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Sample records for e3640 decommissioning aberdeen

  1. Geophysics: Building E5481 decommissioning, Aberdeen Proving Ground

    International Nuclear Information System (INIS)

    Building E5481 is one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The building is located on the northern margin of a landfill that was sited in a wetland. The large number of magnetic sources surrounding the building are believed to be contained in construction fill that had been used to raise the grade. The smaller anomalies, for the most part, are not imaged with ground radar or by electrical profiling. A conductive zone trending northwest to southeast across the site is spatially related to an old roadbed. Higher resistivity areas in the northeast and east are probably representive of background values. Three high-amplitude, positive, rectangular magnetic anomalies have unknown sources. The features do not have equivalent electrical signatures, nor are they seen with radar imaging

  2. Geophysics: Building E5375 decommissioning, Aberdeen Proving Ground

    International Nuclear Information System (INIS)

    Building E5375 was one of ten potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar (GPR), were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. Several anomalies wear, noted: (1) An underground storage tank located 25 ft east of Building E5375 was identified with magnetic, resistivity, and GPR profiling. (2) A three-point resistivity anomaly, 12 ft east of the northeast comer of Building E5374 (which borders Building E5375) and 5 ft south of the area surveyed with the magnetometer, may be caused by another underground storage tank. (3) A 2,500-gamma magnetic anomaly near the northeast corner of the site has no equivalent resistivity anomaly, although disruption in GPR reflectors was observed. (4) A one-point magnetic anomaly was located at the northeast comer, but its source cannot be resolved. A chaotic reflective zone to the east represents the radar signature of Building E5375 construction fill

  3. Geophysics: Building E5190 decommissioning, Aberdeen Proving Ground

    Energy Technology Data Exchange (ETDEWEB)

    Miller, S.F.; Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.

    1992-07-01

    Building E5190 is one of ten potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May 1992. A noninvasive geophysical survey, including the complementary technologies of magnetics, electrical resistivity, and ground-penetrating radar, was conducted around the perimeter as a guide to developing a sampling and monitoring program prior to decommissioning and dismantling the building. The magnetics surveys indicated that multistation, positive magnetic sources are randomly distributed north and west of the building. Two linear trends were noted: one that may outline buried utility lines and another that is produced by a steel-covered trench. The resistivity profiling indicated three conductive zones: one due to increased moisture in a ditch, one associated with buried utility lines, and a third zone associated with the steel-covered trench. Ground-penetrating radar imaging detected two significant anomalies, which were correlated with small-amplitude magnetic anomalies. The objectives of the study -- to detect and locate objects and to characterize a located object were achieved.

  4. Interim progress report -- geophysics: Decommissioning of Buildings E5974 and E5978, Aberdeen Proving Ground

    International Nuclear Information System (INIS)

    Buildings E5974 and E5978, located near the mouth of Canal Creek, were among 10 potentially contaminated sites in the Westwood and Canal Creek areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including the complementary technologies of magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeters of the buildings to guide a sampling program prior to decommissioning and dismantling. The magnetic anomalies and the electrically conductive areas around these buildings have a spatial relationship similar to that observed in low-lying sites in the Canal Creek area; they are probably associated with construction fill. Electrically conductive terrain is dominant on the eastern side of the site, and resistive terrain predominates on the west. The smaller magnetic anomalies are not imaged with ground radar or by electrical profiling. The high resistivities in the northwest quadrant are believed to be caused by a natural sand lens. The causes of three magnetic anomalies in the high-resistivity area are unidentified, but they are probably anthropogenic

  5. Geophysics: Building E5190 decommissioning, Aberdeen Proving Ground. Interim progress report

    Energy Technology Data Exchange (ETDEWEB)

    Miller, S.F.; Thompson, M.D.; McGinnis, M.G.; McGinnis, L.D.

    1992-07-01

    Building E5190 is one of ten potentially contaminated sites in the Canal Creek area of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May 1992. A noninvasive geophysical survey, including the complementary technologies of magnetics, electrical resistivity, and ground-penetrating radar, was conducted around the perimeter as a guide to developing a sampling and monitoring program prior to decommissioning and dismantling the building. The magnetics surveys indicated that multistation, positive magnetic sources are randomly distributed north and west of the building. Two linear trends were noted: one that may outline buried utility lines and another that is produced by a steel-covered trench. The resistivity profiling indicated three conductive zones: one due to increased moisture in a ditch, one associated with buried utility lines, and a third zone associated with the steel-covered trench. Ground-penetrating radar imaging detected two significant anomalies, which were correlated with small-amplitude magnetic anomalies. The objectives of the study -- to detect and locate objects and to characterize a located object were achieved.

  6. Environmental geophysics: Buildings E5485, E5487, and E5489 decommissioning - the open-quotes Ghost Townclose quotes complex, Aberdeen Proving Ground, Maryland

    International Nuclear Information System (INIS)

    Buildings E5485, E5487, and E5489, referred to informally as the open-quotes Ghost Townclose quotes complex, are potentially contaminated sites in the Edgewood section of Aberdeen Proving Ground. Noninvasive geophysical surveys, including magnetics, EM-31, EM-61, and ground-penetrating radar, were conducted to assist a sampling and monitoring program prior to decommissioning and dismantling of the buildings. The buildings are located on a marginal wetland bordering the west branch of Canal Creek. The dominant geophysical signature in the open-quotes Ghost Town close quotes complex is a pattern of northeast-southwest and northwest-southeast anomalies that appear to be associated with a trench/pipe/sewer system, documented by the presence of a manhole. Combinations of anomalies suggest that line sources include nonmetallic and ferromagnetic materials in trenches. On the basis of anomaly associations, the sewer lines probably rest in a trench, back-filled with conductive, amphibolitic, crushed rock. Where the sewer lines connect manholes or junctions with other lines, ferromagnetic materials are present. Isolated, unidentified magnetic anomalies litter the area around Building E5487, particularly to the north. Three small magnetic sources are located east of Building E5487

  7. Decommissioning

    International Nuclear Information System (INIS)

    The main part of this deals with nuclear power station decommissioning. The reactors already decommissioned or partially so are listed. The most important are Elk River, the advanced gas cooled reactor at Windscale and Shippingport. The three stages of decommissioning are defined and the benefits of delaying decommissioning until the level of activity decreases are discussed. The wastes resulting from decommissioning, the cost and the packaging problems are considered. Some generalized comments are made on decommissioning active process plants. General features on simplifying plant decommissioning are listed. Although there are no major technical problems in decommissioning, the scale of the operation does make organization and logistics difficult. (U.K.)

  8. Initial building investigations at Aberdeen Proving Ground, Maryland: Building E5375

    Energy Technology Data Exchange (ETDEWEB)

    Brubaker, K.L.; Dougherty, J.M.; Tome, C.

    1993-06-01

    As part of a building decommissioning and demolition program at Aberdeen Proving Ground, a detailed inspection of each target building is being conducted in order to characterize and describe the state of the building as it currently exists and to identify areas potentially contaminated with toxic or other hazardous substances. Room surfaces, drains and sumps, remaining equipment, and such associated exterior aboveground and underground appurtenances as tanks and pipelines are among the features, generically termed compartments, that may be potentially contaminated. Detailed drawings are being prepared for each building to illustrate the existing structure. This report presents the results of the inspection of Building E5375 in the Edgewood/Canal Creek area of Aberdeen Proving Ground. Nine potentially contaminated compartments were identified in this building and its vicinity.

  9. Geophysics: Building E5476 decommissiong, Aberdeen Proving Ground

    International Nuclear Information System (INIS)

    Building E5476 was one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, electrical resistivity, and ground-penetrating radar, were conducted around the perimeter of the building to guide a sampling program prior to decommissioning and dismantling. The large number of magnetic sources surrounding the building are believed to be contained in construction fill. The smaller anomalies, for the most part, were not imaged with ground radar or by electrical profiling. Large magnetic anomalies near the southwest comer of the building are due to aboveground standpipes and steel-reinforced concrete. Two high-resistivity areas, one projecting northeast from the building and another south of the original structure, may indicate the presence of organic pore fluids in the subsurface. A conductive lineament protruding from the south wall that is enclosed by the southem, high-resistivity feature is not associated with an equivalent magnetic anomaly. Magnetic and electrical anomalies south of the old landfill boundary are probably not associated with the building. The boundary is marked by a band of magnetic anomalies and a conductive zone trending northwest to southeast. The cause of high resistivities in a semicircular area in the southwest comer, within the landfill area, is unexplained

  10. Decommissioning Handbook

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    The Decommissioning Handbook is a technical guide for the decommissioning of nuclear facilities. The decommissioning of a nuclear facility involves the removal of the radioactive and, for practical reasons, hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. This handbook identifies and technologies and techniques that will accomplish these objectives. The emphasis in this handbook is on characterization; waste treatment; decontamination; dismantling, segmenting, demolition; and remote technologies. Other aspects that are discussed in some detail include the regulations governing decommissioning, worker and environmental protection, and packaging and transportation of the waste materials. The handbook describes in general terms the overall decommissioning project, including planning, cost estimating, and operating practices that would ease preparation of the Decommissioning Plan and the decommissioning itself. The reader is referred to other documents for more detailed information. This Decommissioning Handbook has been prepared by Enserch Environmental Corporation for the US Department of Energy and is a complete restructuring of the original handbook developed in 1980 by Nuclear Energy Services. The significant changes between the two documents are the addition of current and the deletion of obsolete technologies and the addition of chapters on project planning and the Decommissioning Plan, regulatory requirements, characterization, remote technology, and packaging and transportation of the waste materials.

  11. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Planning studies for decommissioning the Magnox, then the advanced gas cooled reactors, and much further in the future, the pressurized water reactors are in progress. Decommissioning will be in three stages. The first stage is the defuelling, removal of waste and decommissioning. This is done immediately the station is shut down. The second is the removal of the plant and buildings outside the reactor biological shield. This includes the boilers. The final stage is to take apart the reactor itself. The Magnox stations have graphite cores of over 2000 tonnes per reactor. These are also core supports, pressure vessel etc, all of which are active. An outline plan for decommissioning Sizewell-B (to make decommissioning easier when the time comes), is discussed briefly. (U.K.)

  12. Decommissioning handbook

    International Nuclear Information System (INIS)

    The purpose of this paper is to provide information on the Handbook and its application as a resource in decontamination and decommissioning (D and D) work. The nature of the unique hazards contained in nuclear facilities demand a comprehensive step-by-step program to cover their design, licensing, and commissioning or start-up. Similarly, because of residual radioactivity, a termination of operations (decommissioning) also presents hazards that must be addressed from a technological and programmatic standpoint. To meet the needs raised by these issues, the original Decommissioning Handbook was prepared in 1980 by Nuclear Energy Services under contract to the United States Department of Energy (DOE). Its mission was to provide technical guidance on the D and D of both commercial and government-owned nuclear facilities, including characterization, decontamination, dismantling, and disposition (disposal or salvage) of a facility's equipment and structure. In addition, depending on the regulatory requirements for material disposal and/or the wastes generated by decontamination, the management of waste can also be considered as a decommissioning activity. Chapters are Operational and predecommissioning activities; Decommissioning project; Decommissioning plan; Regulations; Final project configuration; Characterization; Waste treatment; Decontamination; Dismantling, segmenting, and demolition; Remote handling equipment; Environmental protection; Packaging and transportation; and Decommissioning cost estimates. Appendices contain a prediction method for estimation of radiactive inventory and a glossary

  13. Decommissioning handbook

    International Nuclear Information System (INIS)

    This document is a compilation of information pertinent to the decommissioning of surplus nuclear facilities. This handbook is intended to describe all stages of the decommissioning process including selection of the end product, estimation of the radioactive inventory, estimation of occupational exposures, description of the state-of-the-art in re decontamination, remote csposition of wastes, and estimation of program costs. Presentation of state-of-the-art technology and data related to decommissioning will aid in consistent and efficient program planning and performance. Particular attention is focused on available technology applicable to those decommissioning activities that have not been accomplished before, such as remote segmenting and handling of highly activated 1100 MW(e) light water reactor vessel internals and thick-walled reactor vessels. A summary of available information associated with the planning and estimating of a decommissioning program is also presented. Summarized in particular are the methodologies associated with the calculation and measurement of activated material inventory, distribution, and surface dose level, system contamination inventory and distribution, and work area dose levels. Cost estimating techniques are also presented and the manner in which to account for variations in labor costs as impacting labor-intensive work activities is explained

  14. Decommissioning handbook

    Energy Technology Data Exchange (ETDEWEB)

    Manion, W.J.; LaGuardia, T.S.

    1980-11-01

    This document is a compilation of information pertinent to the decommissioning of surplus nuclear facilities. This handbook is intended to describe all stages of the decommissioning process including selection of the end product, estimation of the radioactive inventory, estimation of occupational exposures, description of the state-of-the-art in re decontamination, remote csposition of wastes, and estimation of program costs. Presentation of state-of-the-art technology and data related to decommissioning will aid in consistent and efficient program planning and performance. Particular attention is focused on available technology applicable to those decommissioning activities that have not been accomplished before, such as remote segmenting and handling of highly activated 1100 MW(e) light water reactor vessel internals and thick-walled reactor vessels. A summary of available information associated with the planning and estimating of a decommissioning program is also presented. Summarized in particular are the methodologies associated with the calculation and measurement of activated material inventory, distribution, and surface dose level, system contamination inventory and distribution, and work area dose levels. Cost estimating techniques are also presented and the manner in which to account for variations in labor costs as impacting labor-intensive work activities is explained.

  15. Unexploded ordnance issues at Aberdeen Proving Ground: Background information

    Energy Technology Data Exchange (ETDEWEB)

    Rosenblatt, D.H.

    1996-11-01

    This document summarizes currently available information about the presence and significance of unexploded ordnance (UXO) in the two main areas of Aberdeen Proving Ground: Aberdeen Area and Edgewood Area. Known UXO in the land ranges of the Aberdeen Area consists entirely of conventional munitions. The Edgewood Area contains, in addition to conventional munitions, a significant quantity of chemical-munition UXO, which is reflected in the presence of chemical agent decomposition products in Edgewood Area ground-water samples. It may be concluded from current information that the UXO at Aberdeen Proving Ground has not adversely affected the environment through release of toxic substances to the public domain, especially not by water pathways, and is not likely to do so in the near future. Nevertheless, modest but periodic monitoring of groundwater and nearby surface waters would be a prudent policy.

  16. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Sufficient work has now been done, on a world-wide basis, to justify confidence that full decommissioning of nuclear installations, both plant and reactors, can be carried out safely and efficiently. Projects in several countries should confirm this in the next few years. In the United Kingdom, good progress has been made with the Windscale Advanced Gas-cooled Reactor and supporting development work is finding solutions to resolve uncertainties. Estimates from several sources suggest that decommissioning costs can be kept to an acceptable level. (author)

  17. Decommissioning standards

    International Nuclear Information System (INIS)

    EPA has agreed to establish a series of environmental standards for the safe disposal of radioactive waste through participation in the Interagency Review Group on Nuclear Waste Management (IRG). One of the standards required under the IRG is the standard for decommissioning of radioactive contaminated sites, facilities, and materials. This standard is to be proposed by December 1980 and promulgated by December 1981. Several considerations are important in establishing these standards. This study includes discussions of some of these considerations and attempts to evaluate their relative importance. Items covered include: the form of the standards, timing for decommissioning, occupational radiation protection, costs and financial provisions. 4 refs

  18. A consolidated environmental monitoring plan for Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Ebinger, M.H.; Hansen, W.R.

    1997-04-01

    The US Army operates facilities in Edgewood and Aberdeen under several licenses from the Nuclear Regulatory Commission (NRC). Compliance with each license is time consuming and could potentially result in duplicated efforts to demonstrate compliance with existing environmental regulations. The goal of the ERM plan is to provide the sampling necessary to ensure that operations at Edgewood and Aberdeen are within applicable regulatory guidelines and to provide a means of ensuring that adverse effects to the environment are minimized. Existing sampling plans and environmental data generated from those plans are briefly reviewed as part of the development of the present ERM plan. The new ERM plan was designed to provide data that can be used for assessing risks to the environment and to humans using Aberdeen and Edgewood areas. Existing sampling is modified and new sampling is proposed based on the results of the long-term DU fate study. In that study, different environmental pathways were identified that would show transport of DU at Aberdeen. Those pathways would also be impacted by other radioactive constituents from Aberdeen and Edgewood areas. The ERM plan presented in this document includes sampling from Edgewood and Aberdeen facilities. The main radioactive constituents of concern at Edgewood are C, P, N, S, H, I, Co, Cs, Ca, Sr and U that are used in radiolabeling different compounds and tracers for different reactions and syntheses. Air and water sampling are the thrust of efforts at the Edgewood area.

  19. Decommissioning challenges

    International Nuclear Information System (INIS)

    A global perspective is given of the problems facing the oil and gas industry from the decommissioning of offshore platforms after their useful life. The range of platforms includes shallow and deep water steel, gravity based and floaters. The wide variety even within these categories is illustrated by examples from around the world. (UK)

  20. Gaining confidence in decommissioning

    International Nuclear Information System (INIS)

    A report is given of the International Symposium on Decommissioning, held in Seattle, 11-14 October 1982. Research and development work on decommissioning, waste management and past decommissioning experience were topics discussed. (U.K.)

  1. 1982 international decommissioning symposium

    International Nuclear Information System (INIS)

    Sixty-four papers were presented at the following sessions: policy, regulations, and standards; management of decommissioning wastes; decommissioning experience; decommissioning tooling and techniques; radiological concerns; and planning and engineering

  2. Workshop on decommissioning

    International Nuclear Information System (INIS)

    A Nordic workshop on decommissioning of nuclear facilities was held at Risoe in Denmark September 13-15, 2005. The workshop was arranged by NKS in cooperation with the company Danish Decommissioning, DD, responsible for decommissioning of nuclear facilities at Risoe. Oral presentations were made within the following areas: International and national recommendations and requirements concerning decommissioning of nuclear facilities Authority experiences of decommissioning cases Decommissioning of nuclear facilities in Denmark Decommissioning of nuclear facilities in Sweden Plans for decommissioning of nuclear facilities in Norway Plans for decommissioning of nuclear facilities in Finland Decommissioning of nuclear facilities in German and the UK Decommissioning of nuclear facilities in the former Soviet Union Results from research and development A list with proposals for future work within NKS has been prepared based on results from group-work and discussions. The list contains strategic, economical and political issues, technical issues and issues regarding competence and communication. (au)

  3. Utility planning for decommissioning

    International Nuclear Information System (INIS)

    Though the biggest impact on a utility of nuclear power plant decommissioning may occur many years from now, procrastination of efforts to be prepared for that time is unwarranted. Foresight put into action through planning can significantly affect that impact. Financial planning can assure the recovery of decommissioning costs in a manner equitable to customers. Decision-making planning can minimize adverse affects of current decisions on later decommissioning impacts and prepare a utility to be equipped to make later decommissioning decisions. Technological knowledge base planning can support all other planning aspects for decommissioning and prepare a utility for decommissioning decisions. Informed project planning can ward off potentially significant pitfalls during decommissioning and optimize the effectiveness of the actual decommissioning efforts

  4. Decommissioning Fort St. Vrain

    International Nuclear Information System (INIS)

    This article describes the decommissioning of Fort St. Vrain, a unique, high-temperature gas-cooled reactor with a 330 megawatta electric output. The operating licence was issued in 1973 and the reactor was shut down in 1989 because of operational problems. Westinghouse Electric Company is responsible for the decommissioning. Specific components of the decommissioning described are the fuel removal and storage, component removal and disposal, diving operations, and the final stages of decommissioning. 7 figs

  5. Authority and discipline in Aberdeen, 1650-1700

    OpenAIRE

    DesBrisay, Gordon Russell

    1989-01-01

    This study is concerned with aspects of urban society in the Scottish city of Aberdeen in the second half of the seventeenth century. The principal aim is to examine the multi-faceted nature and workings of civic government, of the interlocking hierarchies of people and institutions which together formed an invisible web of authority and discipline in the town. The burgh's three main administrative and judicial bodies - the town council, the kirk session, and the justice ...

  6. Genetic characterization of Aberdeen Angus cattle using molecular markers

    Directory of Open Access Journals (Sweden)

    Luciana Pimentel de Mello Klocker Vasconcellos

    2003-01-01

    Full Text Available Aberdeen Angus beef cattle from the Brazilian herd were studied genetically using restriction fragment length polymorphism (RFLP of the kappa-casein - HinfI (CSN3 - HinfI, beta-lactoglobulin - HaeIII (LGB - HaeIII and growth hormone AluI (GH- AluI genes, as well as four microsatellites (TEXAN15, CSFM50, BM1224 and BM7160. The RFLP genotypes were determined using the polymerase chain reaction (PCR followed by digestion with restriction endonucleases and electrophoresis in agarose gels. With the exception of the microsatellite BM7160, which was analyzed in an automatic sequencer, the PCR products were genotyped by silver staining. The allele and genotype frequencies, heterozygosities and gene diversity were estimated. The values for these parameters of variability were comparable to other cattle breeds. The genetic relationship of the Aberdeen Angus to other breeds (Caracu, Canchim, Charolais, Guzerath, Gyr, Nelore, Santa Gertrudis and Simmental was investigated using Nei's genetic distance. Cluster analysis placed the Aberdeen Angus in an isolated group in the Bos taurus breeds branch. This fact is in agreement with the geographic origin of this breed.

