sites, radionuclide species in soil. Transfer of the products of the air and the ground nuclear explosions by air flows and their sedimentation on the ground surfaces have caused broadband radioactive plumes extending over hundreds of kilometres. As a result of hydronuclear experiments, plenty of alpha-active radionuclides, consisting of a nuclear device is thrown locally out. Besides the ground and the air explosions, radiation conditions of the territory of the SNTS were influenced by excavation explosions with ground throwing out. Such tests resulted in an intensive local pollution. Other zone of an original pollution is the Degelen mountains. Although an basic mass of the nuclear explosion products is obviously concentrated in basin cavities of the tunnels, the radionuclides are taken out on a day time surface together with waters acting in the basin cavity of the tunnels. The results of investigation of radionuclide pollution on the various platforms of the SNTS territory are presented. The results characterise the radionuclide pollution by specificity of spent tests

  3. The Site Selected. The Local Decision-Making Regarding the Siting of the Spent Nuclear Fuel Repository in Olkiluoto

    International Nuclear Information System (INIS)

    Kojo, Matti

    2006-01-01

    In May 1999 Posiva, the company responsible for the final disposal of spent nuclear fuel in Finland, suggested that the Finnish Government considers only Olkiluoto in Eurajoki in its application of a decision in principle to be a final disposal site. In January 2000 the municipal council of Eurajoki made a positive statement on the decision in principle. The Government made the decision in principle in Dec 2000, and the Parliament ratified the decision in May 2001. The paper is focused on the decision making of Eurajoki municipality regarding the siting of the spent nuclear fuel repository. The paper shows how the interaction between the representatives of the candidate municipality and the nuclear energy industry was the crucial factor in the decision-making. Eurajoki serves as an example, in where the parties reached an agreement of the compensations for the final disposal repository. The negotiations between the Eurajoki municipality and the nuclear energy industry in reaching a positive decision are analysed from the beginning of the 1980s. The main emphasis is however on the years 1996-99, when the nuclear energy industry negotiated with the municipality on the compensation for the final disposal repository. The loss of income was an important reason why some of the councillors of Eurajoki were interested in having the final disposal repository in Olkiluoto. The industry's problem on the other hand was to safeguard the final disposal site. From the TVO's angle Olkiluoto was a potential final disposal site for example for its limited need for transport and for the existing infrastructure. The company used the financial benefits of the project as its trump card. The attitude of Eurajoki municipality to the final disposal of spent nuclear fuel turned positive with the Olkiluoto vision in December 1998, when still five years earlier the municipal council was prepared to act and prevent the final disposal. The future image presented by the municipality now matched

  4. The Site Selected. The Local Decision-Making Regarding the Siting of the Spent Nuclear Fuel Repository in Olkiluoto

    Energy Technology Data Exchange (ETDEWEB)

    Kojo, Matti [Univ. of Tampere (Finland). Dept. of Political Science and International Relations

    2006-09-15

    In May 1999 Posiva, the company responsible for the final disposal of spent nuclear fuel in Finland, suggested that the Finnish Government considers only Olkiluoto in Eurajoki in its application of a decision in principle to be a final disposal site. In January 2000 the municipal council of Eurajoki made a positive statement on the decision in principle. The Government made the decision in principle in Dec 2000, and the Parliament ratified the decision in May 2001. The paper is focused on the decision making of Eurajoki municipality regarding the siting of the spent nuclear fuel repository. The paper shows how the interaction between the representatives of the candidate municipality and the nuclear energy industry was the crucial factor in the decision-making. Eurajoki serves as an example, in where the parties reached an agreement of the compensations for the final disposal repository. The negotiations between the Eurajoki municipality and the nuclear energy industry in reaching a positive decision are analysed from the beginning of the 1980s. The main emphasis is however on the years 1996-99, when the nuclear energy industry negotiated with the municipality on the compensation for the final disposal repository. The loss of income was an important reason why some of the councillors of Eurajoki were interested in having the final disposal repository in Olkiluoto. The industry's problem on the other hand was to safeguard the final disposal site. From the TVO's angle Olkiluoto was a potential final disposal site for example for its limited need for transport and for the existing infrastructure. The company used the financial benefits of the project as its trump card. The attitude of Eurajoki municipality to the final disposal of spent nuclear fuel turned positive with the Olkiluoto vision in December 1998, when still five years earlier the municipal council was prepared to act and prevent the final disposal. The future image presented by the municipality

  5. The historical seismicity in Spain. Analysis. Incidence over the nuclear sites

    International Nuclear Information System (INIS)

    Lopez Marinas, J.M.

    1985-01-01

    The lack of good instrumental registers till very recently and the great documental richness existing in Spain emphasize the importance of the historical seismicity. In the present report, the Spanish catalogues of earthquakes and the necessity of their revision are analyzed showing several examples. Finally the incidence of a historical seismicity datum over a nuclear site is discussed. (author)

  6. Evaluation of nuclear power plant siting by probabilistic assessment of environmental impacts

    International Nuclear Information System (INIS)

    Vuori, S.

    1978-01-01

    The work consists of the description of a probabilistic consequence assessment model ARANO, and the individual calculation schemes therein included. This assessment model has been applied to the risk/benefit and cost/benefit analyses of the siting of nuclear power plants. In addition, there have been made some comparisons with the alternative fossil fuelled energy production scenarios. (author)

  7. Nuclear tourists: the challenge of EDF's production sites accessibility, 1974-1991

    International Nuclear Information System (INIS)

    Lopez, Fanny

    2014-01-01

    This article focuses on the evolution of accessibility of Electricite de France (EDF) production sites when the country chose energy independence in 1974. If the nuclear program seems to be at the origins of French industrial tourism, which process made these energy plants a touristic attraction?

  8. Bavarian Constitutional Court, decision of August 14, 1987 (Referendum on sites of nuclear installations)

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    In the dissenting opinion of one of the judges of the Bavarian Constitutional Court concerning the decision of August 14, 1987, the Land Bavaria has a competence according to the constitution to decide about sites of nuclear installations. Hence it follows that a referendum on this problem has to be permitted. (CW) [de

  9. The main directions of prospective cohort study of population living around the Semipalatinsk nuclear test site

    OpenAIRE

    ZHUNUSSOVA T.; GROSCHE B.; APSALIKOV K.; BELIKHINA T.; PIVINA L.; MULDAGALIEV T.

    2014-01-01

    In the paper we have presented the possibilities of prospective cohort study of health status in the radiation exposed population living around the Semipalatinsk nuclear test site. It was substantiated the necessity of international cooperation of scientists from Kazakhstan, Europe, Japan and the United States for long-term study of radiation effects for the people and the environment.

  10. Lightning vulnerability of nuclear explosive test systems at the Nevada Test Site

    International Nuclear Information System (INIS)

    Hasbrouck, R.T.

    1985-01-01

    A task force chartered to evaluate the effects of lightning on nuclear explosives at the Nevada Test Site has made several recommendations intended to provide lightning-invulnerable test device systems. When these recommendations have been implemented, the systems will be tested using full-threat-level simulated lightning

  11. Study of a conceptual nuclear-energy center at Green River, Utah: site-specific transportation

    International Nuclear Information System (INIS)

    1981-10-01

    The objective of the following report is to assess the adequacy of the local and regional transportation network for handling traffic, logistics, and the transport of major power plant components to the Utah Nuclear Energy Center (UNEC) Horse Bench site. The discussion is divided into four parts: (1) system requirements; (2) description of the existing transportation network; (3) evaluation; (4) summary and conclusions

  12. Terrain and building effects on the transport of radioactive material at a nuclear site

    International Nuclear Information System (INIS)

    Jeong, Hyojoon; Park, Misun; Jeong, Haesun; Hwang, Wontae; Kim, Eunhan; Han, Moonhee

    2014-01-01

    Highlights: • This study is to quantify the building and terrain effects on the atmospheric dispersion. • Statistical methods with AERMOD-PRIME and CFD were used. • To assess the risk in nuclear power plants, terrain and building effects have to be considered. - Abstract: This study identified the terrain and building effects on the atmospheric dispersion of radioactive materials at the Wolsong Nuclear Site. To analyze the atmospheric dispersion of radioactive materials, the AERMOD-PRIME model, CFD model and meteorological data from 2010 were used. The terrain and building effects on the atmospheric dispersion of radioactive materials within a 1 km radius of the site were statistically significant. The maximum concentration of the radioactive material increased by 7 times compared to the concentration when the terrain and building effects were not considered. It was found that the terrain and building influenced the decrease in the concentration of radioactive material in a concentric circle with a 914 m radius from the center of the site. The concentration of radioactive material in a concentric circle with a 350 m radius was two-times higher than the concentration estimated at the backside of the building, which is the downwind side, without any consideration of the terrain and building effects. In consideration of the Korean situation, in which multiple nuclear reactors are built on the same nuclear site, it is necessary to evaluate the risk that may affect workers and nearby residents by reflecting the terrain and building effects

  13. Assessment procedure and probability determination methods of aircraft crash events in siting for nuclear power plants

    International Nuclear Information System (INIS)

    Zheng Qiyan; Zhang Lijun; Huang Weiqi; Yin Qingliao

    2010-01-01

    Assessment procedure of aircraft crash events in siting for nuclear power plants, and the methods of probability determination in two different stages of prelimi- nary screening and detailed evaluation are introduced in this paper. Except for general air traffic, airport operations and aircraft in the corridor, the probability of aircraft crash by military operation in the military airspaces is considered here. (authors)

  14. Radiological analysis of materials sampled on the old nuclear test site of In Ekker (Algeria)

    International Nuclear Information System (INIS)

    Chareyron, Bruno

    2010-01-01

    After having recalled the context of the French nuclear test campaign in Algeria between 1961 and 1966, this document reports and comments radiological measurements performed on the site of In Ekker, and also results of analysis performed in laboratory (contamination by cesium 137, americium 241, plutonium); recommendations are given

  15. Assessment of hydrologic transport of radionuclides from the Gnome underground nuclear test site, New Mexico

    International Nuclear Information System (INIS)

    Earman, S.; Chapman, J.; Pohlmann, K.; Andricevic, R.

    1996-09-01

    The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary site risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Gnome site in southeastern New Mexico was the location of an underground detonation of a 3.5-kiloton nuclear device in 1961, and a hydrologic tracer test using radionuclides in 1963. The tracer test involved the injection of tritium, 90 Sr, and 137 Cs directly into the Culebra Dolomite, a nine to ten-meter-thick aquifer located approximately 150 in below land surface. The Gnome nuclear test was carried out in the Salado Formation, a thick salt deposit located 200 in below the Culebra. Because salt behaves plastically, the cavity created by the explosion is expected to close, and although there is no evidence that migration has actually occurred, it is assumed that radionuclides from the cavity are released into the overlying Culebra Dolomite during this closure process. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides may be present in concentrations exceeding drinking water regulations outside the drilling exclusion boundary established by DOE. Calculated mean tritium concentrations peak at values exceeding the U.S. Environmental Protection Agency drinking water standard of 20,000 pCi/L at distances of up to almost eight kilometers west of the nuclear test

  16. Characteristics of acoustic wave from atmospheric nuclear explosions conducted at the USSR Test Sites

    Science.gov (United States)

    Sokolova, Inna

    2015-04-01

    Availability of the acoustic wave on the record of microbarograph is one of discriminate signs of atmospheric (surface layer of atmosphere) and contact explosions. Nowadays there is large number of air wave records from chemical explosions recorded by the IMS infrasound stations installed during recent decade. But there is small number of air wave records from nuclear explosions as air and contact nuclear explosions had been conducted since 1945 to 1962, before the Limited Test Ban Treaty was signed in 1963 (the treaty banning nuclear weapon tests in the atmosphere, in outer space and under water) by the Great Britain, USSR and USA. That time there was small number of installed microbarographs. First infrasound stations in the USSR appeared in 1954, and by the moment of the USSR collapse the network consisted of 25 infrasound stations, 3 of which were located on Kazakhstan territory - in Kurchatov (East Kazakhstan), in Borovoye Observatory (North Kazakhstan) and Talgar Observatory (Northern Tien Shan). The microbarograph of Talgar Observatory was installed in 1962 and recorded large number of air nuclear explosions conducted at Semipalatinsk Test Site and Novaya Zemlya Test Site. The epicentral distance to the STS was ~700 km, and to Novaya Zemlya Test Site ~3500 km. The historical analog records of the microbarograph were analyzed on the availability of the acoustic wave. The selected records were digitized, the database of acoustic signals from nuclear explosions was created. In addition, acoustic signals from atmospheric nuclear explosions conducted at the USSR Test Sites were recorded by analogue broadband seismic stations at wide range of epicentral distances, 300-3600 km. These signals coincide well by its form and spectral content with records of microbarographs and can be used for monitoring tasks and discrimination in places where infrasound observations are absent. Nuclear explosions which records contained acoustic wave were from 0.03 to 30 kt yield for

  17. Analysis of extreme hydrometric values in the nuclear power plants siting

    International Nuclear Information System (INIS)

    Gomez, H.R.; Maggio, G.E.; Tripoli, C.R.

    1983-01-01

    The atucha nuclear power plants are located on the right shore of the Parana de las Palmas river in the entire transition between a fluvial regime and other of tides. Since the disponibility of cooling water is one of the factors to take into account when choosing the nuclear power plant site, it is essential to perform a probabilistic study of extreme hydrometric values. Deterministic and historical analysis should be done to complete the studies already mentioned, in order to establish the values of probable maximum floods. From the application of these methods, it is concluded that the site of the Atucha nuclear power plants constitutes a hydrometric singularity, so that, an optimization has been obtained from that point of view. (Author) [es

  18. Model calculations of the influence of population distribution on the siting of nuclear power plants

    International Nuclear Information System (INIS)

    Nielsen, F.; Walmod-Larsen, O.

    1984-02-01

    This report was prepared for a working group established in April 1981 by the Danish Environmental Protection Agency with the task of investigating siting problems of nuclear power stations in Denmark. The purpose of the working group was to study the influence of the population density around a site on nuclear power safety. The importance of emergency planning should be studied as well. In this model study two specific accident sequences were simulated on a 1000 MWe nuclear power plant. The plant was assumed to be placed in the center of two different model population distributions. The concequences for the two population distributions from the two accidents were calculated for the most frequent weather conditions. Doses to individuals were calculated for the bone marrow, lungs, gastrointestinal tract, thyroidea and for the whole body. The collective whole body doses were also calculated for the two populations considered. (author)

  19. A preliminary analysis of the risk of transporting nuclear waste to potential candidate commercial repository sites

    International Nuclear Information System (INIS)

    Madsen, M.M.

    1984-01-01

    In accordance with the provisions of the Nuclear Waste Policy Act of 1982, environmental assessments for potential candidate sites are required to provide a basis for selection of the first site for disposal of commercial radioactive waste in deep geologic repositories. A preliminary analysis of the impacts of transportation for each of the five potential sites will be described. Transportation was assumed to be entirely by truck or entirely by rail in order to obtain bounding impacts. This paper presents both radiological and nonradiological risks for the once-through fuel cycle

  20. Applications of SLAR in nuclear power plant siting: A case history

    Science.gov (United States)

    Siegal, B. S.

    1980-01-01

    Over 10,000 square km of side-looking airborne radar (SLAR) imagery was obtained and analyzed for the siting of the first nuclear power plant in the Republic of the Philippines. The imagery was obtained using the Motorola APS/AN-94D (X-band) real aperture system as part of an overall remote sensing program to site and evaluate potential site regions. Analysis of SLAR images, in conjunction with LANDSAT, color, black and white, and thermal infrared images, provided basic information on structure, relative geochronology, stratigraphy, geomorphology, and ground water, which facilitated field operations and data synthesis.

  1. Numerical Simulation of Groundwater Flow at Kori Nuclear Power Plant Site

    International Nuclear Information System (INIS)

    Sohn, Wook; Sohn, Soon Whan; Chon, Chul Min; Kim, Kue Youn

    2010-01-01

    Recently, the understanding of hydrogeological characteristics of nuclear power sites is getting more importance with increasing public concerns over the environment since such understanding is essential for an environmentally friendly operation of plants. For such understanding, the prediction of groundwater flow pattern onsite plays the most critical role since it is the most dynamic of the factors to be considered. In this study, the groundwater flow at the Kori Plant 1 site has been simulated numerically with aim of providing fundamental information needed for improving the understanding of the hydrogeological characteristics of the site

  2. Development of the on-site power supply in German nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Simon, M. [Gesellschaft fuer Reaktorsicherheit - GRS mbH, Schwertnergasse 1, D-5000 Koeln 1, Cologne (Germany)

    1986-02-15

    The design of the on-site power supply is different in German Nuclear Power Plants, depending on age and size of the plant. The cause for this is the evolution of the safety requirements. The general development of the design of safety Systems, which resulted in a strict separation of redundant trains is also reflected in the design of the emergency power system and even the complete on-site power supply System. This will be demonstrated by different examples. The advantages of this design with respect to the availability of on-site power will be explained and verified by means of operating experience. (author)

  3. [The assessment of radionuclide contamination and toxicity of soils sampled from "experimental field" site of Semipalatinsk nuclear test site].

    Science.gov (United States)

    Evseeva, T I; Maĭstrenko, T A; Belykh, E S; Geras'kin, S A; Kriazheva, E Iu

    2009-01-01

    Large-scale maps (1:25000) of soil contamination with radionuclides, lateral distribution of 137Cs, 90Sr, Fe and Mn water-soluble compounds and soil toxicity in "Experimental field" site of Semipalatinsk nuclear test site were charted. At present soils from studied site (4 km2) according to basic sanitary standards of radiation safety adopted in Russian Federation (OSPORB) do not attributed to radioactive wastes with respect to data on artificial radionuclide concentration, but they do in compliance with IAEA safety guide. The soils studied can not be released from regulatory control due to radioactive decay of 137Cs and 90Sr and accumulation-decay of 241Am up to 2106 year according to IAEA concept of exclusion, exemption and clearance. Data on bioassay "increase of Chlorella vulgaris Beijer biomass production in aqueous extract from soils" show that the largest part of soils from the studied site (74%) belongs to stimulating or insignificantly influencing on the algae reproduction due to water-soluble compounds effect. Toxic soils occupy 26% of the territory. The main factors effecting the algae reproduction in the aqueous extracts from soil are Fe concentration and 90Sr specific activity: 90Sr inhibits but Fe stimulates algae biomass production.

  4. Draft environmental assessment: reference repository location, Hanford Site, Washington. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified a reference repository location at the Hanford Site in Washington as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the reference repository location at the Hanford Site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received on the draft EA. The reference repository location at Hanford is located in the Columbia Plateau, one of five distinct geohydrologic settings that are being considered for the first repository. On the basis of the evaluations reported in this draft EA, the DOE has found that the reference repository location at Hanford is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the reference repository location at Hanford as one of five sites suitable for characterization. Furthermore, having performed a comparative evaluation of the five sites proposed for nomination, the DOE has determined that the reference repository location at Hanford is one of three sites preferred for site characterization

  5. The site of a nuclear power plant and environmental safety; Ydinvoimalaitoksen sijaintipaikka ja ympaeristoen turvallisuus

    Energy Technology Data Exchange (ETDEWEB)

    Rossi, J. [VTT Energy, Espoo (Finland)

    2001-11-01

    The purpose of this report is to give the reader a general view of the things associated with the site of a nuclear power plant. In this context the effect of a nuclear power plant and site on environmental safety is considered. Planning, construction and operating a nuclear power plant require several judgements and licenses based on different laws. The location of the planned nuclear facility project and environmental conditions contribute in great detail to the compliance arguments of permits. At first the environmental impacts of the siting project and its alternatives shall be investigated in the Environmental Impact Assessment procedure. Then the decision in principle according to the Nuclear Energy Act can be applied from the Council of State, the decision shall further be confirmed by Parliament. When the decision in principle is considered the overall good of society shall be assessed by means of considering i.a. site alternatives and safety. The safety related basic principle is that operation of a nuclear power plant may not cause danger to the environment, public or property. After the affirmative principle approval the construction license and later on the operation license can be applied from the Council of State, these licenses need to be supported i.a. by building and environmental licenses of separate authorities. Also some international contracts concern realisation of a nuclear power plant siting. The nuclear power plant site shall be suitable for the needs of the electricity production and the transmission system and it shall be technically appropriate for building and operation of a power plant. The site shall be safe enough on the other hand from the view of external events threatening the power plant - although one can be partly prepared for these things in the design of the plant - and on the other hand from the point of public safety. Requirements for the safety of the site are directed in the decision of the Council of State's general

  6. Seismological studies carried out by the CEA in connection with the safety of nuclear sites

    International Nuclear Information System (INIS)

    Barbreau, A.; Ferrieux, H.; Mohammadioun, B.