  7. Recommended IAEA decommissioning levels

    International Nuclear Information System (INIS)

    The areas covered by each of the two terms 'decommissioning' and 'dismantling' of a nuclear installation are defined in order to distinguish them with greater accuracy. Decommissioning is first an administrative decision and afterwards all the material operations involved by this decision. Dismantling is only one of the material operations of the decommissioning but it can be the most important. For the IAEA the possible outcomes for a decommissioned installation fall under three main headings (stages) which we call 'decommissioning levels'. - level 1: shut-down with surveillance, - level 2: conditional release for another use, - level 3: unconditional release of the site

  8. Financial aspects of decommissioning (key aspects of decommissioning costing)

    International Nuclear Information System (INIS)

    In this presentation the following aspects of NPPs decommissioning are discussed: Requirements and purpose of decommissioning costing; Decommissioning costing methodologies; Standardised decommissioning cost structure; Input data for cost estimate process; Waste management in cost estimate process; Grading aspects in cost estimating; Cost control in decommissioning projects; Summary of the cost estimation process; Conclusions and recommendations.

  9. Fort St. Vrain decommissioning experiences

    International Nuclear Information System (INIS)

    Public Service Company of Colorado (PSCo) is in the process of decommissioning the Fort St Vrain nuclear station, the first large-scale commercial nuclear plant to be decommissioned under the U.S. NRC's decommissioning rule. The experience has included providing for the disposition of spent fuel, choosing a decommissioning alternative, and actively decommissioning the plant from dismantlement and decontamination through final survey

  10. Training for decommissioning

    International Nuclear Information System (INIS)

    Plants entering decommissioning face many challenges One of the most important is the challenge of training for decommissioning This is important because: The facility operators and management have spent many years successfully operating the facility; The facility management arrangements are geared to operation; Decommissioning will include non-nuclear specialists and other stakeholders; Other skills are needed to decommission successfully. UKAEA has decommissioned many facilities at its sites in Dounreay, Windscale, Harwell and Winfrith in the UK. We have faced all of the challenges previously described and have developed many training methods for ensuring the challenges are met safely and effectively. We have developed courses for specialised skills such as safety cases which can be deployed to support any decommissioning. (author)

  11. On decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    As the number of nuclear power plants commissioned is increasing worldwide, both the responsible goverment agencies and the public are more and more concerned about decommissioning nuclear facilities after they have been shut down for good. IAEA organized a symposium on November 13-17, 1978 which dealt with problems of decommissioning, covering national objectives, technical processes, radiological questions, experience in plant decommissioning, decontamination techniques and remote handling procedures. It turned out that sufficient practical experience and highly developed decommissioning concepts and techniques are now available. Experts feel that also in the future no insoluble technical problems or problems must be expected which could only be solved at inordinately high technical expenditure. The article contains a survey of the present staus of problem solutions. Current work is being dedicated to the dose rates accumulated by decommissioning personnel and to the costs of decommissioning. (orig.)

  12. Genetic characterization of Aberdeen Angus cattle using molecular markers

    OpenAIRE

    Vasconcellos Luciana Pimentel de Mello Klocker; Tambasco-Talhari Daniella; Pereira Andréa Pozzi; Coutinho Luiz Lehmann; Regitano Luciana Correia de Almeida

    2003-01-01

    Aberdeen Angus beef cattle from the Brazilian herd were studied genetically using restriction fragment length polymorphism (RFLP) of the kappa-casein - HinfI (CSN3 - HinfI), beta-lactoglobulin - HaeIII (LGB - HaeIII) and growth hormone AluI (GH- AluI) genes, as well as four microsatellites (TEXAN15, CSFM50, BM1224 and BM7160). The RFLP genotypes were determined using the polymerase chain reaction (PCR) followed by digestion with restriction endonucleases and electrophoresis in agarose gels. W...

  13. Absence of 1/29 translocation in Aberdeen Angus breed

    OpenAIRE

    De Luca, Julio César; Sister, P.; Prando, Alberto; Baldo, Andrés; Giovambattista, Guillermo

    2007-01-01

    Las translocaciones robertsonianas son las translocaciones más frecuentes en el ganado bovino. La primera translocación robertsoniana descripta en el Ganado bovino fue la 1/29. Al igual que otras fusiones céntricas esta alteración reduce la fertilidad de los animales portadores, ya que se originan gametas genéticamente desbalanceadas, provocando un aumento de la mortalidad embrionaria temprana. Se evaluó la incidencia de la translocación 1/29 en 89 bovinos Aberdeen Angus (38 hembras y 51 mach...

  14. Shippingport NPP decommissioning

    International Nuclear Information System (INIS)

    State of operations in the Shippingport NPP decommissioning, which was shut down in 1982, has been described. Data on dose rates in different components of the primary circuit are presented. During dismountling it is decided to reject the primary circuit decontamination and to remove the reactor vessel in a single package. The design of the shipping cask made of light concrete is presented. Decommissioning is planned to be finished in 1988. Total decommissioning costs will constitute 12 % of cost on NPP construction

  15. Fort St. Vrain decommissioning

    International Nuclear Information System (INIS)

    The first commercial reactor to be decommissioned under the NRC's decommissioning rule is Public Service Company of Colorado's Fort St. Vrain Nuclear Station. The dismantlement and decontamination of this 330 MWe High Temperature Gas Cooled Reactor (HTGR) has involved many challenges for PSC, including establishing adequate funding, obtaining required regulatory approvals, selecting a decommissioning alternative, defueling to an Independent Spent Fuel Storage Installation, arranging for sufficient waste disposal, and managing a large fixed-price decommissioning contract. With physical dismantlement activities about one-third complete, the project is approximately on schedule and within the agreed upon costs

  16. Feasibility studies for decommissioning

    International Nuclear Information System (INIS)

    In this presentation author deals with planning of decommission of the NPPs A1, V1 and V2 Bohunice and Mochovce. It was concluded that: Used model for decommissioning parameters assessment has been suitable for elaboration of initial decommissioning plans (feasibility studies); Basic assessment of main decommissioning parameters and basic comparison of various decommissioning options have been possible; Improvement of the model and corresponding software is desirable and works on software improvement began one year ago; V1-NPP initial decommissioning plan should be actualized, because initial decommissioning plan does not correspond by its content and structure to requirements of Act No. 130/98 and Nuclear Regulatory Authority Degree No. 246/99; Strategy of radioactive wastes treatment and conditioning together with technical provisions at Jaslovske Bohunice site was changed in comparison with the assumptions in 1991-92; Considered V1 NPP decommissioning options are necessary to be re-evaluated in accordance with latest development of knowledge and approaches to NPP decommissioning in the world; Specific unit costs are substantially and differentially changed in comparison with the assumptions in 1991-92; Necessity to take into account technical changes resulted from V1 NPP reconstruction. (author)

  17. Decommissioning planning for HIFAR

    International Nuclear Information System (INIS)

    HIFAR, a 10MW research reactor, has been in operation for the last 44 years. It is to be shut down in early 2006 after a replacement reactor is commissioned. The preferred option for decommissioning HIFAR is to remove the fuel immediately, followed by an extended period of care and maintenance. A decommissioning team will be formed to develop strategies and prepare a decommissioning plan for regulatory approval. The plan will comply with the regulatory licence conditions, be in accordance with the IAEA safety guides and will take advantage of the lessons learned from the decommissioning of other reactors. (author)

  18. NPP Krsko decommissioning concept

    International Nuclear Information System (INIS)

    At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP Krsko. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for a decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill the decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economic aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling of all activities necessary for the decommissioning of the NPP Krsko are presented. (author)

  19. NPP Krsko decommissioning concept

    International Nuclear Information System (INIS)

    At the end of the operational lifetime of a nuclear power plant (NPP) it is necessary to take measures for the decommissioning as stated in different international regulations and also in the national Slovenian law. Based on these requirements Slovenian authorities requested the development of a site specific decommissioning plan for the NPP KRSKO. In September 1995, the Nuklearna Elektrarna Krsko (NEK) developed a site specific scope and content for decommissioning plan including the assumptions for determination of the decommissioning costs. The NEK Decommissioning Plan contains sufficient information to fulfill decommissioning requirements identified by NRC, IAEA and OECD - NEA regulations. In this paper the activities and the results of development of NEK Decommissioning Plan consisting of the development of three decommissioning strategies for the NPP Krsko and selection of the most suitable strategy based on site specific, social, technical, radiological and economical aspects, cost estimates for the strategies including the costs for construction of final disposal facilities for fuel/high level waste (fuel/HLW) and low/intermediate level waste (LLW/ILW) and scheduling all activities necessary for the decommissioning of the NPP KRSKO are presented. (author)

  20. Tokai-1 decommissioning project

    International Nuclear Information System (INIS)

    Tokai-1 (GCR, Gas Cooled Reactor) nuclear power plant of JAPC (the Japan Atomic Power Company) started commercial operation in 1966 as the first commercial nuclear power plant in Japan and ceased its operation in 1998. Spent fuel elements were removed out of the reactor core and shipped to the reprocessing plant by June 2001. JAPC launched Tokai-1 decommissioning in December 2001 after the submission of the notification of decommissioning plan to the competent authority. This is the first instance of the decommissioning for a commercial nuclear power plant in Japan. During first five years, the conventional facilities were removed, such as turbine system. Cartridge Cooling Pond (CCP) water was also drained and CCP was cleaned up for future works. In 2006 JAPC started SRU (Steam Raising Unit) and auxiliary equipments removal. After the safe store of the reactor, Reactor Dismantling would be started. JAPC and Japanese Utilities make efforts on rulemaking for decommissioning and disposal in cooperation with METI. Nuclear Regulations were amended in December 2005. JAPC got approval of a Decommissioning Plan pursuant to the amended Regulations in June 2006. Under the new regulation, it is possible to be applied reasonable and phased measures to keep the unit safe in accordance with dismantling phases. Tokai-1 decommissioning project has an important role for demonstrating that the decommissioning of commercial nuclear power plant can be executed safely and economically, and for establishing the key technologies for future LWR decommissioning in Japan. (author)

  1. The IAEA's decommissioning concept

    International Nuclear Information System (INIS)

    The IAEA has been developing guidance and technical information relating to the decommissioning of nuclear facilities for over 20 years. During this time, the international concept of decommissioning, and its importance, has changed. The basic approach adopted by the IAEA is discussed in the paper. It also identifies issues that still require resolution at the international level. (author)

  2. Odin - lessons learnt. Decommissioning

    International Nuclear Information System (INIS)

    The article relates briefly to the abandoned natural gas field of Odin on the Norwegian continental shelf. The platform could be seen as the benchmark by which all other decommissioning activity in the North Sea takes place, since it is the first significantly large structure to have been decommissioned in deep water. 1 fig

  3. Decommissioning activities in FUGEN

    International Nuclear Information System (INIS)

    FUGEN Decommissioning Engineering Center (hereinafter called as 'FUGEN'), JAEA obtained the approval of the decommissioning program for the prototype Advanced Thermal Reactor on February, 2008. FUGEN has been carrying out decommissioning works based on its decommissioning program since then. In the initial stage, the dismantling works were launched in turbine system whose contamination was relatively low level and their various data have been accumulating. And the draining heavy water, tritium decontamination and transferring of heavy water were carried out safely and reasonably. The preparation for introducing the clearance system, and the research and development works for the reactor core dismantling have been progressed steadily as well. Meanwhile, FUGEN has affiliations with local industries and universities for collaboration research, and has exchanged the decommissioning information with domestic and overseas organizations continuously. (author)

  4. Decommissioning and jobs

    International Nuclear Information System (INIS)

    One aspect of the decommissioning web is its effect on socioeconomics, particularly jobs. What will reactor retirement mean to jobs, especially in rural communities where power plant operations may be the most reliable and dominant source of direct and indirect employment in the area? The problems which any plant closure produces for job security are generally understood, but the decommissioning of nuclear power plants is different because of the residual radioactivity and because of the greater isolation of the power plant sites. For example, what will be the specific employment effects of several possible decommissioning scenarios such as immediate dismantlement and delayed dismantlement? The varying effects of decommissioning on jobs is discussed. It is concluded that the decommissioning of nuclear power plants in some areas such as Wales could bring benefits to the surrounding communities. (author)

  5. International Decommissioning Strategies

    International Nuclear Information System (INIS)

    The IAEA has been developing guidance and technical information relating to the decommissioning and decommissioning strategies of nuclear facilities for over 20 years. During this time, the international concept of decommissioning strategies, and its importance, has changed. Three basic decommissioning strategies are envisaged as possibilities for nuclear installations: immediate dismantling, deferred dismantling and entombment. All have advantages and disadvantages, but the International Conference on Safe Decommissioning for Nuclear Activities demonstrated that immediate dismantling is the generally preferred option. However, there are a number of factors that might lead operators to choose one of the other strategies, and each situation has to be examined individually to identify the optimal strategy for that situation. The basic approach of these three strategies is discussed in the paper. (author)

  6. Decommissioning project management: The Japan power demonstration reactor decommissioning program

    International Nuclear Information System (INIS)

    The Japan power demonstration reactor (JPDR) decommissioning program is in progress of developing new technology for reactor decommissioning and collecting various data on project management and performance of developed dismantling devices. The experience and the data obtained from the JPDR decommissioning program are expected to contribute to future decommissioning of commercial nuclear power plants. (author). 8 refs, 9 figs, 3 tabs

  7. Nuclear decommissioning: Funding arrangements

    International Nuclear Information System (INIS)

    This statement describes the United Kingdom's approach to funding civil nuclear decommissioning activities and explain proposed changes to the current arrangements. The UK has nuclear operators both in the private and public sectors and the approach to decommissioning funding differs. British Energy (BE), which operates a fleet of AGR power stations and a PWR, is in the private sector. On privatization, a segregated fund was established to cover BE's future decommissioning costs. Money paid into the fund is invested and the accumulated assets used to meet future decommissioning and cleanup costs. The precise amount of money that will be required to cover decommissioning costs is not an exact science. That is why the performance of the segregated fund is reviewed at five yearly intervals, at which stage BE's annual contribution can be adjusted as appropriate. To ensure that the fund is managed effectively and investments are made wisely, the fund is managed by independent trustees jointly appointed by the Government and the company. So far, the fund is performing as expected and it is on target to cover BE's decommissioning costs. Operators in the public sector include British Nuclear Fuels Limited (BNFL) and the United Kingdom Atomic Energy Authority (UKAEA). BNFL operates the fleet of Magnox power stations, a number of which are in various stages of decommissioning. BNFL also operates Sellafield (reprocessing, MOX and other operations) and Springfields (fuel manufacture). UKAEA is responsible for decommissioning the UK's former research reactor sites at Dounreay, Windscale (Cumbria), Harwell and Winfrith (Dorset). Under current arrangements, taxpayers meet the cost of decommissioning and cleanup at UKAEA sites; taxpayers will also meet the costs associated with the decommissioning of Magnox power stations from 2008 onwards

  8. Decommissioning of Olkiluoto power plant

    International Nuclear Information System (INIS)

    A conceptual plan for decommissioning of Olkiluoto Power Plant is presented. Deferred dismantlement after a safe storage period of 30 years is regarded as the main alternative. The sequence of decommissioning tasks and the techniques for performing them are described, including the management and disposal of decommissioning wastes. Occupational and public radiation dose estimates are given. Manpower requirements and costs of decommissioning are evaluated

  9. Research reactor decommissioning

    International Nuclear Information System (INIS)

    Full text: Of the ∼ 800 research reactors constructed worldwide to date, ∼50% have been shut down and are at various stages of decommissioning. Many reached the end of their design lives or were shut down due to strategic, economic or regulatory considerations. 27% of those in operation are over 40 years old and will need to be decommissioned soon. Decommissioning normally takes the facility permanently out of service and subjects it to progressive hazard reduction, dismantling and decontamination in a safe, secure economically viable way, using best practicable means to meet the best practicable environmental option, such that the risks and doses to workers and the general public are maintained as low as reasonably practicable. Whilst most decommissioning techniques are well established there are still some challenging and important issues that need resolution. Perhaps the most challenging issue is radioactive waste management and storage. It is vitally important that all local and national waste classification, transportation, storage and end point requirements are known, as the adopted strategy will be heavily influenced by these factors. Other equally important but softer issues include the requirement for early decommissioning plans, adequate funding/cost estimates and the involvement of all relevant stakeholders. A comprehensive decommissioning plan should be produced up front that encompasses an early radiological characterisation survey of the facility/site. An appropriate funding mechanism needs to be assured. Whilst regular revisions of the decommissioning cost study should help to determine required funds, it is important to validate these cost estimates by benchmarking other decommissioning projects and accumulated experience. The use of appropriate 'stakeholder dialogue' methods by the facility operator to inform and communicate with all interested parties, such as government and non-government organisations, regulators, trades unions, anti-nuclear groups, local activists and the general public should ideally start before decommissioning commences and continue throughout the project. (author)

  10. Sterilisation: the Aberdeen experience, and some broader implications.

    Science.gov (United States)

    Teper, S

    1978-01-01

    In her paper, Sue Teper outlines the various methods of contraception or fertility control and their relationship to sterilisation. She also considers a particular group of women in Aberdeen as a mini case-study. From these two aspects of sterilization develops a third--that of broader medical and economic issues. Sterilisation usually concerns patients who are free from illness, therefore the attitudes of medical personnel are much more relevant to whether or not the operation is performed on request purely as a means of fertility control, rather than for medical reasons where the patient may be at risk were a pregnancy to occur. Ms Teper calls for medical staff in this instance to clarify their own attitudes in decisions which involve surgical skills and healthy patients. PMID:633306

  11. Geophysical study of the Building 103 Dump, Aberdeen Proving Ground

    Energy Technology Data Exchange (ETDEWEB)

    McGinnis, L.D.; Miller, S.F.; Thompson, M.D.; McGinnis, M.G.

    1992-12-01

    The Building 103 Dump is one of ten potentially contaminated sites in the Canal Creek and Westwood areas of the Edgewood section of Aberdeen Proving Ground examined by a geophysical team from Argonne National Laboratory in April and May of 1992. Noninvasive geophysical surveys, including magnetics, resistivity, ground-penetrating radar, and seismic refraction, were conducted. These surveys indicate that much of the area is free of debris. However, prominent magnetic and resistivity anomalies occur along well-defined lineaments, suggestive of a dendritic stream pattern. Prior to the onset of dumping, the site was described as a ``sand pit,`` which suggests that headward erosion of Canal Creek tributaries cut into the surficial aquifer. Contaminants dumped into the landfill would have direct access to the surficial aquifer and thus to Canal Creek. Seismic refraction profiling indicates 6--12 ft of fill material now rests on the former land surface. Only the northern third of the former landfill was geophysically surveyed.

  12. Safety Assessment for Decommissioning

    International Nuclear Information System (INIS)

    In the past few decades, international guidance has been developed on methods for assessing the safety of predisposal and disposal facilities for radioactive waste. More recently, it has been recognized that there is also a need for specific guidance on safety assessment in the context of decommissioning nuclear facilities. The importance of safety during decommissioning was highlighted at the International Conference on Safe Decommissioning for Nuclear Activities held in Berlin in 2002 and at the First Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management in 2003. At its June 2004 meeting, the Board of Governors of the IAEA approved the International Action Plan on Decommissioning of Nuclear Facilities (GOV/2004/40), which called on the IAEA to: ''establish a forum for the sharing and exchange of national information and experience on the application of safety assessment in the context of decommissioning and provide a means to convey this information to other interested parties, also drawing on the work of other international organizations in this area''. In response, in November 2004, the IAEA launched the international project Evaluation and Demonstration of Safety for Decommissioning of Facilities Using Radioactive Material (DeSa) with the following objectives: -To develop a harmonized approach to safety assessment and to define the elements of safety assessment for decommissioning, including the application of a graded approach; -To investigate the practical applicability of the methodology and performance of safety assessments for the decommissioning of various types of facility through a selected number of test cases; -To investigate approaches for the review of safety assessments for decommissioning activities and the development of a regulatory approach for reviewing safety assessments for decommissioning activities and as a basis for regulatory decision making; -To provide a forum for exchange of experience in evaluation and demonstration of safety during decommissioning of various types of facility using radioactive material. This book presents the outcomes of the work carried out in fulfilling the action plan through the DeSa project (November 2004-November 2007); it contains a summary of the whole project and a methodology for the safety assessment of the decommissioning of facilities using radioactive material. It is supported by technical reports provided in the annexes.

  13. Decommissioning: an insurance perspective

    International Nuclear Information System (INIS)

    The nuclear insurance pools, through American Nuclear Insurers (ANI) and the Mutual Atomic Energy Liability Underwriters (MAELU), have been providing third-party nuclear liability insurance to the nuclear industry since 1957. Third-party liability and property damage coverage resulting from the nuclear hazard are provided by separate insurance policies issued by the nuclear insurance pools. A liability insurer's view of decommissioning is addressed by discussing the following: insurer's perspective of potential nuclear liability; insurance claim experience and trends; objectives and accomplishments of ANI/MAELU's involvement with facility decommissioning; and important nuclear liability considerations for facility decommissioning

  14. Decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Nuclear facilities present a number of problems at the end of their working lives. They require dismantling and removal but public and environmental protection remain a priority. The principles and strategies are outlined. Experience of decommissioning in France and the U.K. had touched every major stage of the fuel cycle by the early 1990's. Decommissioning projects attempt to restrict waste production and proliferation as waste treatment and disposal are costly. It is concluded that technical means exist to deal with present civil plant and costs are now predictable. Strategies for decommissioning and future financial provisions are important. (UK)

  15. Decommissioning waste processing system

    International Nuclear Information System (INIS)

    Many commercial nuclear reactor, which have been in operation since the early 1970's, will be decommissioned after the year 2000 in Japan. This paper reports that it is essential to establish a decommissioning waste processing system for a great deal of waste generated from decommissioned commercial nuclear reactors in the 21 century. The competent minister for the decommissioning of commercial nuclear reactor is Ministry of International Trade and Industry (Law for Regulation of Nuclear Source Material, Nuclear Fuel Material and Atomic Reactor, Article 38). Licensing termination and unrestricted release criteria are not yet mentioned in Japanese regulation. Safety evaluation of the Low Level Waste (LLW) repository, which will be constructed in Rokkashomura, Aomori Pref. is underway

  16. Decommissioning - A regulatory view

    International Nuclear Information System (INIS)

    Decommissioning is the final stage in the life of a facility and is regulated in a similar manner to the operational phase. The nuclear regulatory regime is described including the new regulations on Environmental Impact Assessment for reactors. The Health and Safety Executive has recently issued guidance to its inspectors on the regulation of facilities being decommissioned. A number of aspects of this guidance are discussed including strategies, timetables, safety cases, management and organisation and finally de-licensing. (authors)

  17. Decommissioning and Decontamination

    International Nuclear Information System (INIS)

    The objectives of SCK-CEN's decommissioning and decontamination programme are (1) to develop, test and optimise the technologies and procedures for decommissioning and decontamination of nuclear installations in order to minimise the waste arising and the distributed dose; (2) to optimise the environmental impact; (3) to reduce the cost of the end-of-life of the installation; (4) to make these new techniques available to the industry; (5) to share skills and competences. The programme and achievements in 1999 are summarised

  18. Decommissioning Russian Research Facilities

    International Nuclear Information System (INIS)

    Gosatomnadzor of Russia is conducting the safety regulation and inspection activity related to nuclear and radiation safety of nuclear research facilities (RR), including research reactors, critical assemblies and sub-critical assemblies. Most of the Russian RR were built and put in operation more than 30 years ago. The problems of ageing equipment and strengthening of safety requirements in time, the lack of further experimental programmes and financial resources, have created a condition when some of the RR were forced to take decisions on their decommissioning. The result of these problems was reflected in reducing the number of RR from 113 in 1998 to 81 in the current year. At present, seven RR are already under decommissioning or pending it. Last year, the Ministry of Atomic Energy took the decision to finally shut down two remaining actual research reactors in the Physics and Power Engineering Institute in Obninsk: AM-1, the first reactor in the world built for peaceful purposes, graphite-type reactor, and the fast liquid metal reactor BR-10, and to start their preparation for decommissioning. It is not enough just to declare the decommissioning of a RR: it is also vital to find financial resources for that purpose. For this reason, due to lack of financing, the MR reactor at the Kurchatov Institute has been pending decommissioning since 1992 and still is. The other example of long-lasting decommissioning is TVR, a heavy water reactor at the Institute of Theoretical Physics in Moscow (ITEF). The reason is also poor financing. Another example discussed in the paper concerns on-site disposal of a RR located above the Arctic Pole Circle, owned by the Norilsk Mining Company. Furthermore, the experience of the plutonium reactor decommissioning at the Joint Institute of Nuclear Research is also discussed. As shown, the Russian Federation has had good experiences in the decommissioning of nuclear research facilities. (author)

  19. Magnitude of the decommissioning task in Europe

    International Nuclear Information System (INIS)

    The paper deals with the current and future decommissioning of nuclear facilities in Europe, excluding the Commonwealth of Independent States. The following topics are addressed in detail: current decommissioning projects; decommissioning strategies; future decommissioning projects; and conclusions. (author)

  20. The decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    This file includes five parts: the first part is devoted to the strategies of the different operators and includes the following files: the decommissioning of nuclear facilities Asn point of view, decommissioning of secret nuclear facilities, decommissioning at the civil Cea strategy and programs, EDF de-construction strategy, Areva strategy for decommissioning of nuclear facilities; the second one concerns the stakes of dismantling and includes the articles as follow: complete cleanup of buildings structures in nuclear facilities, decommissioning of nuclear facilities and safety assessment, decommissioning wastes management issues, securing the financing of long-term decommissioning and waste management costs, organizational and human factors in decommissioning projects, training for the decommissioning professions: the example of the Grenoble University master degree; the third part is devoted to the management of dismantling work sites and includes the different articles as follow: decommissioning progress at S.I.C.N. plant, example of decommissioning work site in Cea Grenoble: Siloette reactor decommissioning, matters related to decommissioning sites, decommissioning of french nuclear installations: the viewpoint of a specialist company, specificities of inspections during decommissioning: the Asn inspector point of view; the fourth part is in relation with the international approach and includes as follow: IAEA role in establishing a global safety regime on decommissioning, towards harmonization of nuclear safety practices in Europe: W.E.N.R.A. and the decommissioning of nuclear facilities, EPA superfund program policy for decontamination and decommissioning, progress with remediation at Sellafield, progress and experiences from the decommissioning of the Eurochemic reprocessing plant in Belgium, activities of I.R.S.N. and its daughter company Risk-audit I.r.s.n./G.r.s. international in the field of decommissioning of nuclear facilities in eastern countries,; the fifth part presents the external points of view on dismantling with: the decommissioning of Saint-Laurent A, as seen by the local information committee, decommissioning: the urge for a public consultation, an evaluation of the work of the 'conseil superieur de la surete et de linformation nucleaire' (C.S.S.I.N.) - a consultative body dealing with information in the field of nuclear safety) on the issue of decommissioning basic nuclear installations, monitoring the decommissioning of nuclear facilities and examining applications. (N.C.)

  1. Decommissioning plan - decommissioning project for KRR 1 and 2 (revised)

    Energy Technology Data Exchange (ETDEWEB)

    Jung, K. J.; Paik, S. T.; Chung, U. S.; Jung, K. H.; Park, S. K.; Lee, D. G.; Kim, H. R.; Kim, J. K.; Yang, S. H.; Lee, B. J

    2000-10-01

    This report is the revised Decommissioning Plan for the license of TRIGA research reactor decommissioning project according to Atomic Energy Act No. 31 and No. 36. The decommissioning plan includes the TRIGA reactor facilities, project management, decommissioning method, decontamination and dismantling activity, treatment, packaging, transportation and disposal of radioactive wastes. the report also explained the radiation protection plan and radiation safety management during the decommissioning period, and expressed the quality assurance system during the period and the site restoration after decommissioning. The first decommissioning plan was made by Hyundai Engineering Co, who is the design service company, was submitted to the Ministry of Science and Technology, and then was reviewed by the Korea Institute of Nuclear Safety. The first decommissioning plan was revised including answers for the questions arising from review process.

  2. Decommissioning plan - decommissioning project for KRR 1 and 2 (revised)

    International Nuclear Information System (INIS)

    This report is the revised Decommissioning Plan for the license of TRIGA research reactor decommissioning project according to Atomic Energy Act No. 31 and No. 36. The decommissioning plan includes the TRIGA reactor facilities, project management, decommissioning method, decontamination and dismantling activity, treatment, packaging, transportation and disposal of radioactive wastes. the report also explained the radiation protection plan and radiation safety management during the decommissioning period, and expressed the quality assurance system during the period and the site restoration after decommissioning. The first decommissioning plan was made by Hyundai Engineering Co, who is the design service company, was submitted to the Ministry of Science and Technology, and then was reviewed by the Korea Institute of Nuclear Safety. The first decommissioning plan was revised including answers for the questions arising from review process

  3. Shippingport decommissioning nears completion

    International Nuclear Information System (INIS)

    GE Nuclear Energy's Advanced Nuclear Technology Operation's Decommissioning Service Group is decommissioning Shippingport (PWR, 90 MWe), the world's first commercial nuclear power plant. This key project is the first entire decommissioning of a large, commercial-size nuclear power plant in the world, and is being completed safely and cost effectively using existing dismantling practices. The Shippingport Decommissioning Project has consisted of two distinct phases: a surveillance, maintenance and operation phase, and a decommissioning phase. The former, also known as the caretaker phase, was completed by the end of 1984. Following a detailed operational preparatory review, decommissioning began during September 1985. Non-fuel-bearing irradiated core components were removed from the fuel-handling canal and placed into the reactor pressure vessel. The water level was then lowered to allow the drainage of water from the reactor coolant system pipes and components. At the same time, the electrical system was shut down, asbestos was removed, external surfaces were decontaminated, and the systems were drained. During 1987, all reactor coolant system pipes and components were removed. Early in 1988, the reactor pressure vessel and neutron shield tank (RPV/NST) was shielded and prepared for one-piece removal. The removal of the fuel-handling canal and non-radioactive concrete and structures is now well advanced. At present there are no major technical issues remaining. The project is expected to be completed with less than 200 man-rem exposure which is one-fifth of the radiation exposure than the US Department of Energy has estimated for the decommissioning. 3 figs

  4. Decommissioning in western Europe

    International Nuclear Information System (INIS)

    This report gives an overview of the situation in Western Europe. The original aim was to focus on organisational and human issues with regard to nuclear reactor decommissioning, but very few articles were found. This is in sharp contrast to the substantial literature on technical issues. While most of the reports on decommissioning have a technical focus, several provide information on regulatory issues, strategies and 'state of the art'. The importance of the human and organizational perspective is however discovered, when reading between the lines of the technical publications, and especially when project managers summarize lessons learned. The results are to a large extent based on studies of articles and reports, mainly collected from the INIS database. Decommissioning of nuclear facilities started already in the sixties, but then mainly research and experimental facilities were concerned. Until now about 70 reactors have been shutdown world-wide. Over the years there have been plenty of conferences for exchanging experiences mostly about technical matters. Waste Management is a big issue. In the 2000s there will be a wave of decommissioning when an increasing amount of reactors will reach the end of their calculated lifetime (40 years, a figure now being challenged by both life-extension and pre-shutdown projects). Several reactors have been shut-down for economical reasons. Shutdown and decommissioning is however not identical. A long period of time can sometimes pass before an owner decides to decommission and dismantle a facility. The conditions will also differ depending on the strategy, 'immediate dismantling' or 'safe enclosure'. If immediate dismantling is chosen the site can reach 'green-field status' in less than ten years. 'Safe enclosure', however, seems to be the most common strategy. There are several pathways, but in general a safe store is constructed, enabling the active parts to remain in safe and waterproof conditions for a longer period of time (sometimes hundred years or more), prior to final demolition. Among the reasons for deferring the dismantling are lack of waste repositories and decreasing dose-rates for the workers. Of Europe's 218 commercial reactors in operation, the majority, 151, are located i the Western part. The biggest producers are France, United Kingdom and Germany, with 58, 35 and 20 reactors respectively. Until now mostly research- and pilot reactors have been shut-down. There are yet few experiences from decommissioning of large-scale commercial reactors. The following commercial reactors are undergoing decommissioning. (There are also a great amount of nuclear facilities of other types being decommissioned.) The three gas-cooled twin reactor plants of Berkeley, Trawsfynydd and Hunterston in UK. In Germany Gundremmingen, Lingen, Kahl and Wuergassen are being decommissioned. All of them are located in the Western part of the country. The biggest project is however the dismantling of the gigantic Greifswald facility situated on the coast of the Baltic see in former Eastern Germany. The plant has eight Russian built reactors of VVER-type. Like the rest of the former GDR-plants Greifswald was shutdown after the reunification in 1990. The strategy chosen is immediate dismantling. France is decommissioning seven reactors (Chooz A1, Chinon A1, A2, A3, St Laurent A1, A2 and Bugey 1.) The oldest, Chinon A1, closed down in 1973 and the youngest, Bugey 1, in 1994. Italy closed down all NPPs (altogether four) in 1987 after a referendum. The first reactor of the Netherlands was shutdown in 1997 mainly for economical reasons. The development of a free European electricity market will make it less profitable to run certain facilities. Vandelos 1 in Spain is undergoing decommissioning after a fire in the turbines in 1989. IAEA, OECD/NEA and EU are co-operating in the field of decommissioning. Much work is spent on harmonizing rules and preparing international guidelines. The international agencies now consider decommissioning of nuclear facilities to be technically unproblematic. Decommissioning is entering a mature stage when procedures are to be standardized and common guidelines to be developed. A competitive 'decommissioning market' is to be created including specialized suppliers and contractors. Decommissioning partly demands other competencies than operation. Key issues to be dealt with are management of change, responsibility when appointing contractors, keeping up the work motivation and morale of the staff, retention of key-competencies, and transfer of 'organisational memory'. The interest has until now been focused on technical issues of decommissioning. To be prepared for the coming wave of decommissioning, when the world's large-scale commercial reactors are closing down, international research on human and organisational issues has to be established. Better understanding of the link to technology and business strategies must also be gained in order to manage the process of decommissioning safely and efficiently

  5. Financial aspects of decommissioning

    International Nuclear Information System (INIS)

    European Commission adopted recently two proposals of Directives designed to pave the way for a Community approach to the safety of nuclear power plants and the processing of radioactive waste. Nuclear safety cannot be guaranteed without making available adequate financial resources. With regard, in particular, to the decommissioning of nuclear facilities, the Directive defines the Community rules for the establishment, management and use of decommissioning funds allocated to a body with legal personality separate from that of the nuclear operator. In order to comply with the acquis communautaire, Romanian Government issued the Emergency Ordinance no. 11/2003 which set up the National Agency for Radioactive Waste (ANDRAD) and soon will be established the financial mechanism for raising the necessary funds. Societatea Nationala 'Nuclearelectrica' S.A. operates, through one of its branches, Cernavoda NPP Unit 1 and has to prepare its decommissioning strategy and to analyze the options to assure the financing for covering the future costs. The purpose of this paper is to clarify the financial systems' mechanisms to the satisfaction of the nuclear operator obligations, according to the disbursement schedule foreseen by decommissioning projects . The availability of cash to pay for all the decommissioning expenditure must be foreseen by setting up assets and establishing a suitable financing plan. The different practices of assets management shall be presented in this paper on the basis of the international experience. Some calculation samples shall be given as an illustration. (author)

  6. Decommissioning strategy selection

    International Nuclear Information System (INIS)

    At the end of their useful life nuclear facilities have to be decommissioned. The strategy selection on how to decommission a facility is a highly important decision at the very beginning of decommissioning planning. Basically, a facility may be subject to (a) immediate dismantling; (b) deferred dismantling after a period of ''safe enclosure'' or (c) entombment where a facility is turned into a near surface disposal facility. The first two strategies are normally applied. The third one may be accepted in countries without significant nuclear activities and hence without disposal facilities for radioactive waste. A large number of factors has to be taken into account when a decision on the decommissioning strategy is being made. Many of the factors cannot be quantified. They may be qualitative or subject to public opinion which may change with time. At present, a trend can be observed towards immediate dismantling of nuclear facilities, mainly because it is associated with less uncertainty, less local impact, a better public acceptance, and the availability of operational expertise and know how. A detailed evaluation of the various factors relevant to strategy selection and a few examples showing the situation regarding decommissioning strategy in a number of selected countries are presented in the following article. (orig.)

  7. Factors Impacting Decommissioning Costs - 13576

    International Nuclear Information System (INIS)

    The Electric Power Research Institute (EPRI) studied United States experience with decommissioning cost estimates and the factors that impact the actual cost of decommissioning projects. This study gathered available estimated and actual decommissioning costs from eight nuclear power plants in the United States to understand the major components of decommissioning costs. Major costs categories for decommissioning a nuclear power plant are removal costs, radioactive waste costs, staffing costs, and other costs. The technical factors that impact the costs were analyzed based on the plants' decommissioning experiences. Detailed cost breakdowns by major projects and other cost categories from actual power plant decommissioning experiences will be presented. Such information will be useful in planning future decommissioning and designing new plants. (authors)

  8. Factors Impacting Decommissioning Costs - 13576

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Karen; McGrath, Richard [Electric Power Research Institute, 3420 Hillview Ave., Palo Alto, California (United States)

    2013-07-01

    The Electric Power Research Institute (EPRI) studied United States experience with decommissioning cost estimates and the factors that impact the actual cost of decommissioning projects. This study gathered available estimated and actual decommissioning costs from eight nuclear power plants in the United States to understand the major components of decommissioning costs. Major costs categories for decommissioning a nuclear power plant are removal costs, radioactive waste costs, staffing costs, and other costs. The technical factors that impact the costs were analyzed based on the plants' decommissioning experiences. Detailed cost breakdowns by major projects and other cost categories from actual power plant decommissioning experiences will be presented. Such information will be useful in planning future decommissioning and designing new plants. (authors)

  9. Decommissioning of Fort St. Vrain

    International Nuclear Information System (INIS)

    The Fort St. Vrain Nuclear Generating Station Decommissioning is rapidly reaching completion. This paper discusses the methods and techniques applied that made the project a technical, scheduler, and safety success and that demonstrates the practicality of commercial nuclear reactor decommissioning

  10. About decommissioning of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Brosche, Dieter [Bayernwerk AG, Muenchen (Germany); Klein, K. [Badenwerk AG, Kalrsruhe (Germany); Vollradt, Juergen [Vereinigte Elektrizitaetswerke Westfalen AG, Dortmund (Germany)

    2015-10-15

    The IAEA organised an International Symposium in 1978, which dealt with the main aspects of decommissioning nuclear plants. Sufficient practical experiences and elaborated decommissioning concepts and techniques are already available. Unsolvable problems or only solvable with tremendous efforts of time and expenses are according to the opinion of experts not to be expected. Important statements concern above all the dose load of the decommissioning staff and the costs for decommissioning.

  11. Decommissioning funding: ethics, implementation, uncertainties

    International Nuclear Information System (INIS)

    This status report on Decommissioning Funding: Ethics, Implementation, Uncertainties also draws on the experience of the NEA Working Party on Decommissioning and Dismantling (WPDD). The report offers, in a concise form, an overview of relevant considerations on decommissioning funding mechanisms with regard to ethics, implementation and uncertainties. Underlying ethical principles found in international agreements are identified, and factors influencing the accumulation and management of funds for decommissioning nuclear facilities are discussed together with the main sources of uncertainties of funding systems. (authors)

  12. Bioeconomic model and selection indices in Aberdeen Angus cattle.

    Science.gov (United States)

    Campos, G S; Braccini Neto, J; Oaigen, R P; Cardoso, F F; Cobuci, J A; Kern, E L; Campos, L T; Bertoli, C D; McManus, C M

    2014-08-01

    A bioeconomic model was developed to calculate economic values for biological traits in full-cycle production systems and propose selection indices based on selection criteria used in the Brazilian Aberdeen Angus genetic breeding programme (PROMEBO). To assess the impact of changes in the performance of the traits on the profit of the production system, the initial values ​​of the traits were increased by 1%. The economic values for number of calves weaned (NCW) and slaughter weight (SW) were, respectively, R$ 6.65 and R$ 1.43/cow/year. The selection index at weaning showed a 44.77% emphasis on body weight, 14.24% for conformation, 30.36% for early maturing and 10.63% for muscle development. The eighteen-month index showed emphasis of 77.61% for body weight, 4.99% for conformation, 11.09% for early maturing, 6.10% for muscle development and 0.22% for scrotal circumference. NCW showed highest economic impact, and SW had important positive effect on the economics of the production system. The selection index proposed can be used by breeders and should contribute to greater profitability. PMID:24438200

  13. Environmental geophysics, offshore Bush River Peninsula, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Miller, S.F.; Kuecher, G.J.; Davies, B.E. [and others

    1995-11-01

    Geophysical studies in shallow waters adjacent to the Bush River Peninsula, Edgewood Area of Aberdeen Proving Ground, Maryland, have delineated the extent of waste disposal sites and established a hydrogeologic framework, which may control contaminant transport offshore. These studies indicate that during the Pleistocene Epoch, alternating stands of high and low sea levels resulted in a complex pattern of shallow channel-fill deposits around the Bush River Peninsula. Ground-penetrating radar studies reveal paleochannels greater than 50 ft deep. Some of the paleochannels are also imaged with marine seismic reflection. Conductivity highs measured with the EM-31 are also indicative of paleochannels. This paleochannel depositional system is environmentally significant because it may control the shallow groundwater flow regime beneath the peninsula. Magnetic, conductivity, and side-scan sonar anomalies outline anthropogenic anomalies in the study area. On the basis of geophysical data, underwater anthropogenic materials do exist in some isolated areas, but large-scale offshore dumping has not occurred in the area studied.

  14. Environmental geophysics at Beach Point, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    McGinnis, L.D.; Daudt, C.R.; Thompson, M.D.; Miller, S.F. [Argonne National Lab., IL (United States). Reclamation Engineering and Geosciences Section; Mandell, W.A. [Jacobs Engineering Group, Inc., Washington, DC (United States); Wrobel, J. [Dept. of Defense, Aberdeen Proving Ground, MD (United States)

    1994-07-01

    Geophysical studies at Beach Point Peninsula, in the Edgewood area of Aberdeen Proving Ground, Maryland, provide diagnostic signatures of the hydrogeologic framework and possible contaminant pathways. These studies permit construction of the most reasonable scenario linking dense, nonaqueous-phase liquid contaminants introduced at the surface with their pathway through the surficial aquifer. Subsurface geology and contaminant presence were identified by drilling, outcrop mapping, and groundwater sampling and analyses. Suspected sources of near-surface contaminants were defined by magnetic and conductivity measurements. Negative conductivity anomalies may be associated with unlined trenches. Positive magnetic and conductivity anomalies outline suspected tanks and pipes. The anomalies of greatest concern are those spatially associated with a concrete slab that formerly supported a mobile clothing impregnating plant. Resistivity and conductivity profiling and depth soundings were used to identify an electrical anomaly extending through the surficial aquifer to the basal pleistocene unconformity, which was mapped by using seismic reflection methods. The anomaly may be representative of a contaminant plume connected to surficial sources. Major activities in the area included liquid rocket fuel tests, rocket fuel fire suppression tests, pyrotechnic material and smoke generator tests, and the use of solvents at a mobile clothing impregnating plant.

  15. Depleted uranium risk assessment at Aberdeen Proving Ground

    International Nuclear Information System (INIS)

    The Environmental Science Group at Los Alamos and the Test and Evaluation Command (TECOM) are assessing the risk of depleted uranium (DU) testing at Aberdeen Proving Ground (APG). Conceptual and mathematical models of DU transfer through the APG ecosystem have been developed in order to show the mechanisms by which DU migrates or remains unavailable to different flora and fauna and to humans. The models incorporate actual rates of DU transfer between different ecosystem components as much as possible. Availability of data on DU transport through different pathways is scarce and constrains some of the transfer rates that can be used. Estimates of transfer rates were derived from literature sources and used in the mass-transfer models when actual transfer rates were unavailable. Objectives for this risk assessment are (1) to assess if DU transports away from impact areas; (2) to estimate how much, if any, DU migrates into Chesapeake Bay; (3) to determine if there are appreciable risks to the ecosystems due to DU testing; (4) to estimate the risk to human health as a result of DU testing

  16. An air quality survey and emissions inventory at Aberdeen Harbour

    Science.gov (United States)

    Marr, I. L.; Rosser, D. P.; Meneses, C. A.