    1975-01-01

    In order to evaluate the seismic risk at nuclear sites, the Department of Nuclear Safety of the French Atomic Energy Commission (CEA) has been conducting a programme of seismological studies for several years past. This programme is aimed at acquiring a better knowledge of seismic phenomena, in particular the spectral distribution of the energy of earthquakes, considered to be the only correct approach to the problem of earthquake protection, as well as a better knowledge of the seismic activity of the areas surrounding nuclear sites. The authors propose defining the design spectrum of the site on the basis of the probable energy at the source, the distance from the epicentre and the transfer function of the geological formations. The need - for the purpose of defining this spectrum - to acquire data on the characteristics of French earthquakes and on regional seismicity led the Department of Nuclear Safety to set up a network of seismic stations. It now has an observatory at the Cadarache Nuclear Research Centre and mobile stations with automatic magnetic recording for studying aftershock sequences and the activity of faults in the vicinity of nuclear sites, and for making the measurements necessary to calculate the transfer functions. With this equipment it was possible to record six aftershocks of the Oleron earthquake on 7 September 1972 close to the epicentre, and to calculate the spectra therefrom. The latter contained a lot of high frequencies, which is in agreement with the data obtained from other sources for earthquakes of low energy. The synthetic spectra calculated on the basis of one magnitude and one distance are in good agreement with the spectra obtained experimentally

  7. Analysis of the portfolio of sites to characterize for selecting a nuclear repository

    International Nuclear Information System (INIS)

    Keeney, R.L.

    1987-01-01

    The US Department of Energy has selected three sites, from five nominated, to characterize for a nuclear repository to permanently dispose of nuclear waste. This decision was made without the benefit of an analysis of this portfolio problem. This paper analyzes different portfolios of three sites for simultaneous characterization and strategies for sequential characterization. Characterization of each site, which involves significant subsurface excavation, is now estimated to cost $1 billion. Mainly because of the high characterization costs, sequential characterization strategies are identified which are the equivalent of $1.7-2.0 billion less expensive than the selected DOE simultaneous characterization of the three sites. If three sites are simultaneously characterized, one portfolio is estimated to be the equivalent of $100-400 million better than the selected DOE portfolio. Because of these potential savings and several other complicating factors that may influence the relative desirability of characterization strategies, a thorough analysis of characterization strategies that addresses the likelihood of finding disqualifying conditions during site characterization, uncertainties, and dependencies in forecast site repository costs, preclosure and postclosure health and safety impacts, potential delays of both sequential and simultaneous characterization strategies, and the environmental, socioeconomic, and health and safety impacts of characterization activities is recommended

  8. Assessment of hydrologic transport of radionuclides from the Rulison Underground Nuclear Test Site, Colorado

    International Nuclear Information System (INIS)

    Earman, S.; Chapman, J.; Andricevic, R.

    1996-09-01

    The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Rulison site in west-central Colorado was the location of an underground detonation of a 40-kiloton nuclear device in 1969. The test took place 2,568 m below ground surface in the Mesaverde Formation. Though located below the regional water table, none of the bedrock formations at the site yielded water during hydraulic tests, indicating extremely low permeability conditions. The scenario evaluated was the migration of radionuclides from the blast-created cavity through the Mesaverde Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. The transport calculations are most sensitive to changes in the mean groundwater velocity and the correlation scale of hydraulic conductivity, with transport of strontium and cesium also sensitive to the sorption coefficient

  9. Siting of repositories for high level nuclear waste geological and institutional issues

    International Nuclear Information System (INIS)

    Ahagen, H.

    1993-01-01

    Two studies have been conducted in Sweden under contract from SKN-National Board for Spent Nuclear Fuel. The responsibilities of SKN has been transferred to SKI as of July 1, 1992. The first study is related to a compilation of experience and lessons learned from siting of nuclear waste repositories and other controversial facilities in seven countries. The second study is aimed at compiling examples of the state of knowledge related to the regional geological information with relevance to siting of a repository in Sweden. This paper is drawing the general combined conclusions from both these studies. The first study reviewed programs for siting of nuclear and hazardous waste disposal facilities in Canada, Finland, France, Sweden, Switzerland, United Kingdom and USA. The main topics reviewed are related to a/ The use of technical screening, b/ Legal framework and local veto, c/ Public involvement, d/ Interim storage and schedule flexibility, e/ Sequential vs. parallel characterization. The second study focused on the regional geological information available for Sweden and if this information allows for a ''grouping'' of tectonic regions in Sweden with significant differences in history and characteristics. Factors studied as potentially important for siting are bedrock properties, mineralizations, ground water conditions and available volume for a repository. The experience gained from these studies is aimed to be used as background information in the review of the program conducted for the Swedish nuclear utilities by SKB. SKB will according to current plans initiate siting for a repository for spent nuclear fuel in Sweden during 1993. (author). 2 refs

  10. Assessment of national systems for obtaining local acceptance of nuclear waste management siting activities

    International Nuclear Information System (INIS)

    Paige, H.W.; Owens, J.E.

    1984-01-01

    On behalf of the United States Department of Energy (DOE), International Energy Associates Limited (IEAL) of Washington, D.C. has conducted surveys and analyses of fourteen countries' plans and approaches for dealing with the problems of obtaining local siting acceptance for nuclear waste management facilities. It was determined that the following elements of the formal systems generally facilitate and/or expedite waste management siting decisions: (1) a clear-cut pro-nuclear power position on the part of the government; (2) a willingness on the part of the central government to exert (with prudence and restraint) its pre-emptive rights in nuclear matters; (3) political structures in which the heads of regional or provincial governments are appointed by the central government; (4) national laws that link reactor licensing with a detailed plan for waste management; (5) an established and stable policy with regard to reprocessing. In contrast, it was determined that the following elements of the formal system generally hinder waste management siting activities: (1) historically strong local land used veto laws; (2) the use of national referenda for making nuclear decisions; (3) requirements for public hearings. The informal approaches fall into the following five categories: (1) political: e.g. assertion of will by political leaders, activities to enlist support of local politicians, activities to broaden involvement in decision-making; (2) economic: e.g. emphasis on normal benefits, provision for additional economic benefits; (3) siting: e.g. at or near existing nuclear facilities, on government or utility property, at multiple locations to spread the political burden; (4) timing: e.g. decoupling drilling activities from ultimate repository site decision, deliberate deferral to (long-range) future; (5) education: e.g. creation of special government programmes, enlisting of media support

  11. Childhood leukaemia and non-Hodgkin's lymphoma near large rural construction sites, with a comparison with Sellafield nuclear site

    International Nuclear Information System (INIS)

    Kinlen, L.J.; Dickson, M.; Stiller, C.A.

    1995-01-01

    The objective was to determine whether population mixing produced by large, non-nuclear construction projects in rural areas is associated with an increase in childhood leukaemia and non-Hodgkin's lymphoma. A study was undertaken of the incidence of leukaemia and non-Hodgkin's lymphoma among children living near large construction projects in Britain since 1945, situated more than 20 km from a population centre, involving a workforce of more than 1000, and built over three or more calendar years. A 37% excess of leukaemia and non-Hodgkin's lymphoma at 0-14 years of age was recorded during construction and the following calendar year. The excesses were greater at times when construction workers and operating staff overlapped (72%), particularly in areas of relatively high social class. For several sites the excesses were similar to or greater than that near the nuclear site of Sellafield (67%), which is distinctive in its large workforce with many construction workers. Seascale, near Sellafield, with a ninefold increase had an unusually high proportion of residents in social class I. The findings support the infection hypothesis and reinforce the view that the excess of childhood leukaemia and non-Hodgkin's lymphoma near Sellafield has a similar explanation. (author)

  12. Enhancing nuclear power plant safety via on-site mental fatigue management

    Directory of Open Access Journals (Sweden)

    Tsai Ming-Kuan

    2017-01-01

    Full Text Available Nuclear incidents and accidents have occurred at various nuclear power plants. Since some of these incidents and accidents caused by human errors might be preventable, numerous researchers argue that fatigue management for on-site workers is the key, especially for mental fatigue. Thus, this study proposes an approach consisting of two mechanisms. A fatigue monitor could identify the mentally fatigued workers by detecting their brain wave rhythms through a brain-computer interface. For such workers, a fatigue alert would awaken them. If the status of the mentally fatigued workers becomes worse, based on a positioning technique (i.e., wireless networks, this mechanism would alert the nearby workers and managers to deal with this condition. The test results indicate that the proposed approach enhanced the capacity to examine the mentally fatigued workers, ensured the accuracy in locating these workers, and avoided possible nuclear incidents. This study is a useful reference for similar applications in the nuclear industry.

  13. Cytogenetic biomonitoring carried out in a village (Dolon) adjacent to the Semipalatinsk nuclear weapon test site.

    Science.gov (United States)

    Testa, A; Stronati, L; Ranaldi, R; Spanò, M; Steinhäusler, F; Gastberger, M; Hubmer, A; Ptitskaya, L; Akhmetov, M

    2001-06-01

    The Semipalatinsk region (Kazakhstan Republic) has been affected by extensive radioactive contamination due to more than 450 nuclear tests of which almost 100 were exploded in the atmosphere. The present results refer to cytogenetic assessments in a study cohort of the population of Dolon, a settlement located on the NE boundary of the nuclear weapon test site, which was exposed to elevated doses of ionising radiation primarily due to the first Soviet nuclear test in 1949. Conventional cytogenetic analyses were carried out on 21 blood samples from individuals (more than 50 years old) living in Dolon since the very beginning of nuclear testing. A matched control group included 20 individuals living in non-contaminated areas. Higher frequencies of chromosome aberrations were found in the Dolon cohort compared to the control group, even though they remain within the range of the background levels reported for large normal human population studies on elderly individuals.

  14. Integrating geographical information and augmented reality techniques for mobile escape guidelines on nuclear accident sites

    International Nuclear Information System (INIS)

    Tsai, Ming-Kuan; Lee, Yung-Ching; Lu, Chung-Hsin; Chen, Mei-Hsin; Chou, Tien-Yin; Yau, Nie-Jia

    2012-01-01

    During nuclear accidents, when radioactive materials spread into the environment, the people in the affected areas should evacuate immediately. However, few information systems are available regarding escape guidelines for nuclear accidents. Therefore, this study constructs escape guidelines on mobile phones. This application is called Mobile Escape Guidelines (MEG) and adopts two techniques. One technique is the geographical information that offers multiple representations; the other is the augmented reality that provides semi-realistic information services. When this study tested the mobile escape guidelines, the results showed that this application was capable of identifying the correct locations of users, showing the escape routes, filtering geographical layers, and rapidly generating the relief reports. Users could evacuate from nuclear accident sites easily, even without relief personnel, since using slim devices to access the mobile escape guidelines is convenient. Overall, this study is a useful reference for a nuclear accident emergency response.

  15. Integrating geographical information and augmented reality techniques for mobile escape guidelines on nuclear accident sites.

    Science.gov (United States)

    Tsai, Ming-Kuan; Lee, Yung-Ching; Lu, Chung-Hsin; Chen, Mei-Hsin; Chou, Tien-Yin; Yau, Nie-Jia

    2012-07-01

    During nuclear accidents, when radioactive materials spread into the environment, the people in the affected areas should evacuate immediately. However, few information systems are available regarding escape guidelines for nuclear accidents. Therefore, this study constructs escape guidelines on mobile phones. This application is called Mobile Escape Guidelines (MEG) and adopts two techniques. One technique is the geographical information that offers multiple representations; the other is the augmented reality that provides semi-realistic information services. When this study tested the mobile escape guidelines, the results showed that this application was capable of identifying the correct locations of users, showing the escape routes, filtering geographical layers, and rapidly generating the relief reports. Users could evacuate from nuclear accident sites easily, even without relief personnel, since using slim devices to access the mobile escape guidelines is convenient. Overall, this study is a useful reference for a nuclear accident emergency response. Copyright © 2012 Elsevier Ltd. All rights reserved.

  16. On-site inspection for the radionuclide observables of an underground nuclear explosion

    International Nuclear Information System (INIS)

    Burnett, J.L.

    2015-01-01

    Under the Comprehensive Nuclear-Test-Ban Treaty an on-site inspection (OSI) may be undertaken to identify signatures from a potential nuclear explosion. This includes the measurement of 17 particulate radionuclides ( 95 Zr, 95 Nb, 99 Mo, 99m Tc, 103 Ru, 106 Rh, 132 Te, 131 I, 132 I, 134 Cs, 137 Cs, 140 Ba, 140 La, 141 Ce, 144 Ce, 144 Pr, 147 Nd). This research provides an assessment of the potential to detect these radionuclides during an OSI within 1 week to 2 years after a nuclear explosion at two locations. A model has been developed that simulates the underground detonation of a 1 kT 235 U nuclear weapon with 1 % venting. This indicates a requirement to minimise the time since detonation with accurate determination of the test location. (author)

  17. UK safety and standards for radioactive waste management and decommissioning on nuclear licensed sites

    International Nuclear Information System (INIS)

    Mason, D.J.

    2001-01-01

    This paper discusses the regulation of radioactive waste and decommissioning in the United Kingdom and identifies the factors considered by HM Nuclear Installations Inspectorate in examining the adequacy arrangements for their management on nuclear licensed sites. The principal requirements are for decommissioning to be undertaken as soon as reasonably practicable and that radioactive wastes should be minimised, disposed of or contained and controlled by storage in a passively safe form. However, these requirements have to be considered in the context of major organisational changes in the UK nuclear industry and the non-availability of disposal routes for some decommissioning wastes. The legislative framework used to regulate decommissioning of nuclear facilities in the UK is described. Reference is made to radioactive waste and decommissioning strategies, quinquennial reviews criteria for delicensing and the forthcoming Environmental Impact Assessment Regulations. (author)

  18. Methodology to evaluate the site standard seismic motion to a nuclear facility

    International Nuclear Information System (INIS)

    Soares, W.A.

    1983-01-01

    For the seismic design of nuclear facilities, the input motion is normally defined by the predicted maximum ground horizontal acceleration and the free field ground response spectrum. This spectrum is computed on the basis of records of strong motion earthquakes. The pair maximum acceleration-response spectrum is called the site standard seismic motion. An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic principles of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; available methodologies and recommended procedures to evaluate the site standard seismic motion. (Author) [pt

  19. Pre operational background radiation monitoring around Kudankulam Nuclear Power Project site - a decade long experience

    International Nuclear Information System (INIS)

    Vijayakumar, B.; George, Thomas; Sundara Rajan, P.; Selvi, B.S.; Balamurugan, M.; Pandit, G.G.; Ravi, P.M.; Tripathi, R.M.

    2014-01-01

    Pre-operational environmental background radiation monitoring around nuclear power plants is very important to understand baseline values existing in the site and also to identify any hot spots of naturally occurring high background radiation areas and their sources. These baseline measurements will act as a benchmark for future comparison after the reactors go into operation. The radiation measurements are continued during the operational phase of the plant and the results are compared to see whether there is any impact of the operation of the plant on the environment. A comprehensive background radiation monitoring plan has been in vogue at site from 2004 to meet this objective. This paper describes the different monitoring strategies adopted around Kudankulam Nuclear Power Project site and throws light on the pre operational background radiation levels in the environment

  20. Siting of nuclear desalination plants in Saudi Arabia: A seismic study

    International Nuclear Information System (INIS)

    Aljohani, M.S.; Abdul-Fattah, A.F.; Almarshad, A.I.

    2005-01-01

    This paper presents the selection criteria generally and seismic criteria specifically to select a suitable site in Saudi Arabia for a nuclear desalination plant. These criteria include geological, meteorological, cooling water supply discharge, transport infrastructure, population, electric grid, water network capacity, environmental impact and airport movement. The seismicity of the Arabian peninsula for the locations of seismic activity along the Red Sea and the Arabian Gulf coastlines from 1973 to 2000 was studied carefully. This study included towns and locations along the east and west coastlines and their distances from the seismic event site. The results showed that Rabigh City along the west coast of Saudi Arabia is a good site to build a nuclear desalination plant. This is because of the following reasons: good seismic stability; good weather statistics; no flooding; mild wave conditions; good supply and discharge; good transportation infrastructure; low population area; very close to the huge electric grid. (author)

  1. Factors of site selection for nuclear power plants in selected industrial states

    International Nuclear Information System (INIS)

    Hoffmann, L.; Obermair, G.; Ringler, W.; Romahn, B.; Sanders, H.

    1978-01-01

    The range of the tasks within the project consists of working out an optimal catalogue of criteria for the site selection for nuclear power plants; establishing a structured documentation system for the criteria and licensing procedures used by selected industrial countries when selecting sites for nuclear power plants; analyzing and evaluating the documented material with the aim of supplying the basis for decisions concerning land use. The tasks are being realized within a technological ring of data (for the period until 1990, reactor types, cooling, power-heat coupling, special sites, block sizes, local concentration) and a set politico-economical ring of data for the following countries: F.R. Germany, Belgium, Switzerland, Great Britain, Sweden, Denmark, Austria, France, Netherlands, USA, Japan, Yougoslavia. (HP) [de

  2. The Role of Tectonic and Seismicity in Siting of Nuclear Power Plant

    International Nuclear Information System (INIS)

    Abdel Aziz, M.A.H.

    2008-01-01

    The site selection for the a nuclear power plant (NPP) is controlled by many criteria. One of the most important criterion is the tectonic and seismicity of the site and its surroundings. Since, it is preferable the site in concern is characterized by low tectonic and low seismicity to avoid the damage effects associated with the occurrence of destructive earthquakes. The investigation of the tectonic and seismicity maps of egypt has been carried out to candidate potential areas or sites for nuclear power plant installation from seismicity point of view. Also, the design basis ground motion in terms of peak ground acceleration and response spectra of some of the potential sites are defined through the conduct of probabilistic seismic hazard analysis The study revealed that although there is no criterion to exclude areas of high tectonic and high seismicity as potential sites for nuclear power plant installation but, it is preferable avoiding such areas. This is attributed to the critical seismic curve that characterizes such areas and is required high seismic design levels to resist the destructive vibratory ground motion associated with the expected earthquake. Consequently, the required high seismic design levels will have a negative impact on the economic cost of the facility compared with that built in low and moderate seismic areas. Hence, areas like the gulf of suez, the northern part of the Red Sea and the southern part of Sinai Peninsula should be avoided as potential sites for NPP from the tectonic and seismicity point of view. On the other hand, areas like Nile delta and its valley, the Northern and Southern parts of Western desert and the central and southern parts of the Eastern Desert should be candidate as potential sites on condition, the other criteria meet the IAEA's regulations. Also, the seismic hazard curve of the Northwest littoral zone reflects low design basis ground motion values compared with the Nile delta region

  3. Radioactive residues at nuclear sites in the United States of America

    International Nuclear Information System (INIS)

    Fiore, J.; Rampertaap, A.; Greeves, J.; MacKinney, J.; Raguso, M.; Selstrom, J.

    2000-01-01

    The United States of America has a large number of sites where radioactive materials have been mined, processed, produced, or used. Upon completion of activities at these sites, some will be cleaned up completely and released for unrestricted future use. However, at other sites, contamination will remain on the site following cleanup, requiring long term institutional controls. Depending on the purpose or the activity conducted at a specific site, these locations are generally under the jurisdiction of a federal agency: the United States Department of Energy, the United States Nuclear Regulatory Commission, the United States Environmental Protection Agency, or the United States Department of Defense. However, under certain conditions, the Nuclear Regulatory Commission relinquishes regulatory authority to individual states to regulate the commercial uses of radioactive materials (except for nuclear reactors), so some locations with radioactive materials are under the jurisdiction of individual states. Other sites with naturally occurring radioactive contamination may also be controlled by individual states. One or two sites under the jurisdiction of each agency are discussed where radioactive materials either existed in the past or exist today, and the source of contamination, the anticipated end state, and the process by which the responsible agency did or will conduct cleanup and site closure are described. Several issues are reviewed that must be addressed in order to design and implement remediations that will ensure long term protection for the environment and future inhabitants. The role of citizens in environmental cleanups is examined, and how institutional controls may be applied to ensure long term protection of remediations that leave some contaminants in place. (author)

  4. Nuclear Site Remediation and Restoration during Decommissioning of Nuclear Installations. A Report by the NEA Co-operative Programme on Decommissioning

    International Nuclear Information System (INIS)