    A network of 10 stations, with passive sampling for VOCs (including benzene), NO 2, and SO 2, over 2-week periods, grab sampling for CO, and 48-h pumped sampling for PM 10, was set up to make an air quality survey for 12 months around Aberdeen Harbour. Benzene, CO, SO 2 and PM 10 were always well below the AQS target values. However, NO 2 frequently showed a pronounced gradient across the harbour reaching its highest concentrations at the city end, indicating that the road traffic was the principal source of the pollution. This was backed up by the predominance of aromatics in the VOCs in the city centre, derived from petrol engined vehicles, compared to the predominance of alkanes and alkenes around the docks, derived from diesel engined heavy trucks and possibly ships. Black carbon on the PM 10 filters also showed a gradient with highest levels in the city centre. It is proposed that for such surveys in future, NO 2 and black carbon would be the two most informative parameters. This emissions inventory has shown first, that trucks contribute very little to the total, and second, that the ro-ro ferries are the major contributors as they burn light fuel oil while the oil platform supply vessels burn low-sulphur marine gas oil with around 0.1% S. When the whole picture of the emissions from the city is considered, the emissions from the harbour constitute only a small part.

  17. Shippingport Station Decommissioning Project

    International Nuclear Information System (INIS)

    The Shippingport Atomic Power Station was located on the Ohio River in Shippingport Borough (Beaver County), Pennsylvania, USA. The US Atomic Energy Commission (AEC) constructed the plant in the mid-1950s on a seven and half acre parcel of land leased from Duquesne Light Company (DLC). The purposes were to demonstrate and to develop Pressurized Water Recovery technology and to generate electricity. DLC operated the Shippingport plant under supervision of (the successor to AEC) the Department of Energy (DOE)-Naval Reactors (NR) until operations were terminated on October 1, 1982. NR concluded end-of-life testing and defueling in 1984 and transferred the Station's responsibility to DOE Richland Operations Office (RL), Surplus Facility Management Program Office (SFMPO5) on September 5, 1984. SFMPO subsequently established the Shippingport Station Decommissioning Project and selected General Electric (GE) as the Decommissioning Operations Contractor. This report is intended to provide an overview of the Shippingport Station Decommissioning Project

  18. Site decommissioning management plan

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff's strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites

  19. Site decommissioning management plan

    Energy Technology Data Exchange (ETDEWEB)

    Fauver, D.N.; Austin, J.H.; Johnson, T.C.; Weber, M.F.; Cardile, F.P.; Martin, D.E.; Caniano, R.J.; Kinneman, J.D.

    1993-10-01

    The Nuclear Regulatory Commission (NRC) staff has identified 48 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC staff`s strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 48 sites and describes the status of decommissioning activities at the sites.

  20. Tunney's Pasture decommissioning project

    International Nuclear Information System (INIS)

    AECL's Tunney's Pasture facility located in Ottawa was used for research, production and worldwide shipping of radioisotopes. After 30 years of operation, it was shut down in 1984, and decommissioned in two phases. During the first phase, which began in 1985 and lasted until 1987, staff moving to the new Kanata facility, now the property of Nordion International, removed the bulk of the equipment. After a three year period of storage under surveillance, AECL in 1990 initiated the second phase of decommissioning, which was completed in August 1993. In January 1994, the AECB unconditionally released the facility for unrestricted use. The paper provides an overview of the second phase of decommissioning, and a summary of a few lessons learned. 4 figs

  1. Decommissioning licensing procedure

    International Nuclear Information System (INIS)

    Decommissioning or closure of a nuclear power plant, defined as the fact that takes place from the moment that the plant stops producing for the purpose it was built, is causing preocupation. So this specialist meeting on Regulatory Review seems to be the right place for presenting and discusing the need of considering the decommissioning in the safety analysis report. The main goal of this paper related to the licensing procedure is to suggest the need of a new chapter in the Preliminary Safety Analysis Report (P.S.A.R.) dealing with the decommissioning of the nuclear power plant. Therefore, after a brief introduction the problem is exposed from the point of view of nuclear safety and finally a format of the new chapter is proposed. (author)

  2. Preparation for Ignalina NPP decommissioning

    International Nuclear Information System (INIS)

    Latest developments of atomic energy in Lithuania, works done to prepare Ignalina NPP for final shutdown and decommissioning are described. Information on decommissioning program for Ignalina NPP unit 1, decommissioning method, stages and funding is presented. Other topics: radiation protection, radioactive waste management and disposal. Key facts related to nuclear energy in Lithuania are listed

  3. Decommissioning with diamond

    International Nuclear Information System (INIS)

    The decommissioning of the Windscale Advanced Gas-cooled Reactor is discussed. The decommissioning is carried out to stage 3, when the reactor core, including the thick reinforced concrete bioshield, is demolished. In particular, the use of diamond sawing and stitch-drilling in the demolition is discussed. New techniques have had to be developed and experiments made as to the best tools to tackle the problems. The problem of the thickness of the reinforced concrete can be overcome by diamond wire-sawing. The other main problem is contamination and activation of the materials used to build the reactors. (U.K.)

  4. Vinca nuclear decommissioning program

    International Nuclear Information System (INIS)

    In this paper a preliminary program for the nuclear decommissioning in The Vinca Institute of Nuclear Sciences is presented. Proposed Projects and Activities, planned to be done in the next 10 years within the frames of the Program, should improve nuclear and radiation safety and should solve the main problems that have arisen in the previous period. Project of removal of irradiated spent nuclear fuel from the RA reactor, as a first step in all possible decommissioning strategies and the main activity in the first two-three years of the Program realization, is considered in more details. (author)

  5. Decommissioning and Decontamination

    Energy Technology Data Exchange (ETDEWEB)

    Massaut, V

    2000-07-01

    The objectives of SCK-CEN's decommissioning and decontamination programme are (1) to develop, test and optimise the technologies and procedures for decommissioning and decontamination of nuclear installations in order to minimise the waste arising and the distributed dose; (2) to optimise the environmental impact; (3) to reduce the cost of the end-of-life of the installation; (4) to make these new techniques available to the industry; (5) to share skills and competences. The programme and achievements in 1999 are summarised.

  6. Decommissioning of IFEC

    International Nuclear Information System (INIS)

    The IFEC nuclear fuel fabrication plant operated in Italy for more then thirty years and has now been successfully decommissioned. The rules and regulations relating to Quality Assurance established during the fabrication of Cirene reactor fuel have been adhered to during the decommissioning phase. The use of personnel with large experience in the nuclear field has resulted in vast majority of cares of material and apparatus to be reutilized in conventional activities without the need of calling on the assistance of external firms. The whole decontamination process was successfully completed on time and in particular the quantity of contaminated wastes was kept to eminimun

  7. Platform decommissioning costs

    International Nuclear Information System (INIS)

    There are over 6500 platforms worldwide contributing to the offshore oil and gas production industry. In the North Sea there are around 500 platforms in place. There are many factors to be considered in planning for platform decommissioning and the evaluation of options for removal and disposal. The environmental impact, technical feasibility, safety and cost factors all have to be considered. This presentation considers what information is available about the overall decommissioning costs for the North Sea and the costs of different removal and disposal options for individual platforms. 2 figs., 1 tab

  8. Decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    The I.A.E.A. recommendations about the possible stages of decommissioning facilities are recalled and, for each of the three selected stages, the physical state of the plant and its equipments, the survey, the inspections and testing required by this state, are described. The specific characteristics of decommissioning with regard to intervention and maintenance operations in ionizing atmosphere are emphasized. A list of known methods and technics and special equipments necessary to carry out the dismantling of large nuclear facilities are drawn. The state of large nuclear facilities permanently withdrawn from service in France and the interventions which have been executed are described

  9. Planning of MZFR decommissioning

    International Nuclear Information System (INIS)

    The concept chosen for decommissioning the MZFR reactor of plant components followed by the safe enclosure of the reactor building for about 30 years. It is intended that after lifting of the controlled areas the auxiliary building will be reused within the framework of KfK research projects. A decommissioning will be carried out in steps, the scope of licensing will be broken down into partial licences. It is expected that the last partial licence for safe enclosure will be granted in 1988. (orig.)

  10. New projects related to decommissioning

    International Nuclear Information System (INIS)

    The PMU has been established in support of the KNPP Decommissioning Department. All of the Infrastructure Projects associated with Decommissioning have been identified and are being managed through the EBRD Procurement Process. The status of the following projects is presented: Evaluation of the Radiological Inventory for Units 1 to 4; Supply of Size Reduction and Decontamination Workshops; Dismantling Tools and Equipment; Heat Generation Plant; Environmental Assessment for Decommissioning; Decay Storage Site for Transitional RAW ; Information Centres for Decommissioning; Storage Site for Conventional Waste from Decommissioning; Inventory, Treatment an Conditioning of Contaminated Soil; Concrete Core Sampling Analysis; Asbestos Removal Equipment; Demolition Equipment

  11. Nuclear facility decommissioning practice for plant-221

    International Nuclear Information System (INIS)

    This paper describes the practice of decommissioning nuclear facilities of the plant-221, including pre-preparation of decommissioning projects, implementing criteria, organizational management and quality assurance system for decommissioning, construction of decommissioning projects, decontaminating methods, operational monitoring, treatment and disposal of decommissioned radioactive contaminants and radiation survey for verification inspection of decommissioning termination. After being decommissioned to national acceptance standards, the whole plant-221 was transferred to local government for its unrestricted use. (authors)

  12. Particle-accelerator decommissioning

    International Nuclear Information System (INIS)

    Generic considerations involved in decommissioning particle accelerators are examined. There are presently several hundred accelerators operating in the United States that can produce material containing nonnegligible residual radioactivity. Residual radioactivity after final shutdown is generally short-lived induced activity and is localized in hot spots around the beam line. The decommissioning options addressed are mothballing, entombment, dismantlement with interim storage, and dismantlement with disposal. The recycle of components or entire accelerators following dismantlement is a definite possibility and has occurred in the past. Accelerator components can be recycled either immediately at accelerator shutdown or following a period of storage, depending on the nature of induced activation. Considerations of cost, radioactive waste, and radiological health are presented for four prototypic accelerators. Prototypes considered range from small accelerators having minimal amounts of radioactive mmaterial to a very large accelerator having massive components containing nonnegligible amounts of induced activation. Archival information on past decommissionings is presented, and recommendations concerning regulations and accelerator design that will aid in the decommissioning of an accelerator are given

  13. Decontamination and decommissioning

    International Nuclear Information System (INIS)

    The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of all bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; and (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. These four phases of work were conducted in accordance with applicable regulations for D and D of research facilities and applicable regulations for packaging, transportation, and burial and storage of radioactive materials. The final result is that the Advanced Fuel Laboratories now meet requirements of ANSI 13.12 and can be released for unrestricted use. The four principal documents utilized in the D and D of the Cheswick Site were: (1) Plan for Fully Decontaminating and Decommissioning, Revision 3; (2) Environmental Assessment for Decontaminating and Decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, Pa.; (3) WARD-386, Quality Assurance Program Description for Decontaminating and Decommissioning Activities; and (4) Health Physics, Fire Control, and Site Emergency Manual. These documents are provided as Attachments 1, 2, 3 and 4

  14. Particle-accelerator decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Opelka, J.H.; Mundis, R.L.; Marmer, G.J.; Peterson, J.M.; Siskind, B.; Kikta, M.J.

    1979-12-01

    Generic considerations involved in decommissioning particle accelerators are examined. There are presently several hundred accelerators operating in the United States that can produce material containing nonnegligible residual radioactivity. Residual radioactivity after final shutdown is generally short-lived induced activity and is localized in hot spots around the beam line. The decommissioning options addressed are mothballing, entombment, dismantlement with interim storage, and dismantlement with disposal. The recycle of components or entire accelerators following dismantlement is a definite possibility and has occurred in the past. Accelerator components can be recycled either immediately at accelerator shutdown or following a period of storage, depending on the nature of induced activation. Considerations of cost, radioactive waste, and radiological health are presented for four prototypic accelerators. Prototypes considered range from small accelerators having minimal amounts of radioactive mmaterial to a very large accelerator having massive components containing nonnegligible amounts of induced activation. Archival information on past decommissionings is presented, and recommendations concerning regulations and accelerator design that will aid in the decommissioning of an accelerator are given.

  15. Decommissioning - The worldwide challenge

    International Nuclear Information System (INIS)

    Full text: Whatever the future may hold for nuclear power, there are closed or ageing nuclear facilities in many countries around the world. While these may be in safe care and maintenance at present, a sustainable long term solution is required. Facilities need to be decommissioned, contaminated land remediated, and wastes conditioned for safe storage or disposal. Practical nuclear site restoration has been demonstrated internationally. This experience has revealed generic challenges in dealing with old, often experimental, facilities. These include: Facilities not designed for ease of decommissioning; Records of plant construction and operation, and of the materials utilised and wastes produced, not to modern standards; Fuels and wastes stored for long periods in less than optimal conditions, leading to deterioration and handling problems; The historic use of experimental fuels and materials, giving rise to unique waste streams requiring unique waste management solutions; The application of modern safety and environmental standards to plant which dates from the 1940s, 50s and 60s, requiring investment before decommissioning can even commence. These problems can be tackled, as examples from UKAEA's own programme will illustrate. But two fundamental issues must be recognised and considered. First, the costs of decommissioning older facilities are very high, and may place a heavy burden on national budgets, despite using best efforts to control them. We can limit these costs by learning from one another's experience and sharing the development of new techniques and technologies. UKAEA has already initiated a programme of international collaboration, and hopes that other IAEA countries will be encouraged to follow suit. But whilst the costs of decommissioning may be high, the process normally meets with public acceptance. This is seldom the case for long term waste storage or disposal. Until waste management routes are available - either nationally or internationally - the environmental restoration of nuclear sites can never be fully completed. (author)

  16. CNEA decommissioning program

    International Nuclear Information System (INIS)

    Full text: According to chapter I, Art. 2.e of the National Law Nr. 24804 ruling nuclear activities in Argentina, CNEA is responsible for determining the procedure for decommissioning Nuclear Power Plants and any other relevant radioactive facilities'. The implementation the Nuclear Law, states that CNEA is responsible for deactivation and decommissioning of all relevant radioactive facilities in the country, at end of life. Consequently CNEA have created the D and D Branch in order to perform this activity. It is important point out that none of the 28 nuclear installations in Argentina is undergoing decommissioning. Nevertheless planning stages prior decommissioning have been started with the criterion of prioritising those that will probably generate the greatest volume of radioactive waste. Decommissioning plan for research reactors and Atucha I Nuclear Power Plant, radiological characterization, decontamination and treatment of miscellaneous equipment and components of the Atucha I Nuclear Power Plant and old installations are being carry out. The main task is to get the technical capability of the steps which must be followed. In order to accomplish this objective the main activities are: a) Coordinates the training of personnel and organizes the experience and technical knowledge already existing in CNEA and members of the Argentinean nuclear sector; b) Coordinates a R and D program on D and D technologies; c) Establishes close links with the operators of nuclear facilities, whose participation both in planning and in actual D and D work is considered extremely important; d)Preliminary planning and radiological characterization of significant nuclear installations. This paper summarizes general aspects of the activities which are currently in progress. (author)

  17. High resolution seismic reflection profiling at Aberdeen Proving Grounds, Maryland

    International Nuclear Information System (INIS)

    The effectiveness of shallow high resolution seismic reflection (i.e., resolution potential) to image geologic interfaces between about 70 and 750 ft at the Aberdeen Proving Grounds, Maryland (APG), appears to vary locally with the geometric complexity of the unconsolidated sediments that overlay crystalline bedrock. The bedrock surface (which represents the primary geologic target of this study) was imaged at each of three test areas on walkaway noise tests and CDP (common depth point) stacked data. Proven high resolution techniques were used to design and acquire data on this survey. Feasibility of the technique and minimum acquisition requirements were determined through evaluation and correlation of walkaway noise tests, CDP survey lines, and a downhole velocity check shot survey. Data processing and analysis revealed several critical attributes of shallow seismic data from APG that need careful consideration and compensation on reflection data sets. This survey determined: (1) the feasibility of the technique, (2) the resolution potential (both horizontal and vertical) of the technique, (3) the optimum source for this site, (4) the optimum acquisition geometries, (5) general processing flow, and (6) a basic idea of the acoustic variability across this site. Source testing involved an accelerated weight drop, land air gun, downhole black powder charge, sledge hammer/plate, and high frequency vibrator. Shallow seismic reflection profiles provided for a more detailed picture of the geometric complexity and variability of the distinct clay sequences (aquatards), previously inferred from drilling to be present, based on sparse drill holes and basewide conceptual models. The seismic data also reveal a clear explanation for the difficulties previously noted in correlating individual, borehole-identified sand or clay units over even short distances

  18. Environmental geophysics at J-Field, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Daudt, C.R.; McGinnis, L.D.; Miller, S.F.; Thompson, M.D.

    1994-11-01

    Geophysical data collected at J-Field, Aberdeen Proving Ground, Maryland, were used in the characterization of the natural hydrogeologic framework of the J-Field area and in the identification of buried disturbances (trenches and other evidences of contamination). Seismic refraction and reflection data and electrical resistivity data have aided in the characterization of the leaky confining unit at the base of the surficial aquifer (designated Unit B of the Tertiary Talbot Formation). Excellent reflectors have been observed for both upper and lower surfaces of Unit B that correspond to stratigraphic units observed in boreholes and on gamma logs. Elevation maps of both surfaces and an isopach map of Unit B, created from reflection data at the toxic burning pits site, show a thickening of Unit B to the east. Abnormally low seismic compressional-wave velocities suggest that Unit B consists of gassy sediments whose gases are not being flushed by upward or downward moving groundwater. The presence of gases suggests that Unit B serves as an efficient aquitard that should not be penetrated by drilling or other activities. Electromagnetic, total-intensity magnetic, and ground-penetrating radar surveys have aided in delineating the limits of two buried trenches, the VX burning pit and the liquid smoke disposal pit, both located at the toxic burning pits site. The techniques have also aided in determining the extent of several other disturbed areas where soils and materials were pushed out of disposal pits during trenching activities. Surveys conducted from the Prototype Building west to the Gunpowder River did not reveal any buried trenches.

  19. Decommissioning database. Public presentation by intranet

    International Nuclear Information System (INIS)

    In order to efficiently develop a decommissioning plan of a nuclear facility, it is useful to develop a database containing information on decommissioning technology, cost and risk analysis results, and decommissioning projects such as the JPDR decommissioning project by collecting the information systematically. A decommissioning database has been developed by collecting decommissioning related information and analyzing it. The database provides information on not only data of decommissioning technology and decommissioning projects but also laws and safety standards for decommissioning in each country and international organizations. The database is released in a Homepage on Web and is available for use via intranet with functions of retrieval, display and printing. (author)

  20. Decommissioning of offshore installations

    Energy Technology Data Exchange (ETDEWEB)

    Oeen, Sigrun; Iversen, Per Erik; Stokke, Reidunn; Nielsen, Frantz; Henriksen, Thor; Natvig, Henning; Dretvik, Oeystein; Martinsen, Finn; Bakke, Gunnstein

    2010-07-01

    New legislation on the handling and storage of radioactive substances came into force 1 January 2011. This version of the report is updated to reflect this new regulation and will therefore in some chapters differ from the Norwegian version (see NEI-NO--1660). The Ministry of the Environment commissioned the Climate and Pollution Agency to examine the environmental impacts associated with the decommissioning of offshore installations (demolition and recycling). This has involved an assessment of the volumes and types of waste material and of decommissioning capacity in Norway now and in the future. This report also presents proposals for measures and instruments to address environmental and other concerns that arise in connection with the decommissioning of offshore installations. At present, Norway has four decommissioning facilities for offshore installations, three of which are currently involved in decommissioning projects. Waste treatment plants of this kind are required to hold permits under the Pollution Control Act. The permit system allows the pollution control authority to tailor the requirements in a specific permit by evaluating conditions and limits for releases of pollutants on a case-to-case basis, and the Act also provides for requirements to be tightened up in line with the development of best available techniques (BAT). The environmental risks posed by decommissioning facilities are much the same as those from process industries and other waste treatment plants that are regulated by means of individual permits. Strict requirements are intended to ensure that environmental and health concerns are taken into account. The review of the four Norwegian decommissioning facilities in connection with this report shows that the degree to which requirements need to be tightened up varies from one facility to another. The permit for the Vats yard is newest and contains the strictest conditions. The Climate and Pollution Agency recommends a number of measures and requirements that should be considered in the regulation of decommissioning facilities for offshore installations. These facilities need sound expertise to be able to identify and deal with different types of waste, including hazardous waste such as heavy metals, other hazardous substances, low specific activity (LSA) radioactive material and asbestos. Facilities must be designed to allow safe handling of such waste, with no risk of runoff or infiltration into the soil. In addition, a decommissioning facility should have an effective collection system and an on-site treatment plant for contaminated water, including surface water. Each facility must have a sampling and analysis programme to monitor releases of the most relevant pollutants. The need for an environmental monitoring programme to follow developments in the recipient should also be considered. Other factors that must be closely monitored include noise and releases to air in connection with metal cutting and other operations. Moreover, decommissioning contracts must ensure that the costs of handling hazardous waste are met by the offshore operators. When decommissioning facilities for offshore installations are being sited, other interests must also be taken into account; for example, the use of nearby areas for housing, holiday housing or recreation. In addition, the implications for other sectors such as fisheries and agriculture must be taken into consideration. These are important issues that the municipalities must consider when preparing zoning plans and drawing up environmental impact assessments. In many cases, a regional authority is in a better position than a national one to make overall, cross-sectoral assessments of developments within the region. Nevertheless, the report recommends transferring the authority for regulating decommissioning facilities for offshore installations from the County Governors to the Climate and Pollution Agency. Regulating these facilities requires special expertise and overall assessments, and is best dealt with at central level. When new regulations have entered into force, the Norwegian Radiation Protection Authority will be responsible for regulating radioactive releases and waste from the same facilities under the Pollution Control Act. This will require close coordination between the two agencies and makes it more important to transfer authority to the Climate and Pollution Agency. In addition, decommissioning of offshore facilities involves the oil and gas industry and may involve the import and export of waste, both areas where the Climate and Pollution Agency is already the competent authority. The costs of decommissioning the roughly 500 installations on the Norwegian continental shelf are uncertain, but a preliminary estimate suggests that the overall cost will be about NOK 160 billion. This estimate does not include the removal of fixed concrete substructures, since the costs of this are very uncertain at present.

  1. Decommissioning a nuclear reactor

    International Nuclear Information System (INIS)

    The process of decommissioning a facility such as a nuclear reactor or reprocessing plant presents many waste management options and concerns. Waste minimization is a primary consideration, along with protecting a personnel and the environment. Waste management is complicated in that both radioactive and chemical hazardous wastes must be dealt with. This paper presents the general decommissioning approach of a recent project at Los Alamos. Included are the following technical objectives: site characterization work that provided a thorough physical, chemical, and radiological assessment of the contamination at the site; demonstration of the safe and cost-effective dismantlement of a highly contaminated and activated nuclear-fuelded reactor; and techniques used in minimizing radioactive and hazardous waste. 12 figs

  2. Decommissioning a nuclear reactor

    International Nuclear Information System (INIS)

    The process of decommissioning a facility such as a nuclear reactor or reprocessing plant presents many waste management options and concerns. Waste minimization is a primary consideration, along with protecting personnel and the environment. Waste management is complicated in that both radioactive and chemical hazardous wastes must be dealt with. This paper presents the general decommissioning approach of a recent project at Los Alamos. Included are the following technical objectives: site characterization work that provided a thorough physical, chemical, and radiological assessment of the contamination at the site; demonstration of the safe and cost-effective dismantlement of a highly contaminated and activated nuclear-fueled reactor; and techniques used in minimizing radioactive and hazardous waste

  3. Fort St. Vrain decommissioning project

    International Nuclear Information System (INIS)

    Public Service Company of Colorado (PSCo), owner of the Fort St. Vrain nuclear generating station, achieved its final decommissioning goal on August 5, 1997 when the Nuclear Regulatory Commission terminated the Part 50 reactor license. PSCo pioneered and completed the world's first successful decommissioning of a commercial nuclear power plant after many years of operation. In August 1989, PSCo decided to permanently shutdown the reactor and proceed with its decommissioning. The decision to proceed with early dismantlement as the appropriate decommissioning method proved wise for all stake holders - present and future - by mitigating potential environmental impacts and reducing financial risks to company shareholders, customers, employees, neighboring communities and regulators. We believe that PSCo's decommissioning process set an exemplary standard for the world's nuclear industry and provided leadership, innovation, advancement and distinguished contributions to other decommissioning efforts throughout the world. (author)

  4. Planning the Nabarlek decommissioning

    International Nuclear Information System (INIS)

    After a general review of the decommissioning and rehabilitation requirement, the paper details the work required to dewater and consolidate the tailings stored in the open pit, preparatory to placing the final cover. Some mention is made of failure modes of the tailings impoundment. Methods of disposing of water stored on site are discussed, with water quantity calculations and the selected disposal method. Also discussed are removal of the plant and revegetation of the site

  5. The Aberdeen Indian Health Service Infant Mortality Study: Design, Methodology, and Implementation

    Science.gov (United States)

    Randall, Leslie L.; Krogh, Christopher; Welty, Thomas K.; Willinger, Marian; Iyasu, Solomon

    2001-01-01

    Of all Indian Health Service areas, the Aberdeen Area has consistently had the highest infant mortality rate. Among some tribes in this area the rate has exceeded 30/1000 live birth and half the infant deaths have been attributed to Sudden Infant Death Syndrome, a rate four to five times higher than the national average. The Indian Health Service,

  6. Decommissioning of nuclear submarines

    International Nuclear Information System (INIS)

    The intention of this Report is to set out in simple terms the options open to the Ministry of Defence in disposing of nuclear submarines, and the extent of the problem. To this end oral evidence was taken from United Kingdom Nirex Limited (Nirex) and from the Ministry of Defence, and written evidence was taken from MoD, Nirex, the United Kingdom Atomic Energy Authority and Rolls-Royce and Associates Limited. The immediate problem is what to do with the nuclear submarine, DREADNOUGHT. Since decommissioning in 1982, the submarine has been lying at Rosyth Naval Base on the Firth of Forth. Upon decommissioning, the highly radioactive reactor core with the uranium fuel was removed and transported to the Sellafield reprocessing plant. The remaining radioactive part is the reactor compartment and it is the size of this, not its level of radioactivity which makes it hard to deal with. By the year 2000 a further seven nuclear submarines will have been decommissioned. There are three main options for disposing of the reactor compartments; dumping at sea, land burial in a shallow trench and land burial in a deep repository. Dumping at sea is the option favoured by the Ministry of Defence and Government, but shallow land burial remains an option. Deep burial is not an option which is available immediately as there will not be a repository ready until 2005. (author)

  7. Decommissioning of nuclear power facilities

    International Nuclear Information System (INIS)

    This is the first manual in Ukraine giving the complete review of the decommissioning process of the nuclear power facilities including the issues of the planning, design documentation development, advanced technology description. On the base of the international and domestic experience, the issues on the radwaste management, the decontamination methods, the equipment dismantling, the remote technology application, and also the costs estimate at decommissioning are considered. The special attention to the personnel safety provision, population and environment at decommissioning process is paid

  8. Risk assessment for HWRR decommissioning

    International Nuclear Information System (INIS)

    A risk assessment method for reactor decommissioning was established. The method comprises five procedures: source analysis, hazard analysis, frequency analysis, accident consequence analysis and risk analysis. Based on the method, the reactor decommissioning risk assessment system (RDRAS) was developed. 53 situations of the 11 activities that may arise in the HWRR decommissioning process were modeled and calculated with RDRAS to identify the radioactive risk that working staff may face in each situation, and the uncertainties of the results were analyzed. (authors)

  9. Tokai-1 decommissioning project

    International Nuclear Information System (INIS)

    Tokai-1 (GCR, Gas Cooled Reactor) nuclear power plant of JAPC (the Japan Atomic Power Company) started commercial operation in 1966 as the first commercial nuclear power plant in Japan. The unit had helped introduction and establishment of the construction and operation technologies regarding nuclear power plant at early stage in Japan by its construction and operating experiences. However, The Japan Atomic Power Company (JAPC), the operator and owner of Tokai-1, decided to cease its operation permanently because of a fulfillment of its mission and economical reason. The unit was finally shut down in March 1998 after about 32 year operation. It took about three years for removal of all spent fuels from the site, and then decommissioning started in 2001. JAPC, always on the forefront of the nation's nuclear power generation, is now grappling Japan's first decommissioning of a commercial nuclear power plant, striving to establish effective, advanced decommissioning. The decommissioning for Tokai-1 was scheduled as 20 years project. At the beginning, the reactor was started to be in a static condition ('safe storage period'). While the reactor had been safely stored, the phased decommissioning works started from non-radioactive or low radioactive equipment toward high radioactive equipment. First five years of the project, JAPC concentrated to drain and clean spent fuel cartridge cooling pond and to remove conventional equipments such as turbine, feed water pump and fuel charge machine as planed and budgeted. From 2006, the project came into a new phase. JAPC has been trying to remove four Steam Raising Units (SRUs). The SRUs are huge component (750ton, φ6.3m, H24.7m) of the Gas Cooling Reactor (GCR) and inside of the SRUs are radioactively contaminated. Major concerns are workers safety and minimizing contamination areas during SRU removal. Therefore, JAPC is developing and introducing Jack-down method and remote control multi-functional dismantling system. This method is to cut and remove the SRUs in turn from the bottom to top remotely while lifting the SRU by a large jack system. The system enables cutting and holding not only the SRU body but also internals. This technology and experiences would be useful for the reactor removal in the near future. Skirt part of No.2 SRU cutting work was done carefully by well trained JAPC staff from August 2010 to December, 2010. (author)

  10. Decommissioning of Radiotherapy Facilities

    International Nuclear Information System (INIS)

    Radiotherapy units containing high activity sealed radioactive sources of 60Co or 137Cs are mainly use for medical, research or calibration applications. After several half-lives of decay, the radionuclide source has to be changed or the unit is decommissioned if no longer required. Before starting a decommissioning project it is very important to look for documents relating to any sources held or installed in equipment. In general this should be no problem because the recommended working life of such sealed radioactive sources is limited to 10 or a maximum of 15 years. These time periods are short in comparison with other facilities like research laboratories or small reactors. These documents (source certificates) will be very helpful to plan the decommissioning because they say everything about the original activity of the source at a reference date, the type of the source and the manufacturer. The next step may be to contact the machine supplier or the source manufacturer, but be aware that neither may still be in existence or may have changed their type of business. In such cases, it is recommended to contact national or international sealed source manufacturers or suppliers for help. Sometimes it is also helpful to contact colleagues in other hospitals or research centres to ask for information about specialists in this topic. In general it is not useful, and even very dangerous, to try to decommission such a unit without expert help It is essential to have specialist tools and shielded containers to recover the source out of the unit. It is strongly recommended to invite the source removal specialist for a site visit to review the situation before starting any decommissioning process. A further problem can occur, if the source must be transported to a national storage centre or even an international storage facility, as the source must be packaged to meet international transport requirements. The end state of such a project should be an empty room where the source is brought out safely within the type-tested container, typically type B. Decontamination of the room will be necessary if a sealed source has leaked, but this is very rare. If a source is leaking, the contamination can be very high and present a high risk to employees and workers due to high dose rates. Some therapy units are additionally shielded with depleted uranium or the source holder is fitted with collimators which are made of depleted uranium. The uranium shielding can cause some minor contamination of the shielded source housing or on the floor. A check should be made for any minor contamination using a surface contamination monitor or wipe tests. The risks of contamination from these sources are small, but can result in the prevention of the free release of the room. A decommissioning plan should be drafted following consultation with the regulator or the decommissioning specialist may undertake this task on behalf of the facility. Normally the specialist contractor will provide a health and safety plan for approval by the regulator and the customer. The decommissioning task of source removal and transport will in general take about 2 to 3 days, but the planning and preparatory work can take several weeks. The amount of preparatory work involved depends mainly of the transport regulations for the source in the type-tested containers and the preparatory work for infrastructures that will be required for decommissioning. Identification of infrastructure and resources. Before dismantling a teletherapy unit, a check should be made that the electrical supply remains connected and that the lighting is both functional and adequate. This will help to accelerate the working process on the unit. Before attempting to move the teletherapy source of unit outside of the building, ensure that the route to be used through the facility is passable (dimensions of doors, floors, etc.) and that the engineering structure of the pathway is sufficient to support the weight of the source or unit (e.g. maximum load limit of floors or lifts). The units and shielding containers can be very heavy because of the shielding material. A typical weight is more than one tonne and closer to three tonnes is more usual. If the infrastructure is not sufficient to support these weights, a specialist constructional engineer should be contacted for advice. It may be necessary to find an alternate method to bring the source or unit out of the building; e.g. bring the unit or container out via the ground floor using mobile cranes or hoists or fork-lifts. The dismantling of the unit is done by specialists who will be familiar with the unit type and will have available the correct specialist tools, mostly manufactured and sold by the manufacturers of the teletherapy machines. There are essentially three steps to dismantling: -Dismantling of the unit in order to gain access to the source; -Transfer of the source in its shielded housing into the transport container; -Demolition of the rest of the unit. Sometimes step (b) is modified and the whole therapy head is transported inside a special over-pack (type BU). In this case, the source remains in the unit head and does not need to be taken out. Normally no radioactive waste will be produced from decommissioning of teletherapy facilities. If contamination is found, there will be secondary waste produced in the form of absorbent paper sheets or textiles from wet cleaning, disposal protective clothing or concrete from the surface of the irradiation bunker. Waste volumes would generally be very small.

  11. Shippingport Station Decommissioning Project start of physical decommissioning

    International Nuclear Information System (INIS)

    This paper describes the current status of the physical decommissioning work, which started September 1985. The preparations required to start a major decommissioning work effort in a safe and cost effective manner are discussed including the development of integrated detailed schedules, manpower and cost estimates, and implementation of a cost/schedule control system. The detailed plan required to ensure that people, property, and procedures are ready in sufficient time to support the start of physical decommissioning is also discussed. The total estimated cost of the Shippingport Station Decommissioning Project should be $98.3 M, with the Project scheduled for completion in April 1990. At the decommissioning of the first commercial-sale nuclear power plant, the Shippingport Project is expected to set the standard for safe, cost-effective demolition of nuclear plants

  12. Workshop on decommissioning; Seminarium om avveckling

    Energy Technology Data Exchange (ETDEWEB)

    Broden, K. (ed.)

    2005-12-15

    A Nordic workshop on decommissioning of nuclear facilities was held at Risoe in Denmark September 13-15, 2005. The workshop was arranged by NKS in cooperation with the company Danish Decommissioning, DD, responsible for decommissioning of nuclear facilities at Risoe. Oral presentations were made within the following areas: International and national recommendations and requirements concerning decommissioning of nuclear facilities Authority experiences of decommissioning cases Decommissioning of nuclear facilities in Denmark Decommissioning of nuclear facilities in Sweden Plans for decommissioning of nuclear facilities in Norway Plans for decommissioning of nuclear facilities in Finland Decommissioning of nuclear facilities in German and the UK Decommissioning of nuclear facilities in the former Soviet Union Results from research and development A list with proposals for future work within NKS has been prepared based on results from group-work and discussions. The list contains strategic, economical and political issues, technical issues and issues regarding competence and communication. (au)

  13. ORNL decontamination and decommissioning program

    International Nuclear Information System (INIS)

    A program has been initiated at ORNL to decontaminate and decommission surplus or abandoned nuclear facilities. Program planning and technical studies have been performed by UCC-ND Engineering. A feasibility study for decommissioning the Metal Recovery Facility, a fuel reprocessing pilot plant, has been completed

  14. Decommissioning hospitals--a checklist.

    Science.gov (United States)

    Battle, T; Clemence, L

    1990-10-01

    Decommissioning a hospital is not an every day management task, but as the health service endeavours to make better use of its estate it is likely to face more managers. St Stephen's Hospital, Chelsea, was recently decommissioned to make way for a new teaching hospital, and Tim Battle and Lynne Clemence offer a checklist based on the experience. PMID:10107166

  15. San Onofre unit 1 decommissioning

    International Nuclear Information System (INIS)

    Nuclear plant decommissioning presents several challenges in radiation protection. The plant demolition must consider radiation protection for workers, protection of the public and careful material management. Decommissioning of the San Onofre Nuclear Generating Station (SONGS) Unit 1 presented some additional challenges. (author)

  16. BNFL decommissioning strategy and techniques

    International Nuclear Information System (INIS)

    This paper provides an overview of the range of reactor decommissioning projects being managed by BNFL, both on its own sites and for other client organizations in the UK and abroad. It also describes the decommissioning strategies and techniques that have been developed by BNFL and adopted in order to carry out this work

  17. RMI decommissioning project

    International Nuclear Information System (INIS)

    The RMI Titanium Company (RMI) Extrusion Plant, owned and operated by RMI is contaminated with both radiological and hazardous materials resulting from previous operations for the US Department of Energy (DOE). The primary function of RMI, since 1962, has been the extrusion and closed-die forging of metallic depleted, natural, and slightly enriched uranium (U) used in the production of nuclear fuel elements for defense production reactors, extrusion operations for other government agencies, and the private sector. Extrusion of uranium ended in September 1988 and other extrusion operations ceased n October 1990. The Nuclear Regulatory Commission (NRC) has identified the RMI Plant as one of 46 existing inactive nuclear material processing facilities required to implement accelerated site clean-up pursuant to its Site Decommissioning Management Plan (SDMP). The US Environmental Protect Agency (USEPA) has issued RMI a Resource Conservation existing Corrective Action Management Unit (CAMU). DOE's Office of Environmental Restoration and removing all radiological and hazardous contaminants to levels which permit the facility and adjacent areas to be released for unrestricted use. This action will allow termination of RMI licenses and closure of the CAMU located on and adjacent to RMI's property. This paper will provide an overview of the project and preparations for conducting the physical decommissioning activities including: (1) Radiological and hazardous material characterization of the site; (2) Waste minimization and volume reduction alternatives considered; (3) Waste disposal alternatives considered; (4) NEPA compliance requirements; (5) EPA compliance requirements [Correctives Measures Study]; (6) NRC compliance requirements [Decommissioning Plan]. The paper will also discuss the project organization and the regulatory interfaces required for the project

  18. Decommissioning policy in Sweden

    International Nuclear Information System (INIS)

    In Sweden the nuclear power program is, according to a parliamentary decision, limited to twelve power producing reactors. The last reactor shall be taken out of service no later than the year 2010. As a result of the Chernobyl accident the program for taking the reactors out of service will be accelerated. This report is the first approach by the Swedish authorities to formulate a decommissioning policy. It is not the final policy document but it discusses the principal questions from the special Swedish viewpoint. (orig.)

  19. PHENIX plant decommissioning project

    International Nuclear Information System (INIS)

    This paper gives a general view of the Phenix reactor decommissioning schedule. It summarizes the main steps of end of operations (Cessation Definitive d'Exploitation: CDE) and dismantling phases. These two phases are described from the final shutdown planned in 2009 to the end of dismantling around 2024. During the first phase, operations consist mainly in removing fuel and other materials. Most of the treatment facilities for sodium and wastes are built during this phase. During the dismantling phase, operations consist mainly in treating the sodium and dismantling the reactor and the other nuclear facilities and equipments. (author)

  20. Accuracy of adults’ recall of childhood social class: findings from the Aberdeen children of the 1950s study

    OpenAIRE

    Batty, G D; Lawlor, D. A.; Macintyre, S.; H. Clark; D A Leon

    2005-01-01

    Background: Although adult reported childhood socioeconomic position has been related to health outcomes in many studies, little is known about the validity of such distantly recalled information. This study evaluated the validity of adults’ reports of childhood paternal social class. Methods: Data are drawn from the Aberdeen children of the 1950s study, a cohort of 12 150 people born in Aberdeen (Scotland) who took part in a school based survey in 1962. In this survey, two indices of ea...