    Orr, Peter; Mitchell, Nick; Mobbs, Shelly; Bennest, Terry; Abu-Eid, Rateb-Boby; Berton, Marie-Anne; Dehaye, Catherine Ollivier; Pellenz, Gilles; Cruikshank, Julian; Diaz Arocas, Paloma; Garcia Tapias, Ester; Hess, Norbert; Hong, Sam-Bung; Miller, Susan; Monken-Fernandes, Horst; ); Morse, John; Nitzsche, Olaf; Ooms, Bart; Osimani, Celso; Stuart Walker

    2014-01-01

    Decommissioning of nuclear facilities and related remedial actions are currently being undertaken around the world to enable sites or parts of sites to be reused for other purposes. Remediation has generally been considered as the last step in a sequence of decommissioning steps, but the values of prevention, long-term planning and parallel remediation are increasingly being recognised as important steps in the process. This report, prepared by the Task Group on Nuclear Site Restoration of the NEA Co-operative Programme on Decommissioning, highlights lessons learnt from remediation experiences of NEA member countries that may be particularly helpful to practitioners of nuclear site remediation, regulators and site operators. It provides observations and recommendations to consider in the development of strategies and plans for efficient nuclear site remediation that ensures protection of workers and the environment. (authors)

  5. Implications for reconstruction of the relationship between nuclear industry and siting areas in Japan. Lessons learnt from the cases of Site Stakeholder Groups in United Kingdom

    International Nuclear Information System (INIS)

    Sugawara, Shin-etsu

    2014-01-01

    After the Fukushima nuclear accident, the Japanese nuclear community began to recognize the need for establishing local stakeholder meetings in nuclear siting areas for information sharing and communication in reference to the experiences in European countries. This report shows the patterns of institutional design and the management style of stakeholder meetings in UK based on the interview survey, including SSGs (Site Stakeholder Groups) around the NDA (Nuclear Decommissioning Authority) sites and LCLCs (Local Community Liaison Councils) around the nuclear power stations in operation. SSGs have developed a local-oriented management style under the leadership of independent chairs elected from local stakeholders, in contrast to LCLCs where the operator of nuclear energy facilities has the initiative of management. SSGs play critical roles in improving quality of decision-making and enhancing its legitimacy through providing forums for local stakeholder engagement in the process of NDA's consultations and BPEO (Best Practicable Environmental Option) implementation. Based on these insights from UK's cases, the author suggests the following remedies for the relationship between the nuclear industry and siting areas in Japan: (1) introducing evaluation systems of stakeholder engagement linked to the insurance rates of nuclear energy liability, and (2) modifying the nuclear safety agreements into risk management principles. (author)

  6. Environmental planning and the siting of nuclear facilities: the integration of water, air, coastal, and comprehensive planning into the nuclear siting process. Improving regulatory effectiveness in federal/state siting actions

    International Nuclear Information System (INIS)

    Noble, J.B.; Epting, J.T.; Blumm, M.C.; Ackerman, S.; Laist, D.W.

    1977-02-01

    The National Environmental Policy Act, the Coastal Zone Management Act, the Federal Water Pollution Control Act, the Clean Air Act Amendments, and the Housing and Urban 701 Comprehensive Planning Assistance Program are discussed in relation to the planning and siting of nuclear facilities

  7. Nuclear power plant attempts in Turkey and the first licensed site

    International Nuclear Information System (INIS)

    Bektur, Y.; Bezdegumeli, U.

    2004-01-01

    In this paper, detailed information regarding Turkey's past attempts for the construction of a nuclear power plant (NPP) and site survey studies conducted for this plant is given. Also, some important characteristics of the first licensed site, namely Akkuyu, are summarized. There were four attempts made for the construction of an NPP in the past. However, all of them failed due to technical, economical and/or some other reasons. Akkuyu site has been selected among around 25 candidate sites for the reasons that bulky materials can be transported there by sea; it is located near the major electricity demand centers; soil-structure interaction and slab stability are suitable for the construction of an NPP; its surrounding is one of the most sparsely populated areas of Turkey; and it is seismically the most stable region in earthquake-prone Turkey, e.g. Turkish Electricity Authority (TEK) was granted a site license for the Akkuyu in 1976. (author)

  8. Decommissioning strategy and schedule for a multiple reactor nuclear power plant site

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Deiglys Borges; Moreira, Joao M.L.; Maiorino, Jose Rubens, E-mail: deiglys.monteiro@ufabc.edu.br, E-mail: joao.moreira@ufabc.edu.br, E-mail: joserubens.maiorino@ufabc.edu.br [Universidade Federal do ABC (CECS/UFABC), Santo Andre, SP (Brazil). Centro de Engenharia, Modelagem e Ciencias Aplicadas

    2015-07-01

    The decommissioning is an important part of every Nuclear Power Plant life cycle gaining importance when there are more than one plant at the same site due to interactions that can arise from the operational ones and a decommissioning plant. In order to prevent undesirable problems, a suitable strategy and a very rigorous schedule should implemented and carried. In this way, decommissioning tasks such as fully decontamination and dismantling of activated and contaminated systems, rooms and structures could be delayed, posing as an interesting option to multiple reactor sites. The present work aims to purpose a strategy and a schedule for the decommissioning of a multiple reactor site highlighting the benefits of delay operational tasks and constructs some auxiliary services in the site during the stand by period of the shutdown plants. As a case study, will be presented a three-reactor site which the decommissioning process actually is in planning stage and that should start in the next decade. (author)

  9. Decommissioning strategy and schedule for a multiple reactor nuclear power plant site

    International Nuclear Information System (INIS)

    Monteiro, Deiglys Borges; Moreira, Joao M.L.; Maiorino, Jose Rubens

    2015-01-01

    The decommissioning is an important part of every Nuclear Power Plant life cycle gaining importance when there are more than one plant at the same site due to interactions that can arise from the operational ones and a decommissioning plant. In order to prevent undesirable problems, a suitable strategy and a very rigorous schedule should implemented and carried. In this way, decommissioning tasks such as fully decontamination and dismantling of activated and contaminated systems, rooms and structures could be delayed, posing as an interesting option to multiple reactor sites. The present work aims to purpose a strategy and a schedule for the decommissioning of a multiple reactor site highlighting the benefits of delay operational tasks and constructs some auxiliary services in the site during the stand by period of the shutdown plants. As a case study, will be presented a three-reactor site which the decommissioning process actually is in planning stage and that should start in the next decade. (author)

  10. Radiological effluents released from nuclear rocket and ramjet engine tests at the Nevada Test Site 1959 through 1969: Fact Book

    Energy Technology Data Exchange (ETDEWEB)

    Friesen, H.N.

    1995-06-01

    Nuclear rocket and ramjet engine tests were conducted on the Nevada Test Site (NTS) in Area 25 and Area 26, about 80 miles northwest of Las Vegas, Nevada, from July 1959 through September 1969. This document presents a brief history of the nuclear rocket engine tests, information on the off-site radiological monitoring, and descriptions of the tests.

  11. Local negotiation on compensation siting of the spent nuclear fuel repository in Finland

    International Nuclear Information System (INIS)

    Kojo, Matti

    2007-01-01

    The aim of the paper is to analyse the local negotiation process between the Municipality of Eurajoki and the nuclear power company Teollisuuden Voima (TVO) and the nuclear waste management company Posiva Oy. The aim of the negotiations was to find an acceptable form of compensation for siting a spent nuclear fuel repository in Olkiluoto, Finland. The paper includes background information on the siting process in Finland, the local political setting in the Municipality of Eurajoki and a description of the negotiation process. The analysis of the negotiations on compensation is important for better understanding the progress of the Finnish siting process. The paper describes the picture of the contest to host the spent nuclear fuel repository. It also provides more information on the relationship between the Municipality of Eurajoki and the power company TVO. The negotiations on compensation and the roles of various players in the negotiations have not been studied in detail because the minutes of the Vuojoki liaison group were not available before the decision of the Supreme Administrative Court in May 2006. (author)

  12. Measurements of Argon-39 at the U20az underground nuclear explosion site.

    Science.gov (United States)

    McIntyre, J I; Aalseth, C E; Alexander, T R; Back, H O; Bellgraph, B J; Bowyer, T W; Chipman, V; Cooper, M W; Day, A R; Drellack, S; Foxe, M P; Fritz, B G; Hayes, J C; Humble, P; Keillor, M E; Kirkham, R R; Krogstad, E J; Lowrey, J D; Mace, E K; Mayer, M F; Milbrath, B D; Misner, A; Morley, S M; Panisko, M E; Olsen, K B; Ripplinger, M D; Seifert, A; Suarez, R

    2017-11-01

    Pacific Northwest National Laboratory reports on the detection of 39 Ar at the location of an underground nuclear explosion on the Nevada Nuclear Security Site. The presence of 39 Ar was not anticipated at the outset of the experimental campaign but results from this work demonstrated that it is present, along with 37 Ar and 85 Kr in the subsurface at the site of an underground nuclear explosion. Our analysis showed that by using state-of-the-art technology optimized for radioargon measurements, it was difficult to distinguish 39 Ar from the fission product 85 Kr. Proportional counters are currently used for high-sensitivity measurement of 37 Ar and 39 Ar. Physical and chemical separation processes are used to separate argon from air or soil gas, yielding pure argon with contaminant gases reduced to the parts-per-million level or below. However, even with purification at these levels, the beta decay signature of 85 Kr can be mistaken for that of 39 Ar, and the presence of either isotope increases the measurement background level for the measurement of 37 Ar. Measured values for the 39 Ar measured at the site ranged from 36,000 milli- Becquerel/standard-cubic-meter-of-air (mBq/SCM) for shallow bore holes to 997,000 mBq/SCM from the rubble chimney from the underground nuclear explosion. Published by Elsevier Ltd.

  13. Numerical Simulation of a Tracer Experiment at the Wolsong Nuclear Site

    International Nuclear Information System (INIS)

    Jeong, Hyojoon; Kim, Eunhan; Park, Misun; Jeong, Haesun; Hwang, Wontae; Han, Moonhee

    2014-01-01

    By comparing the concentration of a tracer measured under weather conditions that are disadvantageous to the dilution of radioactive materials released from the Wolsong Nuclear Power Plant, with the concentration of a tracer calculated using an air Dispersion model, it is possible to evaluate the characteristics of the air concentrations of radioactive materials estimated with an air Dispersion model, which can then be used in an environmental impact analysis of radioactive materials. Therefore, a field Dispersion experiment has been carried out to figure out the behavioral characteristics of the tracer under weather conditions that are disadvantageous to the dilution of radioactive materials released from the Wolsong Nuclear Power Plant site in Korea. In addition, through a comparison of the tracer concentrations estimated by the Gaussian plume model with measurements, this study checked the degree of conservative estimation for the Gaussian plume at the Wolsong nuclear site in Korea. A tracer Dispersion experiment using an SF 6 trace was implemented to determine the Dispersion characteristics of radioactive materials at the Wolsong Nuclear Power Plant site in Korea. Based on meteorological data and the emission rate of the tracers, this study estimated the tracer concentrations using a Gaussian plume model, and then compared it with the measurement to check the conservative estimation of the Gaussian plume model. The measured concentrations of the tracer tends to be lower than the concentrations estimated by the Gaussian plume model overall

  14. Minisatellite mutations and retrospective biodosimetry of population living close to the Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Lindholm, C.; Bersimbaev, R.I.; Dubrova, Y.E. EI KAUP; EI MAATA

    2003-01-01

    During the period between 1949 and 1989 nuclear weapon testing carried out at the Semipalatinsk Nuclear Test Site (STS) resulted in local fallout affecting the residents of Semipalatinsk, East Kazakhstan and Pavlodar districts of Kazakhstan and Altai region of Russia. The Semipalatinsk nuclear polygon in Kazakhstan has been the site for 470 nuclear tests, including 26 tests performed on the ground and 87 in the atmosphere. More than 1.5 million people living in the vicinity of the test site were repeatedly exposed to ionizing radiation. The paper reviews the study where the main objectives are: (1) to establish a biosample database of blood samples of families in three generations living close to the STS and control families in three generations from clean areas, (2) to determine the minisatellite mutation rates in the three generations of exposed people and the control families of the same ethinic origin living in non-contaminated areas, and (3) to determine the chromosomal translocation frequencies by FISH chromosome painting in the lymphocytes of the exposed and the control people in order to determine the radiation exposure. The aim of the study was to select the population living near to the STS and subjected to the greatest radiation exposure. Of particular interest was the first test of 29th of August 1949, as this was reported to have caused heavy fallout along a narrow trajectory extending north-east from Polygon, also covering parts of the Altai region of Russia and parts of Pavlodar and Karaganda regions in Kazakhstan

  15. Incidence of childhood leukemia around French nuclear sites between 1990 and 1998

    International Nuclear Information System (INIS)

    White-Koning, M.; Hemon, D.; Goubin, A.; Clavel, J.; Laurier, D.; Tirmarche, M.; Jougla, E.

    2006-01-01

    The works presented here constitute the first systematic study of the incidence of childhood leukemia around the whole of French nuclear facilities. Globally, the incidence of childhood leukemia does not diverge significantly of the expected incidence during the period 1990-1998. It does not show a decrease of S.I.R. (standardized incidence ratio) in function of the distance from child's home to the nuclear site whatever be the age. This study represents the first analysis of the incidence of leukemia focusing on 29 French nuclear sites, including the whole of the 19 C.N.P.E. ( nuclear power plants that produce electric power), and is based on incidence data rather than mortality. The period, the age groups and the studied area have been all chosen a priori, that gives a statistical validity to the results. The estimation of population at risk have been made with several different methods of interpolation in order to check the stability of estimations. The different methods of statistical analysis used have lead to extremely close results, reinforcing our confidence in the reliability of our estimations. The excess of leukemia incidence observed at Chinon and Civaux and the deficit observed at Bruyere/Saclay/Fontenay loose their statistical significance when the correction of Bonferroni is applied. So, the global analysis of the 29 sites and the analysis by site have not shown statistically significant difference between the numbers of observed and expected cases. The study of the 19 C.N.P.E. gave same results, even in taken into account their electric power or their year of service. The possibility of confounding factors has been excluded. The power of the study to detect excess incidence and a decrease of S.I.R. with distance from the site was examined under different alternative hypotheses through simulation methods. For values of S.I.R. near the site (0-5 km) between 1.5 and 2 and a risk of error of 5%, the power of the study is between 96% and 100% depending

  16. Volcanic Hazard Assessments for Nuclear Installations: Methods and Examples in Site Evaluation

    International Nuclear Information System (INIS)

    2016-07-01

    To provide guidance on the protection of nuclear installations against the effects of volcanoes, the IAEA published in 2012 IAEA Safety Standards Series No. SSG-21, Volcanic Hazards in Site Evaluation for Nuclear Installations. SSG-21 addresses hazards relating to volcanic phenomena, and provides recommendations and general guidance for evaluation of these hazards. Unlike seismic hazard assessments, models for volcanic hazard assessment have not undergone decades of review, evaluation and testing for suitability in evaluating hazards at proposed nuclear installations. Currently in volcanology, scientific developments and detailed methodologies to model volcanic phenomena are evolving rapidly.This publication provides information on detailed methodologies and examples in the application of volcanic hazard assessment to site evaluation for nuclear installations, thereby addressing the recommendations in SSG-21. Although SSG-21 develops a logical framework for conducting a volcanic hazard assessment, this publication demonstrates the practicability of evaluating the recommendations in SSG-21 through a systematic volcanic hazard assessment and examples from Member States. The results of this hazard assessment can be used to derive the appropriate design bases and operational considerations for specific nuclear installations

  17. Information report on nuclear safety and radiation protection of the Romans site - Issue 2014

    International Nuclear Information System (INIS)

    2015-06-01

    In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

  18. Economic evaluation of nuclear seawater desalination in an Algerian site: La Macta

    International Nuclear Information System (INIS)

    Belkaid, Abderrahmane; Amzert, Sid Ahmed; Arbaoui, Fahd; Bouaichaoui, Youcef

    2010-01-01

    As the needs for fresh water and electricity increases rapidly in Algeria, the Algerian authorities launched a study to assess the potentialities of the introduction of nuclear energy for the production of electricity and potable water. This study which started in 2007, is held under the framework of an IAEA Project untitled: 'techno-economic feasibility study of seawater desalination using nuclear energy' and its objective is to provide a document which will be used to support the government's decision to introduce the nuclear desalination in Algeria. To that end, one site has been selected to host nuclear desalination plant. This site is located in North West region of the country. In this study, we present the results achieved under this project and which corresponds to the economical evaluation of coupling several nuclear reactors: GT-MHR, PBMR, AP1000 and PWR900, with two desalination processes MED and RO. The results are compared with those obtained with fossil energy sources: Natural Gas Turbine and Natural Gas Combined Cycle. (author)

  19. Information report on nuclear safety and radiation protection of the Romans site - Issue 2012

    International Nuclear Information System (INIS)

    2013-06-01

    In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

  20. Information report on nuclear safety and radiation protection of the Romans site - Issue 2013

    International Nuclear Information System (INIS)

    2014-06-01

    In compliance with the French Code of the Environment, this annual document describes the arrangements regarding nuclear safety and radiation protection, reports incidents and accidents of nuclear safety and radiation protection which must be declared according to this Code and which occurred within the installation, as well as the actions undertaken to limit their development and the consequences for people health for the environment, describes the nature and results of measurements of radioactive and not radioactive releases by the installation in the environment, describes the nature and quantities of radioactive wastes which are warehoused on the installation site as well as measures to limit their volume and their impact on health and on the environment, notably in soils and waters. After a presentation of the AREVA plant located in Romans-sur-Isere which comprises two basic nuclear installations (INB) and where fuel assemblies are manufactured, the different parts of this report address the measures regarding nuclear safety and radiation protection, nuclear events according to the INES scale, the management of releases by the different installations of this site and the control of the environment, the management of radioactive wastes, and the actions undertaken regarding information and transparency. Recommendations of the CHSCT are also reported

  1. Nuclear archaeology: the influence of decommissioning on future reactor siting in the UK

    International Nuclear Information System (INIS)

    Openshaw, S.

    1990-01-01

    Whereas considerations of waste, cost, opinion, and the law are often abstract elements of nuclear power, the siting of generating stations produces concrete land use and aesthetic reminders of its presence. What will future generations find as a result of the nuclear era? Will the power plant sites be restored to greenfield conditions? When will this occur? How will such decisions affect surrounding land use and societal characteristics such as employment opportunities and quality of life? These and other questions revolve around the land use and siting links to decommissioning decisions. The two prime determinants of the land use legacy will be the timing of stage 3 dismantlement and the degree to which the sites can be restored to pre-use conditions. In this chapter it is argued that the sites are unlikely ever to be released for unrestricted use, but rather that the use and the visual impacts of the sites will increase over time, eventually becoming the objects which, perhaps, future archaeologists will study. (author)

  2. Seismic PSA method for multiple nuclear power plants in a site

    Energy Technology Data Exchange (ETDEWEB)

    Hakata, Tadakuni [Nuclear Safety Commission, Tokyo (Japan)

    2007-07-15

    The maximum number of nuclear power plants in a site is eight and about 50% of power plants are built in sites with three or more plants in the world. Such nuclear sites have potential risks of simultaneous multiple plant damages especially at external events. Seismic probabilistic safety assessment method (Level-1 PSA) for multi-unit sites with up to 9 units has been developed. The models include Fault-tree linked Monte Carlo computation, taking into consideration multivariate correlations of components and systems from partial to complete, inside and across units. The models were programmed as a computer program CORAL reef. Sample analysis and sensitivity studies were performed to verify the models and algorithms and to understand some of risk insights and risk metrics, such as site core damage frequency (CDF per site-year) for multiple reactor plants. This study will contribute to realistic state of art seismic PSA, taking consideration of multiple reactor power plants, and to enhancement of seismic safety. (author)

  3. Safety culture aspects of managing for safety. Experience of a large nuclear reprocessing site

    International Nuclear Information System (INIS)

    Rycraft, H.S.