  1. Financing nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Much is at stake in developing a financial strategy for decommissioning nuclear power plants. Since decommissioning experience is limited to relatively small reactors, will the costs associated with larger reactors be significantly higher. Certainly the decommissioning issue intersects with other critical issues that will help to determine the future of commercial nuclear power in the US. The author examines briefly the basic concepts and terms related to decommissioning expenses, namely: (1) segregated fund; (2) non-segregated fund; (3) external method; and (4) internal method. He concludes that state regulatory commissions have turned increasingly to the external funding method because of increasing costs and related problems associated with nuclear power, changing conditions and uncertainties concerned with utility restructuring, and recent changes in federal tax laws related to decommissioning. Further, this trend is likely to continue if financial assurance remains a primary concern of regulators to protect this public interest

  2. Managing the Unexpected in Decommissioning

    International Nuclear Information System (INIS)

    This publication explores the implications of decommissioning in the light of unexpected events and the trade-off between activities to reduce them and factors militating against any such extra work. It classifies and sets out some instances where unexpected findings in a decommissioning programme led to a need to either stop, or reconsider the work, re-think the options, or move forward on a different path. It provides practical guidance in planning and management of decommissioning taking into account unexpected events. This guidance includes an evaluation of the experience and lessons learned in tackling decommissioning that is often neglected. Thus it will enable future decommissioning teams to adopt the relevant lessons to reduce additional costs, time delays and radiation exposures

  3. Decommissioning Funding: Ethics, Implementation, Uncertainties

    International Nuclear Information System (INIS)

    This status report on decommissioning funding: ethics, implementation, uncertainties is based on a review of recent literature and materials presented at NEA meetings in 2003 and 2004, and particularly at a topical session organised in November 2004 on funding issues associated with the decommissioning of nuclear power facilities. The report also draws on the experience of the NEA Working Party on Decommissioning and Dismantling (WPDD). This report offers, in a concise form, an overview of relevant considerations on decommissioning funding mechanisms with regard to ethics, implementation and uncertainties. Underlying ethical principles found in international agreements are identified, and factors influencing the accumulation and management of funds for decommissioning nuclear facilities are discussed together with the main sources of uncertainties of funding systems

  4. Shippingport Station Decommissioning Project Start of Physical Decommissioning

    International Nuclear Information System (INIS)

    The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy, and the turbine-generator and balance of plant, which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by DOE from Duquesne Light Company. The Shippingport Station Decommissioning Project is being performed under contract to the DOE by the General Electric Company and its integrated subcontractor, Morrison-Knudsen Company. as the Decommissioning Operations Contractor. This paper describes the current status of the physical decommissioning work, which started September 1985. The preparations required to start a major decommissioning work effort in a safe and cost effective manner are discussed including the development and implementation of a cost/schedule control system. The detailed plan required to ensure that people, property, and procedures are ready in sufficient time to support the start of physical decommissioning is also discussed. The total estimated cost of the Shippingport Station Decommissioning Project should be $98.3 M, with the Project scheduled for completion in April 1990. As the decommissioning of the first commercial-scale nuclear power plant, the Shippingport Project is expected to set the standard for safe, cost-effective demolition of nuclear plants

  5. Shippingport station decommissioning project start of physical decommissioning

    International Nuclear Information System (INIS)

    The Shippingport Atomic Power Station (SAPS) consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy (DOE), and the turbine-generator and balance of plant, which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by DOE from Duquesne Light Company. The Shippingport Station Decommissioning Project (SSDP) is being performed under contract to the DOE by the General Electric Company and its integrated subcontractor, Morrison-Knudsen Company, as the Decommissioning Operations Contractor (DOC). This paper describes the current status of the physical decommissioning work, which started September 1985. The preparations required to start a major decommissioning work effort in a safe and cost effective manner are discussed including the development of integrated detailed schedules, manpower and cost estimates, and implementation of a cost/schedule control system. The detailed plan required to ensure that people, property, and procedures are ready in sufficient time to support the start of physical decommissioning is also discussed. The total estimated cost of the Shippingport Station Decommissioning Project should be $98.3 M, with the Project scheduled for completion in April 1990. As the decommissioning of the first commercial-scale nuclear power plant, the Shippingport Project is expected to set the standard for safe, cost-effective demolition of nuclear plants

  6. Criteria for decommissioning

    International Nuclear Information System (INIS)

    In this paper the authors describe three risk acceptability criteria as parts of a strategy to clean up decommissioned facilities, related to both the status quo and to a variety of alternative technical clean-up options. The acceptability of risk is a consideration that must enter into any decision to establish when a site is properly decommissioned. To do so, both the corporate and public aspects of the acceptability issue must be considered. The reasons for discussion the acceptability of risk are to: Legitimize the process for making cleanup decisions; Determine who is at risk, who benefits, and who bears the costs of site cleanup, for each specific cleanup option, including the do nothing option; Establish those factors that, taken as a whole, determine measures of acceptability; Determine chemical-specific aggregate and individual risk levels; and Establish levels for cleanup. The choice of these reasons is pragmatic. The method consistent with these factors is risk-risk-effectiveness: the level of cleanup must be consistent with the foreseeable use of the site and budget constraints. Natural background contamination is the level below which further cleanup is generally inefficient. Case-by-case departures from natural background are to be considered depending on demonstrated risk. For example, a hot spot is obviously a prima facie exception, but should be rebuttable. Rebuttability means that, through consensus, the ''hot spot'' is shown not to be associated with exposure

  7. Funding Decommissioning - UK Experience

    International Nuclear Information System (INIS)

    'Funding' started with CEGB and SSEB (state-owned electric utilities) in 1976 using the internal un-segregated fund route (i.e unfunded). This continued until privatisation of electricity industry (excluding nuclear) in 1990. Assets bought with the internal un-segregated fund were mostly transferred into non-nuclear private utilities. New state-owned Nuclear Electric (England and Wales) was given a 'Fossil Fuel Levy', a consumer charge of 10% on retail bills, amounting to c. BP 1 bn. annually. This allowed Nuclear Electric to trade legally (A reserve of BP 2.5 bn. was available from Government if company ran out of money). By 1996 the newer nuclear stations (AGRS plus PWR) were privatised as British Energy. British Energy started an external segregated fund, the Nuclear Decommissioning Fund, with a starting endowment of c. BP 225 m. - and BE made annual contributions of British Pound 16 m. into the Fund. Assumptions were that BE had 70 to accumulate cash and could get a 3.5% average annual real return. Older stations (Magnox) were left in private sector and went to BNFL in 1997. Magnox inherited the surplus cash in BE - mostly unspent Fossil Fuel Levy receipts - of c. BP 2.6 bn. Government gave an 'Undertaking' to pay BP 3.8 bn. (escalating at 4.5% real annually) for Magnox liabilities, should Magnox Electric run out of cash. BNFL inherited the BP 2.6 bn. and by 2000 had a 'Nuclear Liabilities Investment Portfolio' of c. BP 4 bn. This was a quasi-segregated internal fund for liabilities in general. [Note: overall UK nuclear liabilities in civilian sector were running at c. BP 48 bn. by now]. BE started profitable and paid BP 100 m. annually in dividends to private investors for several years. BE ran into severe financial problems after 2001 and Government organised restructuring aid, now approved by European Commission. Terms include: - BE now to contribute BP 20 m. a year into an expanded Nuclear Liabilities Fund; - A bond issue of BP 275 m. to go to Fund; - 65% of all BE free cash flow to go to the Fund; - Government would pay for all Stage 1/2/3 decommissioning expenses that BE could not meet. BE is still a private company in a formal sense but the UK Office of National Statistics classifies it as a public sector company, because it regards control (not ownership) as in State hands. Government is now setting up the Nuclear Decommissioning Authority (NDA) to manage all public sector liabilities. Intention was to have a 'segregated account' to help give assurance that funding would be long-term and reliable. First draft Annual Plan does not mention segregation or any funding commitment beyond the first year (2005/6). The BNFL NLIP will presumably go to the Treasury. NLIP will presumably go to the Treasury. In conclusion, it is clean that the decommissioning funding system has been short term and has relied mainly on Government. Some consumer contributions have been made, but now that nuclear power competes in a private market place and is relatively expensive, there is no guarantee that consumers/polluters will pay for a significant proportion of decommissioning costs

  8. Evaluation of Nuclear Facility Decommissioning Projects program

    International Nuclear Information System (INIS)

    The objective of the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program is to provide the NRC licensing staff with data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. The data will also provide information to determine the funding level necessary to ensure timely and safe decommissioning operations. Actual decommissioning costs, methods and radiation exposures are compared with those estimated by the Battelle-PNL and ORNL NUREGs on decommissioning. Exposure reduction techniques applied to decommissioning activities to meet ALARA objectives are described. The lessons learned concerning various decommissioning methods are evaluated

  9. Planning for decommissioning of Hifar

    International Nuclear Information System (INIS)

    The Australian Nuclear Science and Technology Organisation (ANSTO) has operated the 10MW HIFAR research reactor since 1958. In addition to its role in research, the reactor provides radioisotopes for medical and industrial use and is a major supplier of NTD silicon for the semi-conductor industry. It is anticipated that HIFAR will finally shut down operations in December 2006. Although ANSTO has successfully decommissioned MOATA and undertaken other smaller decommissioning projects the proposed HIFAR decommissioning project will be the largest ever undertaken by ANSTO. ANSTO faces a number of challenges in HIFAR's final year of operation. These include: the establishment of a modern decommissioning strategy in the absence of a long-term nuclear waste repository management facility or waste acceptance criteria for the material generated by the decommissioning; the impact of the impeding closure of the facility on staff morale and retention of key staff; and to meet the our customer's needs up to the final closure. These challenges are compounded by competition for skilled resources required to commission the new research reactor (OPAL) and the need to continue to supply radioisotopes. Important 'lessons in progress' that will be discussed in this paper include staffing the decommissioning team, maintenance of a strong safety culture during final stages of operation, working towards regulatory approval for decommissioning and strategies for knowledge retention. (author)

  10. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 3: Ecological risk assessment

    Energy Technology Data Exchange (ETDEWEB)

    Hlohowskyj, I.; Hayse, J.; Kuperman, R.; Van Lonkhuyzen, R.

    2000-02-25

    The Environmental Management Division of the U.S. Army Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation (RI) and feasibility study (FS) of the J-Field area at APG, pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. As part of that activity, Argonne National Laboratory (ANL) conducted an ecological risk assessment (ERA) of the J-Field site. This report presents the results of that assessment.

  11. The sedimentology of the Teekloof Formation east of Aberdeen C.P

    International Nuclear Information System (INIS)

    The Teekloof Formation (Beaufort Group) sediments to the east of Aberdeen (South Africa) consist of mudstone, siltstone and fine-to very fine-grained lithic wackes and arenites. Sandstone lithosomes commonly have erosive bases and the vertical and lateral arrangement of lithofacies indicate that the environment of deposition was fluviatile. Uranium mineralization was syndepositional and was supplied to the stream waters in the form of soluble complexes by the weathering and leaching of acid volcanic and granitic rocks

  12. Improvising innovation in UK urban district heating: The convergence of social and environmental agendas in Aberdeen

    International Nuclear Information System (INIS)

    Research on district heating has focused on technical-economic appraisal of its contribution to energy and carbon saving in urban centres. There is however lack of analysis of political and social processes which govern its actual take up. This paper examines these processes through a case study of Aberdeen, Scotland. Interviews and documentary analysis are used to examine the 2002 development of Aberdeen Heat and Power (AHP), an independent energy services company (ESCo). Technical-economic feasibility was a necessary component of appraisal, but not sufficient to govern decision-making. In the UK centralised energy market, DH investment is unattractive to commercial investors, and local authorities lack capacity and expertise in energy provision. In Aberdeen, the politics of fuel poverty converged with climate politics, creating an a-typical willingness to innovate through improvisation. The welfare priority resulted in creation of a non-profit locally-owned ESCo, using cost- rather than market-based heat tariffs. AHP has developed three combined heat and power energy centres and heat networks, supplying 34 MWh/pa of heat. Carbon savings are estimated to be 45% in comparison with electric heating, and heating costs are reduced by a similar amount. The conclusion outlines potential policy improvements. - Highlights: • UK policy proposes district heating for urban low carbon heat. • Technical and economic feasibility are insufficient to drive take-up. • In Aberdeen convergence of social and environmental goals gave impetus to improvisation. • The resulting non-profit ESCo has three CHP and district heat networks, supplying 34 MWh of heat pa. • Carbon and cost savings are 45% in comparison with electric heating

  13. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 3: Ecological risk assessment

    International Nuclear Information System (INIS)

    The Environmental Management Division of the U.S. Army Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation (RI) and feasibility study (FS) of the J-Field area at APG, pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. As part of that activity, Argonne National Laboratory (ANL) conducted an ecological risk assessment (ERA) of the J-Field site. This report presents the results of that assessment

  14. Calculating Program for Decommissioning Work Productivity based on Decommissioning Activity Experience Data

    International Nuclear Information System (INIS)

    KAERI is performing research to calculate a coefficient for decommissioning work unit productivity to calculate the estimated time decommissioning work and estimated cost based on decommissioning activity experience data for KRR-2. KAERI used to calculate the decommissioning cost and manage decommissioning activity experience data through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). In particular, KAERI used to based data for calculating the decommissioning cost with the form of a code work breakdown structure (WBS) based on decommissioning activity experience data for KRR-2.. Defined WBS code used to each system for calculate decommissioning cost. In this paper, we developed a program that can calculate the decommissioning cost using the decommissioning experience of KRR-2, UCP, and other countries through the mapping of a similar target facility between NPP and KRR-2. This paper is organized as follows. Chapter 2 discusses the decommissioning work productivity calculation method, and the mapping method of the decommissioning target facility will be described in the calculating program for decommissioning work productivity. At KAERI, research on various decommissioning methodologies of domestic NPPs will be conducted in the near future. In particular, It is difficult to determine the cost of decommissioning because such as NPP facility have the number of variables, such as the material of the target facility decommissioning, size, radiographic conditions exist

  15. Calculating Program for Decommissioning Work Productivity based on Decommissioning Activity Experience Data

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chan-Ho; Park, Seung-Kook; Park, Hee-Seong; Moon, Jei-kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    KAERI is performing research to calculate a coefficient for decommissioning work unit productivity to calculate the estimated time decommissioning work and estimated cost based on decommissioning activity experience data for KRR-2. KAERI used to calculate the decommissioning cost and manage decommissioning activity experience data through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). In particular, KAERI used to based data for calculating the decommissioning cost with the form of a code work breakdown structure (WBS) based on decommissioning activity experience data for KRR-2.. Defined WBS code used to each system for calculate decommissioning cost. In this paper, we developed a program that can calculate the decommissioning cost using the decommissioning experience of KRR-2, UCP, and other countries through the mapping of a similar target facility between NPP and KRR-2. This paper is organized as follows. Chapter 2 discusses the decommissioning work productivity calculation method, and the mapping method of the decommissioning target facility will be described in the calculating program for decommissioning work productivity. At KAERI, research on various decommissioning methodologies of domestic NPPs will be conducted in the near future. In particular, It is difficult to determine the cost of decommissioning because such as NPP facility have the number of variables, such as the material of the target facility decommissioning, size, radiographic conditions exist.

  16. The Chinon A decommissioning plan

    International Nuclear Information System (INIS)

    The three Chinon-A reactor units have been permanently shut down. Reactor Al is now International Atomic Energy Authority level one and has been turned into a tourist museum. Reactor A2 is an IEAE level 2 site. Reactor fuel is being unloaded from reactor A3 as of July 1991. A brief description of each reactor decommissioning state is given. The decommissioning strategy for A2, drawn up in 1986 and revised in 1991 is outlined. The technical studies and their results are described. An economic analysis of decommissioning costs was also undertaken. (UK)

  17. Decommissioning of TRIGA research reactor

    International Nuclear Information System (INIS)

    Decontamination and decommissioning (D and D) of the TRIGA Mark-II and III will be a new era for the safe development of nuclear industries in Korea. The design phase of the D and D project will be carried out by a domestic engineering company associated with foreign experienced one. This strategy will give us an opportunity for the solid development of the decommissioning technologies. These experiences and the compilation of the documents will be applied for the decontamination and decommissioning of the commercial nuclear power plants in Korea. (author). 4 refs., 13 tabs., 6 figs

  18. Progress of JPDR decommissioning project

    International Nuclear Information System (INIS)

    The Japan Power Demonstration Reactor (JPDR) decommissioning project is progressively achieving its final goal; the project will be finished by March 1996 to release the JPDR's site into unrestricted use in a green field condition. The new techniques which developed or improved in R and D, the first phase of this program, have been successfully applied to the actual dismantling activities. Some decommissioning wastes have been managed as the first case of onsite shallow land burial based on the new regulatory frame of radioactive waste management. The experiences and the data obtained from the JPDR dismantling activities are expected to contribute to future decommissioning of commercial nuclear power plants. (author)

  19. Decommissioning Cost Assessment

    International Nuclear Information System (INIS)

    The future costs for dismantling, decommissioning and handling of associated radioactive waste of nuclear installations represents substantial liabilities. It is the generations that benefits from the use of nuclear installations that shall carry the financial burden. Nuclear waste programmes have occasionally encountered set-backs related to the trust from society. This has resulted in delayed, redirected or halted activities, which has the common denominator of costs increases. In modern democratic countries, information sharing, knowledge transfer and open communication about costs for the management of radioactive waste are prerequisites for the task to develop modern methods for public participation and thus to develop well-founded and justified confidence for further development of nuclear energy. Nuclear and radiation safety Authorities have a clear role to provide unbiased information on any health, safety, financial and environmental related issues. This task requires a good understanding of the values and opinion of the public, and especially those of the younger generation

  20. Decontamination & decommissioning focus area

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    In January 1994, the US Department of Energy Office of Environmental Management (DOE EM) formally introduced its new approach to managing DOE`s environmental research and technology development activities. The goal of the new approach is to conduct research and development in critical areas of interest to DOE, utilizing the best talent in the Department and in the national science community. To facilitate this solutions-oriented approach, the Office of Science and Technology (EM-50, formerly the Office of Technology Development) formed five Focus AReas to stimulate the required basic research, development, and demonstration efforts to seek new, innovative cleanup methods. In February 1995, EM-50 selected the DOE Morgantown Energy Technology Center (METC) to lead implementation of one of these Focus Areas: the Decontamination and Decommissioning (D & D) Focus Area.

  1. Power Plant decommissioning

    Directory of Open Access Journals (Sweden)

    Mažeika Jonas

    2014-11-01

    Full Text Available On a first attempt, the determination of 14C and 36Cl activity concentrations in basic operational waste (spent ion-exchange resins and perlite mixture, in decommissioning waste (construction concrete, sand, stainless steel and serpentinite and irradiated graphite from the Ignalina NPP has been performed. The samples for measurement of the specific activity of 14C and 36Cl were obtained from the selected places, where the highest values of the dose rate and the activity concentrations of gamma emitters were found. The performed study of the total 14C and 36Cl activity concentrations was based on estimated chemical forms of 14C (inorganic and organic compounds and 36Cl as Cl- ion. The tested methods used in this study were found to be suitable for estimation of activity concentrations of measured radionuclides.

  2. An analysis of decommissioning costs

    International Nuclear Information System (INIS)

    Within the OECD/NEA Cooperative Programme on Decommissioning a Task Group was set up early in 1989 to identify the reasons for the large variations in decommissioning cost estimates. The Task Group gathered cost data from 12 of the 14 projects in the Programme to form the basis of their analysis. They included reactors being decommissioned to various stages as well as fuel cycle facilities. The projects were divided into groups of projects with similar characteristics ('models') to facilitate the analysis of the cost distribution in each group of projects and the cost data was progressively refined by a dialogue between the Task Group and the project managers. A comparative analysis was then performed and project specific discrepancies were identified. The Task Group's report is summarized on the results of the comparative analysis as well as the lessons learnt by the Task Group in the acquisition and analysis of cost data from international decommissioning projects. (author) 5 tabs

  3. Decommissioning of the Loviisa NPP

    International Nuclear Information System (INIS)

    Imatran Voima Oy has revised the decommissioning plan for the Loviisa Nuclear Power Plant (Loviisa 1 and Loviisa 2) by the end of the year 1998. The thermal power of the power plant has been increased to 2x1500 MWth, and the life time has been designed to be extended to 45 years in the decommissioning plan. The decommissioning of the power plant is designed to begin in 2022 and it will be finished in 2048. The plan is based on immediate dismantlement (i.e. DECON) after the shut down of the power plant. Experienced plant personnel will still be available to lead the decommissioning work. Only the radioactive plant systems, components and structures will be dismantled and disposed of. Decommissioning wastes will be disposed into the underground disposal tunnels situating at the site in the depth of about 110 m. These tunnels are already partly ready for power plant wastes. The big and heavy reactor components, e.g. pressure vessels and steam generators, will be disposed of as such, without cutting them into smaller parts. This saves time and radiation doses. The total volume of decommissioning wastes is 14 800 m3, when packed in boxes. The manpower needed for decommissioning is about 2 800 manyears. The collective radiation dose for personnel is estimated to be about 9.2 manSv. The cost estimate of the decommissioning is about 1 117 million FIM. The spent fuel will be stored at the plant for 20 years after the shut down of the power plant. After that it will be transported from the site to the encapsulation plant for final disposal. (orig.)

  4. Decommissioning challenges - an industrial reality

    International Nuclear Information System (INIS)

    Sellafield Limited has undergone many transformations in previous years. The Nuclear Decommissioning Authority (NDA) has managed the site from April 2005, and a new Parent Body Organisation (PBO) is soon to be announced. In addition, it is an exciting time for the nuclear industry following the announcement of the UK government support new reactor builds. Should the site be selected for new build, the impact on Sellafield, its decommissioning program and economic impact on the local area can only be speculated at the current time. Every past, present and future decommissioning project at the Sellafield Limited site offers complex challenges, as each facility is unique. Specialist skills and experience must be engaged at pre-planned phases to result in a safe, efficient and successful decommissioning project. This paper provides an overview of a small selection of decommissioning projects, including examples of stakeholder engagement, plant and equipment dismantling using remote handling equipment and the application of innovative techniques and technologies. In addition, the final section provides a summary upon how future technologies required by the decommissioning projects are being assessed and developed. (authors)

  5. Decommissioning of major radioactive facilities

    International Nuclear Information System (INIS)

    The decision-making process involving the decommissioning of the UK graphite moderated, gas-cooled nuclear power stations is complex. There are timing, engineering, waste disposal, cost and lost generation capacity factors to consider and the overall decision of when and how to proceed with decommissioning may include political and public tolerance dimensions. These factors and dimensions are briefly reviewed with reference to the ageing Magnox power stations. It is concluded that the UK nuclear industry has adopted a policy of deferred decommissioning, that is delaying the process of complete dismantlement of radioactive components and assemblies for at least one hundred years following close down of the plant. In following this option the nuclear industry has expressed considerable confidence that the technology required will become available with passing time, that acceptable radioactive waste disposal methods and facilities will be available and that the eventual costs of decommissioning will not escalate without restraint. If the UK nuclear industry is to move forward with a new generation of high temperature, gas-cooled reactors then features facilitating decommissioning need to be incorporated at the design concept and detailing stages, although such decommissioning prerequisites may not be compatible with the total containment and integrated reactor pressure vessel aspects that feature so strongly in the UK reactor design philosophy. (author)

  6. An outsider's view of decommissioning

    International Nuclear Information System (INIS)

    The decommissioning of nuclear facilities is not just a technical or even a financial issue. Presenting decommissioning as a technically difficult task overcome by superhuman effort on the part of the industry will not gain much credit amongst sophisticated consumers who now require that any complex technology will work and work safely. Any engineering problems are surmountable given the money to find the solution. Some of the financial aspects of decommissioning are worrying, however, given their open-ended nature. The cost of waste disposal is one of these. Despite a lapse of fifty years since the start-up of its first reactor, the United Kingdom is unlikely to have available a repository for the disposal of intermediate level waste until about 2020. Waste disposal is a large consideration in decommissioning and the industry's forecasts of cost in this area lack credibility in the light of a poor track record in financial prediction. Financial engineering in the form of the segregated fund set up in March 1996 to cover the decommissioning of nuclear power stations in the United Kingdom is likely to provide only short term reassurance in the light of doubts about a credible future for nuclear power. This lack of confidence over the wider problems of nuclear power creates particular problems for decommissioning which go beyond technical difficulties and complicate financial considerations. (UK)

  7. Money Related Decommissioning and Funding Decision Making

    International Nuclear Information System (INIS)

    'Money makes the world go round', as the song says. It definitely influences decommissioning decision-making and financial assurance for future decommissioning. This paper will address two money-related decommissioning topics. The first is the evaluation of whether to continue or to halt decommissioning activities at Fermi 1. The second is maintaining adequacy of financial assurance for future decommissioning of operating plants. Decommissioning costs considerable money and costs are often higher than originally estimated. If costs increase significantly and decommissioning is not well funded, decommissioning activities may be deferred. Several decommissioning projects have been deferred when decision-makers determined future spending is preferable than current spending, or when costs have risen significantly. Decommissioning activity timing is being reevaluated for the Fermi 1 project. Assumptions for waste cost-escalation significantly impact the decision being made this year on the Fermi 1 decommissioning project. They also have a major impact on the estimated costs for decommissioning currently operating plants. Adequately funding full decommissioning during plant operation will ensure that the users who receive the benefit pay the full price of the nuclear-generated electricity. Funding throughout operation also will better ensure that money is available following shutdown to allow decommissioning to be conducted without need for additional funds

  8. Systematization of nuclear fuel facility decommissioning technology

    International Nuclear Information System (INIS)

    In the Ningyo-Toge Environmental Engineering Center, the nature of all decommissioning works is clarified and, as an information base for planning the promotion of efficiency of a work, the Decommissioning Engineering System is being developed. The Decommissioning Engineering System consists of a function for performing work support for a decommissioning, a function for gathering information results of the decommissioning technology and a general evaluation function for the decommissioning plan on the basis of facilities information collected by three-dimensional CAD. (author)

  9. Desempenho em confinamento de machos bovinos inteiros Canchim, Aberdeen angus e cruzamentos recíprocos Feedlot performance of canchim, aberdeen angus and reciprocal crossbred males

    OpenAIRE

    Daniel Perotto; José Luiz Moletta; Carlos Lesskiu

    2002-01-01

    Foram analisados o consumo diário de matéria seca (MS) por 100kg de peso vivo (CMS), a conversão alimentar (CA) e o ganho de peso médio diário (GMD) de 118 machos bovinos inteiros Canchim (Cn), Aberdeen Angus (Ab) e cruzamentos recíprocos (CnAb (F1, 3/4Cn+1/4Ab, 5/8Cn+3/8Ab e 11/16Cn+5/16Ab) e AbCn (F1, 5/8Ab+3/8Cn e 11/16Ab+5/16Cn)). Esses animais foram alimentados em baias individuais por 84 a 95 dias com silagem de milho à vontade mais concentrado (17,8% de PB e 79% de NDT) fornecido à bas...