    1996-01-01

    The Nuclear Industry is going through turbulent times both in terms of public acceptance and business issues. Safety is one area which impacts on whether the business is allowed to continue, and how an organisation organizes itself. The need to cut costs to make nuclear power a viable energy resource, has forced the nuclear utilities to review manning policies, and management style, and in particular how to maintain safety standards during a period of change, and ultimately support continuing improvement of standards. The shrinking workforce requires a new style of management, one that depends more on the people of the organisation taking responsibility for safety at all levels of the organisation. Not only personal safety but the safety of their colleagues, general public and the environment. The safety culture of an organisation is indivisible from the company culture, each aspect of a culture influences the whole and so the balance between business, safety and quality, has to be managed. BNFL provides a full fuel cycle service to nuclear power plants, and associated services to many national and international organisations. The following notes are taken from the work carried out in the company, and mostly at the Nuclear Reprocessing and Waste storage Site at Sellafield, based in the North West of England. Following the recent re-organisation, the site now employs 6200 people and has a further 1500 contractors working on construction activities on the site. Activities on the site range from remote handling to hands on tasks, involving highly active materials to low level waste. (author)

  4. The Contribution of Palaeoseismology to Seismic Hazard Assessment in Site Evaluation for Nuclear Installations

    International Nuclear Information System (INIS)

    2015-06-01

    IAEA Safety Standards Series No. SSG-9, Seismic Hazards in Site Evaluation for Nuclear Installations, published in 2010, covers all aspects of site evaluation relating to seismic hazards and recommends the use of prehistoric, historical and instrumental earthquake data in seismic hazard assessments. Prehistoric data on earthquakes cover a much longer period than do historical and instrumental data. However, gathering such data is generally difficult in most regions of the world, owing to an absence of human records. Prehistoric data on earthquakes can be obtained through the use of palaeoseismic techniques. This publication describes the current status and practices of palaeoseismology, in order to support Member States in meeting the recommendations of SSG-9 and in establishing the necessary earthquake related database for seismic hazard assessment and reassessment. At a donors’ meeting of the International Seismic Safety Centre Extrabudgetary Project in January 2011, it was suggested to develop detailed guidelines on seismic hazards. Soon after the meeting, the disastrous Great East Japan Earthquake and Tsunami of 11 March 2011 and the consequent accident at the Fukushima Daiichi nuclear power plant occurred. The importance of palaeoseismology for seismic hazard assessment in site evaluation was highlighted by the lessons learned from the Fukushima Daiichi nuclear power plant accident. However, no methodology for performing investigations using palaeoseismic techniques has so far been available in an IAEA publication. The detailed guidelines and practical tools provided here will be of value to nuclear power plant operating organizations, regulatory bodies, vendors, technical support organizations and researchers in the area of seismic hazard assessment in site evaluation for nuclear installations, and the information will be of importance in support of hazard assessments in the future

  5. Nuclear Energy Center Site Survey, 1975. Part I. Summary and conclusions

    International Nuclear Information System (INIS)

    1976-01-01

    The Nuclear Energy Center Site Survey is a study of a potential siting approach for projected power and fuel-cycle facilities that would cluster sizable groups of such facilities on a relatively small number of sites, as contrasted with current dispersed siting practices. Three basic types of nuclear energy centers (NECs) are considered: power-plant centers, involving ten to forty units of 1200-megawatt electric capacity each; fuel-cycle centers, involving fuel reprocessing plants, mixed-oxide fuel fabrication facilities, and high-level and transuranic radioactive waste management facilities, with a capacity corresponding to the fuel throughput of power plants with a total capacity of approximately 50,000 to 300,000 MWe; and combined centers, containing both power plants and fuel cycle facilities in representative possible combinations. Included among the principal issues considered in evaluation of feasibility of nuclear energy centers are dissipation of the waste heat from the power-generating facilities; transmission system design, reliability, and economics; radiological impact; and environmental impact

  6. Present situation of radioactive contamination in and around the former Soviet Union's Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Yamamoto, M.; Hoshi, M.; Takada, J.; Tsukatani, T.; Oikawa, S.; Yoshikawa, I.; Takatsuji, T.; Sekerbaev, A. Kh.; Gusev, B.I.

    2001-01-01

    Field missions were sent to the Semipalatinsk regions to investigate the present radioecological situation as a result of the radioactive fallout from nuclear test explosions carried out at the former Soviet Union's Semipalatinsk nuclear test site (SNTS). For this purpose, surface and core soil samples were collected at more than 60 sites, including several settlements such as Dolon, Chagan and Sarzhal, within and outside the SNTS territory. The radioactivities of long-lived radionuclides, 137 Cs, 238 Pu and 239,240 Pu, and the atomic ratio of 240 Pu/ 239 Pu were determined in combination with non-destructive g-ray spectrometric method and radiochemical separation followed by a-particle spectrometric and/or ICP-MS methods. The results showed a distinction of 137 Cs and 239,240 Pu inventories in soil depending on a sampling sites. Although 137 Cs was within typical environmental levels except for the area near the first nuclear test site and Balapan, 239,240 Pu was at elevated levels in all areas we visited. This high Pu contamination was recognized to be due to the weapons-grade Pu from the SNTS by the measurement of 240 Pu/ 239P u atomic ratio in soil samples. (author)

  7. Nuclear waste repository siting and locational conflict analysis: A contextual approach

    International Nuclear Information System (INIS)

    Murauskas, G.T.

    1989-01-01

    This study develops and evaluates an alternative framework that is based on contextual variables. The premise is that differences in attitudes and perceptions regarding the local siting of nuclear wastes and differences in attitudes regarding siting decision-making procedures are influenced by local political, economic, and cultural variables. This framework articulates the nature of conflict in terms of the incongruence between the use-value individuals ascribe to their present situation and the anticipated exchange-value individuals associate with the local siting of a nuclear waste repository. In order to evaluate this conceptual framework a survey was conducted of residents in four communities representing distinct societal contexts: Richton, Mississippi; Peterborough, New Hampshire; Richland, Washington; and Antigo/Waupaca, Wisconsin. Data analyses indicate substantial differences in economic expectations associated with the local siting of a high-level nuclear waste repository and in perception regarding the impacts such a repository might have on the environment, local agriculture, personal health and safety, and the quality of life

  8. A county administrations perspective of the EIA process for the siting of a nuclear waste repository

    International Nuclear Information System (INIS)

    Brodin, G.

    1995-01-01

    Existing and planned activities with possible environmental consequences that affects the northernmost county of Sweden, Norrbotten, are discussed, i. e. the disposal of Swedish nuclear wastes and the increasing storage of nuclear wastes on the Kola peninsula in Russia. A need for developing regional expertise at the Luleaa University is felt, and a proposal has been given for creating a 'Centre for the Study of Strategic Siting, CSS'. The County Administration has committed itself to assist the University in strengthening the necessary competence for, and to instigate a national effort for creation of, such a centre

  9. Projecting labor demand and worker immigration at nuclear power plant construction sites: an evaluation of methodology

    International Nuclear Information System (INIS)

    Herzog, H.W. Jr; Schlottmann, A.M.; Schriver, W.R.

    1981-12-01

    The study evaluates methodology employed for the projection of labor demand at, and worker migration to, nuclear power plant construction sites. In addition, suggestions are offered as to how this projection methodology might be improved. The study focuses on projection methodologies which forecast either construction worker migration or labor requirements of alternative types of construction activity. Suggested methodological improvements relate both to institutional factors within the nuclear power plant construction industry, and to a better use of craft-specific data on construction worker demand/supply. In addition, the timeliness and availability of the regional occupational data required to support, or implement these suggestions are examined

  10. Assessment of radiological consequences of routine releases in a site with various nuclear facilities

    International Nuclear Information System (INIS)

    Lucinio, Elena Albeira Guirado

    2003-01-01

    This work evaluates the radiological consequences of a nuclear site with a complex of fuel enrichment, conversion, reconversion facilities and a nuclear reactor. A methodology recommended by the Commission of the European Communities (CEC) is used and implemented in the PC-CREAM computer code. This code is composed of six linked modules, which describe the transfer of radionuclides to the environment, the pathways on which people may be exposed to radiation, and the radiological consequences. Radiation doses to a selected population are evaluated taking into account atmospheric and aquatic releases. (author)

  11. A county administrations perspective of the EIA process for the siting of a nuclear waste repository

    Energy Technology Data Exchange (ETDEWEB)

    Brodin, G. [County Administrative Board in Norrbotten (Sweden)

    1995-12-01

    Existing and planned activities with possible environmental consequences that affects the northernmost county of Sweden, Norrbotten, are discussed, i. e. the disposal of Swedish nuclear wastes and the increasing storage of nuclear wastes on the Kola peninsula in Russia. A need for developing regional expertise at the Luleaa University is felt, and a proposal has been given for creating a `Centre for the Study of Strategic Siting, CSS`. The County Administration has committed itself to assist the University in strengthening the necessary competence for, and to instigate a national effort for creation of, such a centre.

  12. Engineering assessment of inactive uranium mill tailings: Phillips/United Nuclear site, Ambrosia Lake, New Mexico

    International Nuclear Information System (INIS)

    1981-10-01

    Ford, Bacon and Davis Utah, Inc., has reevaluated the Phillips/United Nuclear site in order to revise the December 1977 engineering assessment of the problems resulting from the existence of radioactive uranium mill tailings at Ambrosia Lake, New Mexico. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from 2.6 million dry tons of tailings at the Phillips/United Nuclear site constitutes the most significant environmental impact, although windblown tailings and external gamma radiation also are factors. The four alternative actions presented in this engineering assessment range from millsite decontamination with the addition of 3 m of stabilization cover material, to removal of the tailings to remote disposal sites and decontamination of the tailings site. Cost estimates for the four options range from about $21,500,000 for stabilization in-place, to about $45,200,000 for disposal at a distance of about 15 mi. Three principal alternatives for the reprocessing of the Phillips/United Nuclear tailings were examined: heap leaching; treatment at an existing mill; and reprocessing at a new conventional mill constructed for tailings reprocessing.The cost of the uranium recovered would be about $87/lb of U 3 O 8 by either heap leach or conventional plant process. The spot market price for uranium was $25/lb early in 1981. Reprocessing the Phillips/United Nuclear tailings for uranium recovery does not appear to be economically attractive under present or foreseeable market conditions