  10. National provisions for decommissioning and managing radioactive waste from decommissioning

    International Nuclear Information System (INIS)

    Large quantities of radioactive waste resulting from decommissioning activities of nuclear research reactors and nuclear power plant units will be generated in Romania in the near and distant future. The actual policy and strategy in the field of the management of radioactive waste in Romania are based on the stipulations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, ratified in Romania by the Law No. 105/1999. The paper gives an introduction of the current policy and strategy applied in Romania for nuclear decommissioning process and management of radioactive waste. The paper points out some key aspects of the national provisions concerning the nuclear decommissioning activities and management of the resulting radioactive waste: the legal framework, the responsibilities of the national authorities and of the licence holders, the main radioactive waste generators, the financing and budgeting mechanisms, etc. (author)

  11. The Tokai NPP decommissioning technique

    International Nuclear Information System (INIS)

    Tokai power station was closed down in March 1998 and started decommissioning from December 2001 as a pioneer of NPP decommissioning. This article presented current state of Tokai NPP decommissioning technique. As the second stage of decommissioning works, removal works of steam raising unit (four units of heat exchangers) were started from 2006 by jacking down method with decommissioning data accumulated. Each heat exchanger was divided into top head, seven 'tears' of shell and bottom head. Each 'tear' was out and separated into a cylinder, and then divided into two by remote-operated cutting equipment with manipulators for gas cutting and motor disk cutting under monitoring works by fixed and mobile cameras. Divided 'tear' was further cut into center baffle plate, heat transfer tubes and fine pieces of shell. Cutting works would produce radioactive fine particles, which were filtered by temporary ventilation equipment with exhaust fan and filters. Appropriate works using existing technique combined and their rationalization were important at this stage. (T. Tanaka)

  12. Costs of Decommissioning Nuclear Power Plants

    International Nuclear Information System (INIS)

    While refurbishments for the long-term operation of nuclear power plants and for the lifetime extension of such plants have been widely pursued in recent years, the number of plants to be decommissioned is nonetheless expected to increase in future, particularly in the United States and Europe. It is thus important to understand the costs of decommissioning so as to develop coherent and cost-effective strategies, realistic cost estimates based on decommissioning plans from the outset of operations and mechanisms to ensure that future decommissioning expenses can be adequately covered. This study presents the results of an NEA review of the costs of decommissioning nuclear power plants and of overall funding practices adopted across NEA member countries. The study is based on the results of this NEA questionnaire, on actual decommissioning costs or estimates, and on plans for the establishment and management of decommissioning funds. Case studies are included to provide insight into decommissioning practices in a number of countries. (authors)

  13. 77 FR 41107 - Decommissioning Planning During Operations

    Science.gov (United States)

    2012-07-12

    ... Decommissioning Planning Rule (DPR) (June 17, 2011, 76 FR 33512). The DPR applies to the operational phase of a..., ``Decommissioning Planning During Operations'' (December 13, 2011, 76 FR 77431). The NRC received more than...

  14. Decommissioning planning of Swedish nuclear power plants

    International Nuclear Information System (INIS)

    The technologies required for the decommissioning work are for the most part readily proven. Taken into account that there will be many more years before the studied reactor units will undergo decommissioning, the techniques could even be called conventional at that time. This will help bring the decommissioning projects to a successful closure. A national waste fund is already established in Sweden to finance amongst others all dismantling and decommissioning work. This will assure that funding for the decommissioning projects is at hand when needed. All necessary plant data are readily available and this will, combined with a reliable management system, expedite the decommissioning projects considerably. Final repositories for both long- and short-lived LILW respectively is planned and will be constructed and dimensioned to receive the decommissioning waste from the Swedish NPP:s. Since the strategy is set and well thought-through, this will help facilitate a smooth disposal of the radioactive decommissioning waste. (orig.)

  15. Phenix Decommissioning Project - Overview

    International Nuclear Information System (INIS)

    The first heading of your manuscript must be 'Introduction'. Phenix is the only remaining French fast breeder reactor after the shutdown of Superphenix (1999) and Rapsodie (1983). Phenix is located inside the Marcoule nuclear site along the Rhone river near Bagnols-sur-Ceze in southeastern France. Phenix is one of the facilities belonging the French Atomic Energy Commission (CEA) on the Marcoule site. It is a fast breeder reactor (FBR) developed at the end of the 1960's. that has been in operation since 1973 and was connected to the power grid in 1974. It is a second generation prototype developed while the first generation FBR, Rapsodie, was still in operation. Phenix is a 250 electrical MW power plant. During the first 20 years of operation, its main aim was to demonstrate the viability of sodium-cooled FBRs. Since the 1991 radioactive waste management act, Phenix has become an irradiation tool for the actinide transmutation program. To extend its operating life for 6 additional cycles, it was necessary to refurbish the plant; this involved major work performed from 1999 to 2003 at a total cost of about 250 M??. Today, with a realistic expectation, the final shutdown is planned for the beginning of 2009. The main objective of the Phenix dismantling project is to eliminate all the process equipment and clean all the building to remove all the radioactive zones. To reach this objective, three main hazards must be eliminated: Fuel (criticality hazard), Sodium, Radioactive equipment. The complexity of decommissioning a facility such as Phenix is increased by: - the lack of storage facility for high radioactive material, - the decision to treat all the radioactive sodium and sodium waste inside the plant, - the very high irradiation of the core structures due to the presence of cobalt alloys. On the other hand, Phenix plant is still under operating with a qualified staff and the radioactivity coming from structural activation is well known. After the final shutdown, the first operations will be conducted by the same staff under the same safety report. Another interesting fact is that the decommissioning funds project exist and are available. The CEA decided to begin the dismantling phase without waiting because after a period of decay it is not really cheaper or easier to work. This approach needs interim storage facilities not long after the final shutdown. For the low- and intermediate-level radioactive waste there are national storage centers but for the high-level wastes, each operator must manage its waste until a suitable disposal site is available. At Marcoule a new storage facility is now being designed and scheduled to begin operating after 2013-2014. After removal of the fuel and core elements, the primary sodium will be drained and eliminated by a carbonation process. To ensure biological shielding, the reference scenario calls for filling the primary vessel with water. The most radioactive structures (dia-grid and core support) will be cut up with remote tools, after which the rest of the structure will be cut up manually. Phenix contains about 1450 metric tons of sodium. The CEA initially planned to build ATENA, a new facility for all radioactive sodium waste from R and D and FBR facilities. For various reasons, but mainly to save money, the CEA decided to treat all radioactive sodium and sodium waste in the framework of the Phenix dismantling project. There are no real difficulties in the dismantling schedule because of the advanced state of development of the processes selected for the ATENA project. Because of the knowledge already obtained, the issues concern project management, waste management and human resources reduction more than technical challenge

  16. Decommissioning: a problem or a challenge?

    OpenAIRE

    Mele Irena

    2004-01-01

    With the ageing of nuclear facilities or the reduced interest in their further operation, a new set of problems, related to the decommissioning of these facilities, has come into forefront. In many cases it turns out that the preparations for decommissioning have come too late, and that financial resources for covering decommissioning activities have not been provided. To avoid such problems, future liailities should be thoroughly estimated in drawing up the decommissioning and waste manageme...

  17. The Italian decommissioning industry

    International Nuclear Information System (INIS)

    Full text: Italy's step out from nuclear activities in 1987 deeply affected an industry that, in the previous years, had managed to grow up in quality and technology levels to meet the nuclear standards. Only a few companies were able to partially retain their skills through activities abroad. The decommissioning program represents a new challenge for the Italian industry at large and will require a consistent effort to properly qualify the potential suppliers. On the other side, a program with such implications in terms of investments and so depending from social aspects cannot be effectively implemented without a significant involvement of the local industry. Essential conditions for the success are a reliable program, as well as a careful supply management scheme, which must facilitate aggregation of skills spread among different subjects. 'Human Resources: Maintaining a Nuclear Culture in Italy' Bruno Panella Politecnico di Torino, Giuseppe Forasassi, Universita di Pisa, Inter-University Consortium for the Nuclear Technological Research (CIRTEN). After a brief history of the nuclear engineering education in Italy within the international and national nuclear energy scenario, the present situation, with reference to the Italian universities, is shown. In order to maintain a nuclear culture in Italy the solution, exploited with different peculiarities in each University, is to carry out high quality research activities in reciprocal collaboration (mostly within the CIRTEN inter university Consortium) as well as with the Industry and research Organisations and to collaborate actively in establishing a stable network and a synergy of teaching activities in Europe in the field of Nuclear Engineering Education. The aim is to maintain at a high level and as updated as possible the Italian educational offer in nuclear engineering and also to attract the best students for the enrolment. (author)

  18. An apparatus for studying spallation neutrons in the Aberdeen Tunnel laboratory

    International Nuclear Information System (INIS)

    In this paper, we describe the design, construction and performance of an apparatus installed in the Aberdeen Tunnel laboratory in Hong Kong for studying spallation neutrons induced by cosmic-ray muons under a vertical rock overburden of 611 m water equivalent (m.w.e.). The apparatus comprises six horizontal layers of plastic-scintillator hodoscopes for determining the direction and position of the incident cosmic-ray muons. Sandwiched between the hodoscope planes is a neutron detector filled with 650 kg of liquid scintillator doped with about 0.06% of Gadolinium by weight for improving the efficiency of detecting the spallation neutrons. Performance of the apparatus is also presented

  19. Sedimentology of the Teekloof formation to the east of Aberdeen (C.P.) with reference to uranium mineralization

    International Nuclear Information System (INIS)

    An area to the immediate east of Aberdeen (C.P.), banded in the north by the Rooiberge and to the east by the Sundays River, has been sedimentologically studied. A notable feature of the sediments investigated, is the presence of linear zones of increased sandstone. Some of the sediments also showed an exessive volume of argillaceous rocks. The sandstones cropping out in the Aberdeen District may be classified as lithic arkoses. Due to the manner in which the detrital grains appear to 'float' in calcite, an expansive growth mechanism is envisaged. This implies early crystallization of calcite, and emplacement of uranium

  20. Development of decommissioning system engineering technology

    International Nuclear Information System (INIS)

    In the decommissioning planning stage, it is important to select the optimized decommissioning process considering the cost and safety. Especially the selection of the optimized decommissioning process is necessary because it affects to improve worker's safety and decommissioning work efficiency. The decommissioning process evaluation technology can provide the optimized decommissioning process as constructing various decommissioning scenarios and it can help to prevent the potential accidents as delivering the exact work procedures to workers and to help workers to perform decommissioning work skillfully. It's necessary to measure the radioactive contamination in the highly contaminated facilities such as hot-cells or glove-boxes to be decommissioned for decommissioning planning. These facilities are very high radiation level, so it is difficult to approach. In this case the detector system is preferable to separate the sensor and electronics, which have to locate in the facility outside to avoid the electric noise and worker's radiation exposure. In this project, we developed the remote detection system for radiation measurement and signal transmission in the high radiation area. In order to minimize worker's exposure when decommissioning highly activated nuclear facilities, it is necessary to develop the remote handling tool to perform the dismantling work remotely. Especially, since cutting, measuring, and decontamination works should be performed remotely in the highly activated area, the remote handling tool for conducting these works should be developed. Therefore, the multi-purpose dismantling machine that can measuring dose, facility cutting, and remote handling for maintenance and decommissioning of highly activated facility should be needed

  1. Redevelopment of nuclear facilities after decommissioning

    International Nuclear Information System (INIS)

    Being aware of reuse options for decommissioned sites is an important aspect of the decommissioning process. Early planning for site reuse can facilitate the transition from operation to decommissioning, possibly reduce the financial burden associated with decommissioning, re-employ workers and specialist staff, and alleviate the overall impact of decommissioning on the local community. Conversely, the lack of early planning for site reuse after completion of the decommissioning process can become a hindrance to implementing decommissioning in a cost effective and optimized manner. This strategic inadequacy may be caused by insufficient knowledge of experience with redevelopment opportunities that were exploited successfully in industries elsewhere. This report provides an overview of decommissioning projects implemented worldwide with reuse of the decommissioned sites for new purposes after delicensing. Lessons learned from these projects and practical guidance on factors creating reuse opportunities are highlighted. Operators of nuclear facilities, decision makers at government level, regulators/authorities and elected officials at all levels, environmental planners and the general public are all important stakeholders in the site redevelopment process. The subject area addressed in this report has not previously been addressed in IAEA publications on decommissioning except in only a marginal fashion. This report is intended to contribute to the systematic coverage of the entire range of decommissioning aspects within the IAEA's decommissioning programme

  2. Platform decommissioning. Environmental challenges and practical solutions

    International Nuclear Information System (INIS)

    The publication gives a short introduction of platform decommissioning, followed by an overview of what to be decommissioned and removed. This will be followed by some of the vital technologies and methods within decommissioning, abandonment of wells, removal and handling of remains that is reuse and scrapping. A final presentation with a view of current research and developments is given. 3 figs

  3. Seminar on decommissioning at Visby 1983

    International Nuclear Information System (INIS)

    The Swedish National Institute of Radiation Protection arranged a nordic seminar on decommissioning of nuclear facilities. Current experience from decommissioning of a reprocessing pilot plant, and from research reactors were presented. Strategies for decommissioning and for deposition after early and after late shut-down of reactors was discussed. Research priorities were assessed. (P.Aa.)

  4. Fort St. Vrain decommissioning experience

    International Nuclear Information System (INIS)

    Nuclear plant decommissioning represents a significant expenditure of time and resources for nuclear utilities. Public Service Company of Colorado (PSC) is in the process of completing the decommissioning of the Fort St. Vrain (FSV) Nuclear Station, the first large-scale commercial nuclear plant to be decommissioned under the U.S. Nuclear Regulatory Commission's (NRC's) 1988 decommissioning rule. PSC's experience has included dispositioning spent fuel, choosing a decommissioning alternative, and actively decommissioning the plant from dismantlement and decontamination through final survey. When the plant was prematurely shut down in August 1989, PSC's initial task was to find a storage location for FSV's spent fuel. PSC had a contract with the U.S. Department of Energy (DOE) to ship FSV spent fuel to the Idaho National Engineering Laboratory (INEL), and all previously removed spent fuel had been shipped there. However, Idaho legally blocked further FSV spent-fuel shipments to INEL, and PSC decided to license and build an on-site, passively cooled independent spent-fuel storage installation (ISFSI). By June 1992, all FSV spent fuel was transferred from the reactor building to the ISFSI. PSC has been able to use low-level radioactive waste (LLWR) disposal facilities in the Northwest Compact, and disposal costs are within estimates. Industrial and radiological safety have been emphasized throughout the project, and performance in these areas has been outstanding. PSC has obtained NRC Aprilproval of a final survey plan that allows for many of the plant's components and systems to remain in place, and final survey activities are nearing completion. PSC is in the process of repowering the facility with natural gas-fired combustion turbines and heat recovery boilers. The first combustion turbine was placed in service Ap 30, 1996

  5. Quality assurance program for decommissioning

    International Nuclear Information System (INIS)

    Defining the quality assurance program for the US Dept. of Energy Shippingport Station Decommissioning Project (SSDP) was a unique opportunity because this is the first full-sized commercial nuclear power plant to be decommissioned. General Electric Co. defined a quality assurance program that provided adequate control, yet was stripped down to the essentials. The program is designed to provide a flexible degree of monitoring of subcontractor work, built around a core of radiation safety monitoring, detailed planning, inspection, and auditing, and operated with a minimum of dedicated personnel. This paper concentrates on the traditional quality assurance activities

  6. Decommissioning strategy for Brennilis France

    International Nuclear Information System (INIS)

    Brennilis is a heavy water moderated - gas cooled reactor with a capacity of 70 MWe. It is located in Brittany and has been jointly operated from 1967 to 1985 by EDF and CEA as an industrial prototype. The reactor was definitely shutdown in 1985. At that time, the decommissioning strategy was to reach the level 2 defined by IAEA for the decommissioning of nuclear facilities, i.e. partial and conditional release of the installation, about ten years after final shutdown and then leave the reactor building in safe store condition for about 30 to 40 years to benefit from radioactive decay. (author)

  7. Decommissioning Experience: Chalk River, Canada

    International Nuclear Information System (INIS)

    Full text: Atomic Energy of Canada Limited has reported that work has continued on the decommissioning of old structures on the Chalk River laboratory site. An environmental assessment was approved in 2006 for the decommissioning of the NRX reactor fuel bays (A and B). The regulator approved two work packages for the removal of water and the wooden structure over the bays. The A bays were cleaned as far as possible and were emptied in 2007. Decontamination work will continue. Sections of the B bays were filled with sand and other parts filled with water. NRX is currently in storage (i.e. a dormant state) with surveillance. (author)

  8. Basic Research about Calculation of the Decommissioning Unit Cost based on The KRR-2 Decommissioning Project

    International Nuclear Information System (INIS)

    The KAERI be used to calculate the decommissioning cost and manage the data of decommissioning activity experience through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). Some country such as Japan and The United States have the information for decommissioning experience of the NPP and publish reports on decommissioning cost analysis. These reports as valuable data be used to compare with the decommissioning unit cost. In particular, need a method to estimate the decommissioning cost of the NPP because there is no decommissioning experience of NPP in case of Korea. makes possible to predict the more precise prediction about the decommissioning unit cost. But still, there are many differences on calculation for the decommissioning unit cost in domestic and foreign country. Typically, it is difficult to compare with data because published not detailed reports. Therefore, field of estimation for decommissioning cost have to use a unified framework in order to the decommissioning cost be provided to exact of the decommissioning cost

  9. Basic Research about Calculation of the Decommissioning Unit Cost based on The KRR-2 Decommissioning Project

    Energy Technology Data Exchange (ETDEWEB)

    Song, Chan-Ho; Park, Hee-Seong; Ha, Jea-Hyun; Jin, Hyung-Gon; Park, Seung-Kook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    The KAERI be used to calculate the decommissioning cost and manage the data of decommissioning activity experience through systems such as the decommissioning information management system (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), decommissioning work-unit productivity calculation system (DEWOCS). Some country such as Japan and The United States have the information for decommissioning experience of the NPP and publish reports on decommissioning cost analysis. These reports as valuable data be used to compare with the decommissioning unit cost. In particular, need a method to estimate the decommissioning cost of the NPP because there is no decommissioning experience of NPP in case of Korea. makes possible to predict the more precise prediction about the decommissioning unit cost. But still, there are many differences on calculation for the decommissioning unit cost in domestic and foreign country. Typically, it is difficult to compare with data because published not detailed reports. Therefore, field of estimation for decommissioning cost have to use a unified framework in order to the decommissioning cost be provided to exact of the decommissioning cost.

  10. Air monitoring for volatile organic compounds at the Pilot Plant Complex, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, J.F.; O`Neill, H.J.; Raphaelian, L.A.; Tomczyk, N.A.; Sytsma, L.F.; Cohut, V.J.; Cobo, H.A.; O`Reilly, D.P.; Zimmerman, R.E.

    1995-03-01

    The US Army`s Aberdeen Proving Ground has been a test site for a variety of munitions, including chemical warfare agents (CWA). The Pilot Plant Complex (PPC) at Aberdeen was the site of development, manufacture, storage, and disposal of CWA. Deterioration of the buildings and violations of environmental laws led to closure of the complex in 1986. Since that time, all equipment, piping, and conduit in the buildings have been removed. The buildings have been declared free of surface CWA contamination as a result of air sampling using the military system. However, no air sampling has been done to determine if other hazardous volatile organic compounds are present in the PPC, although a wide range of toxic and/or hazardous materials other than CWA was used in the PPC. The assumption has been that the air in the PPC is not hazardous. The purpose of this air-monitoring study was to screen the indoor air in the PPC to confirm the assumption that the air does not contain volatile organic contaminants at levels that would endanger persons in the buildings. A secondary purpose was to identify any potential sources of volatile organic contaminants that need to be monitored in subsequent sampling efforts.