  13. Overview of the spent nuclear fuel storage facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    Thomas, Jay

    1999-01-01

    The May 1996 Record of Decision on a Proposed Nuclear Weapons Nonproliferation Policy concerning Foreign Research Reactor Spent Nuclear Fuel initiated a 13 year campaign renewing a policy to support the return of spent nuclear fuel containing uranium of U.S.-origin from foreign research reactors to the United States. As of July 1999, over 18% of the approximately 13,000 spent nuclear fuel assemblies from participating countries have been returned to the Savannah River Site (SRS). These 2400 assemblies are currently stored in two dedicated SRS wet storage facilities. One is the Receiving Basin for Off-site Fuels (RBOF) and the other as L-Basin. RBOF, built in the early 60's to support the 'Atoms for Peace' program, has been receiving off-site fuel for over 35 years. RBOF has received approximately 1950 casks since startup and has the capability of handling all of the casks currently used in the FRR program. However, RBOF is 90% filled to capacity and is not capable of storing all of the fuel to be received in the program. L-Basin was originally used as temporary storage for materials irradiated in SRS's L-Reactor. New storage racks and other modifications were completed in 1996 that improved water quality and allowed L-Basin to receive, handle and store spent nuclear fuel assemblies and components from off-site. The first foreign cask was received into L-Area in April 1997 and approximately 86 foreign and domestic casks have been received since that time. This paper provides an overview of activities related to fuel receipt and storage in both the Receiving Basin for Off-site Fuels (RBOF) and L-Basin facilities. It will illustrate each step of the fuel receipt program from arrival of casks at SRS through cask unloading and decontamination. It will follow the fuel handling process, from fuel unloading, through the cropping and bundling stages, and final placement in the wet storage rack. Decontamination methods and equipment will be explained to show how the empty

  14. Overview of the spent nuclear fuel storage facilities at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Conatser, E.R.; Thomas, J.E. [Westinghouse Savannah River Company, Aiken, SC 29808 (United States)

    2000-07-01

    The May 1996 Record of Decision on a Proposed Nuclear Weapons Nonproliferation Policy concerning Foreign Research Reactor Spent Nuclear Fuel initiated a 13 year campaign renewing a policy to support the return of spent nuclear fuel containing uranium of U.S. origin from foreign research reactors to the United States. As of December 1999, over 22% of the approximately 13,000 spent nuclear fuel assemblies from participating countries have been returned to the Savannah River Site (SRS). These {approx}2650 assemblies are currently stored in two dedicated SRS wet storage facilities. One is the Receiving Basin for Off-site Fuels (RBOF) and the other as L-Basin. RBOF, built in the early 60's to support the 'Atoms for Peace' program, has been receiving off-site fuel for over 35 years. RBOF has received approximately 1950 casks since startup and has the capability of handling all of the casks currently used in the FRR program. However, RBOF is 90% filled to capacity and is not capable of storing all of the fuel to be received in the program. L-Basin was originally used as temporary storage for materials irradiated in SRS's L-Reactor. New storage racks and other modifications were completed in 1996 that improved water quality and allowed the L-Basin to receive, handle and store spent nuclear fuel assemblies and components from off-site. The first foreign cask was received into the L-Area in April 1997 and approximately 105 foreign and domestic casks have been received since that time. This paper provides an overview of activities related to fuel receipt and storage in both the Receiving Basin for Off-site Fuels (RBOF) and L-Basin facilities. It will illustrate each step of the fuel receipt program from arrival of casks at SRS through cask unloading and decontamination. It will follow the fuel handling process, from fuel unloading, through the cropping and bundling stages, and final placement in the wet storage rack. Decontamination methods and equipment

  15. Overview of the spent nuclear fuel storage facilities at the Savannah River Site

    International Nuclear Information System (INIS)

    Conatser, E.R.; Thomas, J.E.

    2000-01-01

    The May 1996 Record of Decision on a Proposed Nuclear Weapons Nonproliferation Policy concerning Foreign Research Reactor Spent Nuclear Fuel initiated a 13 year campaign renewing a policy to support the return of spent nuclear fuel containing uranium of U.S. origin from foreign research reactors to the United States. As of December 1999, over 22% of the approximately 13,000 spent nuclear fuel assemblies from participating countries have been returned to the Savannah River Site (SRS). These ∼2650 assemblies are currently stored in two dedicated SRS wet storage facilities. One is the Receiving Basin for Off-site Fuels (RBOF) and the other as L-Basin. RBOF, built in the early 60's to support the 'Atoms for Peace' program, has been receiving off-site fuel for over 35 years. RBOF has received approximately 1950 casks since startup and has the capability of handling all of the casks currently used in the FRR program. However, RBOF is 90% filled to capacity and is not capable of storing all of the fuel to be received in the program. L-Basin was originally used as temporary storage for materials irradiated in SRS's L-Reactor. New storage racks and other modifications were completed in 1996 that improved water quality and allowed the L-Basin to receive, handle and store spent nuclear fuel assemblies and components from off-site. The first foreign cask was received into the L-Area in April 1997 and approximately 105 foreign and domestic casks have been received since that time. This paper provides an overview of activities related to fuel receipt and storage in both the Receiving Basin for Off-site Fuels (RBOF) and L-Basin facilities. It will illustrate each step of the fuel receipt program from arrival of casks at SRS through cask unloading and decontamination. It will follow the fuel handling process, from fuel unloading, through the cropping and bundling stages, and final placement in the wet storage rack. Decontamination methods and equipment will be explained to show

  16. Savannah River Site nuclear materials management plan FY 2017-2031

    Energy Technology Data Exchange (ETDEWEB)

    Magoulas, V. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-06-22

    The purpose of the Nuclear Materials Management Plan (herein referred to as “this Plan”) is to integrate and document the activities required to disposition the legacy and/or surplus Enriched Uranium (EU) and Plutonium (Pu) and other nuclear materials already stored or anticipated to be received by facilities at the Department of Energy (DOE) Savannah River Site (SRS) as well as the activities to support the DOE Tritium mission. It establishes a planning basis for EU and Pu processing operations in Environmental Management Operations (EMO) facilities through the end of their program missions and for the tritium through the National Nuclear Security Administration (NNSA) Defense Programs (DP) facilities. Its development is a joint effort among the Department of Energy - Savannah River (DOE-SR), DOE – Environmental Management (EM), NNSA Office of Material Management and Minimization (M3), NNSA Savannah River Field Office (SRFO), and the Management and Operations (M&O) contractor, Savannah River Nuclear Solutions, LLC (SRNS). Life-cycle program planning for Nuclear Materials Stabilization and Disposition and the Tritium Enterprise may use this Plan as a basis for the development of the nuclear materials disposition scope and schedule. This Plan assumes full funding to accomplish the required project and operations activities. It is recognized that some aspects of this Plan are pre decisional with regard to National Environmental Policy Act (NEPA); in such cases new NEPA actions will be required.

  17. Alternative methods of salt disposal at the seven salt sites for a nuclear waste repository

    International Nuclear Information System (INIS)

    1987-02-01

    This study discusses the various alternative salt management techniques for the disposal of excess mined salt at seven potentially acceptable nuclear waste repository sites: Deaf Smith and Swisher Counties, Texas; Richton and Cypress Creek Domes, Mississippi; Vacherie Dome, Louisiana; and Davis and Lavender Canyons, Utah. Because the repository development involves the underground excavation of corridors and waste emplacement rooms, in either bedded or domed salt formations, excess salt will be mined and must be disposed of offsite. The salt disposal alternatives examined for all the sites include commercial use, ocean disposal, deep well injection, landfill disposal, and underground mine disposal. These alternatives (and other site-specific disposal methods) are reviewed, using estimated amounts of excavated, backfilled, and excess salt. Methods of transporting the excess salt are discussed, along with possible impacts of each disposal method and potential regulatory requirements. A preferred method of disposal is recommended for each potentially acceptable repository site. 14 refs., 5 tabs

  18. Postulated accident scenarios for the on-site transport of spent nuclear fuel

    International Nuclear Information System (INIS)

    Morandin, G.; Sauve, R.

    2004-01-01

    Once a spent fuel container is loaded with spent fuel it typically travels on-site to a processing building for permanent lid attachment. During on-site transport a lid clamp is utilized to ensure the container lid remains in place. The safe on-site transport of spent nuclear fuel must rely on the structural integrity of the transport container and system of transport. Regard for on-site traffic and safe, efficient travel routes are important and manageable with well thought-out planning. Non-manageable incidences, such as flying debris from tornado force winds or postulated blasts in proximity to the transport container, that may result in high velocity impact and shock loading on the transport system must be considered. This paper consists of simulations that consider these types of postulated accident scenarios using detailed nonlinear finite element techniques

  19. Use of critical pathway models and log-normal frequency distributions for siting nuclear facilities

    International Nuclear Information System (INIS)

    Waite, D.A.; Denham, D.H.

    1975-01-01

    The advantages and disadvantages of potential sites for nuclear facilities are evaluated through the use of environmental pathway and log-normal distribution analysis. Environmental considerations of nuclear facility siting are necessarily geared to the identification of media believed to be sifnificant in terms of dose to man or to be potential centres for long-term accumulation of contaminants. To aid in meeting the scope and purpose of this identification, an exposure pathway diagram must be developed. This type of diagram helps to locate pertinent environmental media, points of expected long-term contaminant accumulation, and points of population/contaminant interface for both radioactive and non-radioactive contaminants. Confirmation of facility siting conclusions drawn from pathway considerations must usually be derived from an investigatory environmental surveillance programme. Battelle's experience with environmental surveillance data interpretation using log-normal techniques indicates that this distribution has much to offer in the planning, execution and analysis phases of such a programme. How these basic principles apply to the actual siting of a nuclear facility is demonstrated for a centrifuge-type uranium enrichment facility as an example. A model facility is examined to the extent of available data in terms of potential contaminants and facility general environmental needs. A critical exposure pathway diagram is developed to the point of prescribing the characteristics of an optimum site for such a facility. Possible necessary deviations from climatic constraints are reviewed and reconciled with conclusions drawn from the exposure pathway analysis. Details of log-normal distribution analysis techniques are presented, with examples of environmental surveillance data to illustrate data manipulation techniques and interpretation procedures as they affect the investigatory environmental surveillance programme. Appropriate consideration is given these

  20. Does nuclear power-related facility siting always lower the local property Values? Comparative analysis among the sites in Japan

    International Nuclear Information System (INIS)

    Yamane, Fumihiro; Ohgaki, Hideaki; Asano, Kota

    2011-01-01

    Yamane et al. (2011) carried out hedonic house rent analyses for several nuclear power plant sites in Japan, compared the result for each plant, and obtained some empirical results indicating that the local residents' marginal willingness-to-pay (MWTP) for living near the plant was not necessarily positive and that the MWTP was correlated with operation years of the plants and some of the host communities' attributes (i.e., population density, financial condition and public service improvement). However, these results may suffer from biases and inefficiency in estimating hedonic functions, caused by spatial dependency: spatial autoregression and spatial autocorrelation. In this paper, we introduce spatial econometric techniques to settle this problem. As a revised result, it is indicated that the local residents' MWTP is correlated with past accidents in the plants, education service improvement in the host communities and so on. (author)