  11. Ecological survey of M-Field, Edgewood Area Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Downs, J.L.; Eberhardt, L.E.; Fitzner, R.E.; Rogers, L.E.

    1991-12-01

    An ecological survey was conducted on M-Field, at the Edgewood Area, Aberdeen Proving Ground, Maryland. M-Field is used routinely to test army smokes and obscurants, including brass flakes, carbon fibers, and fog oils. The field has been used for testing purposes for the past 40 years, but little documented history is available. Under current environmental regulations, the test field must be assessed periodically to document the presence or potential use of the area by threatened and endangered species. The M-Field area is approximately 370 acres and is part of the US Army`s Edgewood Area at Aberdeen Proving Ground in Harford County, Maryland. The grass-covered field is primarily lowlands with elevations from about 1.0 to 8 m above sea level, and several buildings and structures are present on the field. The ecological assessment of M-Field was conducted in three stages, beginning with a preliminary site visit in May to assess sampling requirements. Two field site visits were made June 3--7, and August 12--15, 1991, to identify the biota existing on the site. Data were gathered on vegetation, small mammals, invertebrates, birds, large mammals, amphibians, and reptiles.

  12. Ecological survey of M-Field, Edgewood Area Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Downs, J.L.; Eberhardt, L.E.; Fitzner, R.E.; Rogers, L.E.

    1991-12-01

    An ecological survey was conducted on M-Field, at the Edgewood Area, Aberdeen Proving Ground, Maryland. M-Field is used routinely to test army smokes and obscurants, including brass flakes, carbon fibers, and fog oils. The field has been used for testing purposes for the past 40 years, but little documented history is available. Under current environmental regulations, the test field must be assessed periodically to document the presence or potential use of the area by threatened and endangered species. The M-Field area is approximately 370 acres and is part of the US Army's Edgewood Area at Aberdeen Proving Ground in Harford County, Maryland. The grass-covered field is primarily lowlands with elevations from about 1.0 to 8 m above sea level, and several buildings and structures are present on the field. The ecological assessment of M-Field was conducted in three stages, beginning with a preliminary site visit in May to assess sampling requirements. Two field site visits were made June 3--7, and August 12--15, 1991, to identify the biota existing on the site. Data were gathered on vegetation, small mammals, invertebrates, birds, large mammals, amphibians, and reptiles.

  13. Decommissioning Study of Oskarshamn NPP

    International Nuclear Information System (INIS)

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

  14. A Decommissioning Information Management System

    Energy Technology Data Exchange (ETDEWEB)

    Park, S. K.; Hong, S. B.; Chung, U. S.; Park, J. H. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2007-07-01

    In 1996, it was determined that research reactors, the KRR-1 and the KRR-2, would be shut down and dismantled. A project for the decommissioning of these reactors was launched in January 1997 with the goal of a completion by 2008. The total budget of the project was 19.4 million US dollars, including the cost for the waste disposal and for the technology development. The work scopes during the decommissioning project were the dismantling of all the facilities and the removal of all the radioactive materials from the reactor site. After the removal of the entire radioactivity, the site and buildings will be released for an unconditional use. A separate project for the decommissioning of the uranium conversion plant was initiated in 2001. The plant was constructed for the development of the fuel manufacturing technologies and the localization of nuclear fuels in Korea. It was shut downed in 1993 and finally it was concluded in 2000 that the plant would be decommissioned. The project will be completed by 2008 and the total budget was 9.2 million US dollars. During this project, all vessels and equipment will be dismantled and the building surface will be decontaminated to be utilized as general laboratories.

  15. 76 FR 35511 - Decommissioning Planning

    Science.gov (United States)

    2011-06-17

    ... regulations in 1997 as Subpart E of 10 CFR part 20 (62 FR 39058; July 21, 1997). This set of requirements is... the January 27, 1988 (53 FR 24018), rule on planning for decommissioning require licensees to provide... contamination and the amount of funds set aside and expended on cleanup. (62 FR 39082; July 21, 1997)....

  16. Decommissioning study of Forsmark NPP

    International Nuclear Information System (INIS)

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

  17. Options for Steam Generator Decommissioning

    International Nuclear Information System (INIS)

    Selecting the best option for decommissioning steam generators is a key consideration in preparing for decommissioning PWR nuclear power plants. Steam Generators represent a discrete waste stream of large, complex items that can lend themselves to a variety of options for handling, treatment, recycling and disposal. Studsvik has significant experience in processing full size Steam Generators at its metal recycling facility in Sweden, and this paper will introduce the Studsvik steam generator treatment concept and the results achieved to date across a number of projects. The paper will outline the important parameters needed at an early stage to assess options and to help consider the balance between off-site and on-site treatment solutions, and the role of prior decontamination techniques. The paper also outlines the use of feasibility studies and demonstration projects that have been used to help customers prepare for decommissioning. The paper discusses physical, radiological and operational history data, Pro and Contra factors for on- and off-site treatment, the role of chemical decontamination prior to treatment, planning for off-site shipments as well as Studsvik experience This paper has an original focus upon the coming challenges of steam generator decommissioning and potential external treatment capacity constraints in the medium term. It also focuses on the potential during operations or initial shut-down to develop robust plans for steam generator management. (authors)

  18. Decommissioning Study of Oskarshamn NPP

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-06-15

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

  19. Decommissioning study of Forsmark NPP

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-06-15

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

  20. A Decommissioning Information Management System

    International Nuclear Information System (INIS)

    In 1996, it was determined that research reactors, the KRR-1 and the KRR-2, would be shut down and dismantled. A project for the decommissioning of these reactors was launched in January 1997 with the goal of a completion by 2008. The total budget of the project was 19.4 million US dollars, including the cost for the waste disposal and for the technology development. The work scopes during the decommissioning project were the dismantling of all the facilities and the removal of all the radioactive materials from the reactor site. After the removal of the entire radioactivity, the site and buildings will be released for an unconditional use. A separate project for the decommissioning of the uranium conversion plant was initiated in 2001. The plant was constructed for the development of the fuel manufacturing technologies and the localization of nuclear fuels in Korea. It was shut downed in 1993 and finally it was concluded in 2000 that the plant would be decommissioned. The project will be completed by 2008 and the total budget was 9.2 million US dollars. During this project, all vessels and equipment will be dismantled and the building surface will be decontaminated to be utilized as general laboratories

  1. Decommissioning: a problem or a challenge?

    Directory of Open Access Journals (Sweden)

    Mele Irena

    2004-01-01

    Full Text Available With the ageing of nuclear facilities or the reduced interest in their further operation, a new set of problems, related to the decommissioning of these facilities, has come into forefront. In many cases it turns out that the preparations for decommissioning have come too late, and that financial resources for covering decommissioning activities have not been provided. To avoid such problems, future liailities should be thoroughly estimated in drawing up the decommissioning and waste management programme for each nuclear facility in time, and financial provisions for implementing such programme should be provided. In this paper a presentation of current decommissioning experience in Slovenia is given. The main problems and difficulties in decommissioning of the Žirovski Vrh Uranium Mine are exposed and the lesson learned from this case is presented. The preparation of the decommissioning programme for the Nuclear Power Plant Krško is also described, and the situation at the TRIGA research reactor is briefly discussed.

  2. Shippingport Station Decommissioning Project Technology Transfer Program

    International Nuclear Information System (INIS)

    The Shippingport Station Decommissioning Project (SSDP) is the first commercial size nuclear power plant to undergo decommissioning in the United States. One of the objectives in decommissioning the plant is to demonstrate the technology used and thoroughly document the results for dissemination to utilities, government entities, the nuclear industry, and the decommissioning community. The Project is funded and managed by the Department of Energy (DOE). DOE has established a Technology Transfer Program to assure that useful information compiled on the project; such as, management techniques, radiological controls, decommissioning methods, lessons learned and other special studies and tests, expected to be of interest to the industry, is adequately documented and available to outside parties or participants. The Shippingport decommissioning experience will create a significant data base for the nuclear utility industry in future decommissioning of commercial nuclear power generating facilities

  3. Assessment of foreign decommissioning technology with potential application to US decommissioning needs

    International Nuclear Information System (INIS)

    This study was conducted by the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) to identify and technically assess foreign decommissioning technology developments that may represent significant improvements over decommissioning technology currently available or under development in the United States. Technology need areas for nuclear power reactor decommissioning operations were identified and prioritized using the results of past light water reactor (LWR) decommissioning studies to quantitatively evaluate the potential for reducing cost and decommissioning worker radiation dose for each major decommissioning activity. Based on these identified needs, current foreign decommissioning technologies of potential interest to the US were identified through personal contacts and the collection and review of an extensive body of decommissioning literature. These technologies were then assessed qualitatively to evaluate their uniqueness, potential for a significant reduction in decommissioning costs and/or worker radiation dose, development status, and other factors affecting their value and applicability to US needs

  4. Comparison of composition and quality traits of meat from young finishing bulls from Belgian Blue, Limousin and Aberdeen Angus breeds.

    Science.gov (United States)

    Cuvelier, C; Clinquart, A; Hocquette, J F; Cabaraux, J F; Dufrasne, I; Istasse, L; Hornick, J L

    2006-11-01

    Thirty-six young finishing bulls from three breeds (Belgian Blue, Limousin and Aberdeen Angus) were fattened over five months with finishing diets based either on sugar-beet pulp or on cereals. Nutritional quality traits of meat - fat content and fatty acid composition with emphasis on the n-6 and n-3 polyunsaturated fatty acids - along with some organoleptic quality traits were measured. The Belgian Blue bulls had the lowest intramuscular fat content associated with lower saturated and monounsaturated fatty acid contents. The polyunsaturated fatty acid content did not differ to a large extent between the breeds, the Aberdeen Angus bulls showing slightly higher values. Relative to energy intake, the overall contribution of meat to the n-3 fatty acid recommended intake was small, whatever the breed. By contrast, the contribution of meat to daily fat intake was of greater importance, especially for the Aberdeen Angus bulls. The quality traits of meat varied also according to the breed: compared to the Aberdeen Angus, the Belgian Blue bull meat had the stablest colour, the highest drip and the lowest cooking losses. The meat of Limousin bulls had intermediate characteristics for all the parameters. PMID:22063057

  5. Nuclear decommissioning in Italy

    International Nuclear Information System (INIS)

    Italy is in a unique position. Italy has been in the past among the leading countries in the pacific use of nuclear energy, but, as a consequence of the 1987 referendum decided to shutdown all operating power plants, to leave uncompleted the plants under construction and to stop all related research and industrial activities declaring a 5 years moratorium on any future initiative. The moratorium ended unnoticed in 1992, since there was no political move to restart nuclear power in Italy and, in practice, it is still acting. Therefore, now the major efforts in the nuclear field are focused on the closure of past liabilities assuring safety and security highest levels. This is a duty to be carried out by the generation that used this form of energy, but, at least for somebody, also a precondition for the acceptance of any future renaissance of nuclear energy in Italy. SOGIN is a Company carrying out a service for the country and fully committed to solve the liabilities left by the interrupted nuclear industry in Italy. To this aim SOGIN is managed as a private company to assure the highest possible efficiency, but, at the same time, is driven by moral and ethical objectives and the vision of protecting the environment and health and safety of the public. SOGIN blends in a synergic way the various ENEL experiences (design and operation of NPP's) and ENEA experiences (engineering and operation of R and D and industrial facilities supporting NPP's). Such a comprehensive combination of technical competences should not be dispersed in the medium and long term and the management is committed to facilitate the technical growth of the impressing number of motivated young people joining the Company, whose enthusiasm is contaminating every day also the 'veterans', to assure for the country an asset and a presidium of very specialized multi-disciplinary nuclear competences. Speaking of possible scenarios for the future, we should mention that the current international situation in the oil market, both in terms of barrel cost and in terms of security of supplies, and the severe black-outs that have plagued also Italy (the major one in September 2003 lasting in some areas for about 24 hours), have started a widespread discussion about energy alternatives and strategic energy plans. In this frame an increasing number of politicians and scientists are calling for a reconsideration of nuclear energy as a viable option also for Italy in a new energy mix. It is clear that public acceptance of nuclear energy is strictly connected not only to the demonstration of high safety standards of future plants, but also to the solution of radioactive waste disposal and of plant decommissioning. This is the link that could make the SOGIN mission even more strategic for the country

  6. Considerations about the European Decommissioning Academy (EDA)

    International Nuclear Information System (INIS)

    According to analyses presented at EC meeting focused on decommissioning organized at 11.9.2012 in Brussels, it was stated that at least 500 new international experts for decommissioning will be needed in Europe up to 2025, which means about 35 per year.Having in mind the actual EHRO-N report from 2013 focused on operation of nuclear facilities and an assumption that the ratio between nuclear experts, nuclearized and nuclear aware people is comparable also for decommissioning (16:74:10), as well as the fact that the special study branch for decommissioning in the European countries almost does not exist, this European Decommissioning Academy (EDA) could be helpful in the overbridging this gap.For the first run of the EDA scheduled on 2014 we would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future in Europe.A graduate of the European Decommissioning Academy (EDA) should have at least bachelor level from technical or natural science Universities or Colleges and at least one year working experiences in the area of NPP decommissioning or nuclear power engineering. This study creates prerequisites for acquiring and completion of professional and specialized knowledge in the subjects which are described. (authors)

  7. Decommissioning strategies and programme developments of Japan

    International Nuclear Information System (INIS)

    As of August 2003, there are 52 nuclear power plants in operation producing approximately 35% electricity of total supply in Japan. The Japan Atomic Power Company decided to shutdown the Tokai-1 Power Station (Gas cooled reactor, 166 MWe) at the end of March in 1998 due to the economical reasons such as increase in operation and repair costs. The Fugen reactor, which is a prototype of an advanced thermal reactor, also was shutdown at the end of March in 2003 because of the completion of its initial objectives. In order to ensure stable supply of nuclear energy in the future, decommissioning of retired nuclear facilities is indispensable in Japan for securing sites for the next facilities. Therefore, early dismantling of nuclear power plant facilities after shutdown is required as Japanese basic policy on decommissioning. Based on this basic policy, research and development programs have actively been conducted in both government organizations and private sectors in recent years. Regulatory systems for decommissioning nuclear facilities including waste managements have progressed in the regulatory side taking these situations into account. Decommissioning of nuclear facilities is now getting one of the important issues of nuclear power in Japan. This paper describes the strategies and programs of the decommissioning in Japan. The paper has the following sections: 1. Introduction; 2. National policy on decommissioning; 3. Regulation; 4. Funding; 5. Decommissioning programs; 5.1. JPDR Decommissioning Project; 5.2. Tokai-1 Power Station Decommissioning Project; 5.3. Fugen Decommissioning Project; 6. Technology Development; 7. Radioactive waste management

  8. Status of the NRC Decommissioning Program

    Energy Technology Data Exchange (ETDEWEB)

    Orlando, D. A.; Camper, L.; Buckley, J.; Pogue, E.; Banovac, K.

    2003-02-24

    On July 21, 1997, the U.S. Nuclear Regulatory Commission (NRC) published the final rule on Radiological Criteria for License Termination (the License Termination Rule or LTR) as Subpart E to 10 CFR Part 20. NRC regulations require that materials licensees submit Decommissioning Plans to support the decommissioning of its facility if it is required by license condition, or if the procedures and activities necessary to carry out the decommissioning have not been approved by NRC and these procedures could increase the potential health and safety impacts to the workers or the public. NRC regulations also require that reactor licensees submit Post-shutdown Decommissioning Activities Reports and License Termination Plans to support the decommissioning of nuclear power facilities. This paper provides an update on the status of the NRC's decommissioning program that was presented during WM'02. It discusses the staff's current efforts to streamline the decommissioning process, current issues being faced in the decommissioning program, such as partial site release and restricted release of sites, as well as the status of the decommissioning of complex sites and those listed in the Site Decommissioning Management Plan. The paper discusses the status of permanently shut-down commercial power reactors and the transfer of complex decommissioning sites and sites listed on the SDMP to Agreement States. Finally the paper provides an update of the status of various tools and guidance the NRC is developing to assist licensees during decommissioning, including an effort to consolidate and risk-inform decommissioning guidance.

  9. Planning activities for ANPP decommissioning

    International Nuclear Information System (INIS)

    The Armenian NPP consists of two WWER-440, model 270 pressurized water reactors. After an earthquake in northern Armenia in December 1988 both units were shut down for safety reasons: Unit 1 in February 1988, Unit 2 in March 1989, respectively. Unit 2 was restarted in November 1995 after a number of safety upgrades. Unit 1 remains in a long-term shutdown mode. The design lifetime of Unit 2 expires in 2015. Opportunity to shutdown earlier has been discussed in the last years. In particular a statement has been issued by EC asking for an early shutdown of Unit 2 in exchange for the TACIS support in implementing the safety upgrades in a short term. Currently the safety improvement program is being successfully implemented in the framework of US DOE and TACIS assistance. At the moment the date of the permanent plant shutdown is not specified. As with many older reactors throughout the world, a decommissioning plan has not been developed for Armenian NPP at the design stage. After shutdown of ANPP in 1988-1989 the radiological characterization campaign at Unit 1 had been carried out. Recently two studies in the decommissioning area have been performed for ANPP. The first one has been carried out under the US DOE Assistance Program. The purpose of this study was to identify and evaluate feasible decommissioning options for ANPP. Some critical issues related to the waste management had been specified and the near-term activities within this project will be focused on issues of waste characterization and information data base creation as an important prerequisite to manage waste safely. The model used to calculate many of the decommissioning costs was NRC CECP reprogrammed for WWER NPPs. The second study had been carried out in the framework of TACIS project 'Assistance to Energy Strategic Center'. The purpose of the study was to select the best strategy to phase-out and decommission the ANPP and evaluate conditions, implications and consequence of this decision. A suggested solution was a choice of SAFSTOR as a viable decommissioning option. Spent fuel management is not considered part of decommissioning; however it can strongly affect the decommissioning strategy. Currently the spent nuclear fuel is being stored on site in pools and in a newly constructed NUHOMS storage facility built by FRAMATOME under license of USA Transnuclear West Company. The facility includes 11 horizontal storage modules (HSM). Each HSM has a capacity of 56 non-failed fuel assemblies. A capacity of the existing dry storage facility is not sufficient to accommodate all spent fuel generated during plant operation. However, the NUHOMS concept is modular and it is possible to increase the storage capacity. The facility is designed for 50 years storage of spent nuclear fuel. In any case, these studies should be considered as an informative basis only. Much more additional information should be collected and the detailed characterization survey, i.e. the comprehensive engineering and radiological survey, conducted to have sufficient data for all further planning activities. (author)

  10. Decommissioning of Salaspils Research Reactor

    International Nuclear Information System (INIS)

    The Salaspils Research Reactor (SRR) is out of operation since July 1998 and the decommissioning of SRR was started in 1999 according to the decision of the Government of Latvia. The main decommissioning activities up to 2006 were connected with collecting and conditioning of historical radioactive wastes from different storages outside and inside of reactor hall. The total amount of dismantled materials was about 700 tons, more than 77 tons were conditioned in concrete containers for disposal in repository. The radioactive wastes management technology is discussed in the paper. It was found, that additional efforts must be spent for immobilization of radionuclides in cemented matrix to be comply with the wastes acceptance criteria. The investigations of mechanical stability of water-cement matrix are described and discussed in the paper

  11. Atomics International's recent decommissioning experience

    International Nuclear Information System (INIS)

    A program for decommissioning eight nuclear facilities has been underway by the Atomics International (AI) Division of Rockwell International during the past five years. The facilities are located at the Rockwell Santa Susana Field Laboratory, approximately 30 miles from the center of Los Angeles. The facilities served experimental and development programs for space nuclear power, liquid metal technology, and commercial power generation. The land involved is under lease to the Federal government and may revert to private ownership. The programs conducted in these facilities were terminated in the 1960s, and the facilities were placed in a layaway status. They were designated as being surplus to programmatic needs in the early 1970s, and decommissioning project authorization was received from the government in 1974

  12. Decommissioning challenges: an industrial reality?

    International Nuclear Information System (INIS)

    This dossier describes the present situation of decommissioning and dismantling in France and worldwide, as well as the strategies and techniques involved, and the economic and environment issues that are concerned. 5 conclusions can be drawn: 1) dismantling has become an industrial reality particularly in Europe and Japan, 2) all the operators agree with a need for stability in the regulations and procedures concerning decommissioning, 3) Dismantling requires high technicality but no major technical difficulties have appeared, 4) challenges concerning the management of radioactive wastes are clearly identified and some wait for adequate responses (particularly the disposal of high level radioactive wastes), and 5) the success of dismantling operating will have a positive impact on the perennial and public acceptance of the nuclear energy choice. (A.C.)

  13. Fort St. Vrain defueling ampersand decommissioning considerations

    International Nuclear Information System (INIS)

    Fort St. Vrain Nuclear Generating Station (FSV) is one of the first commercial reactors to be decommissioned under NRC's decommissioning rule. The defueling and decommissioning of this 330 MWe High Temperature Gas Cooled Reactor (HTGR) has involved many challenges for Public Service Company of Colorado (PSC) including defueling to an Independent Spent Fuel Storage Installation (ISFSI), establishing decommissioning funding, obtaining regulatory approvals, arranging for waste disposal, and managing a large fixed price decommissioning contract. In 1990, a team comprised of the Westinghouse Corporation and Morrison Knudsen Corporation, with the Scientific Ecology Group as a major subcontractor, was contracted by PSC to perform the decommissioning under a fixed price contract. Physical work activities began in August 1992. Currently, physical dismantlement activities are about 45% complete, the project is on schedule, and is within budget

  14. Safety yields decommissioning successes. Panel Discussion

    International Nuclear Information System (INIS)

    Full text of publication follows: Panelists will speak to the most recent decommissioning projects successfully conducted. The projects represent facilities over the full range of commercial decommissioning, fuel storage, and weapons facilities. Lessons learned will be stressed to guide interested parties through future decommissioning activities. Human Factors Assessment of D and D Technologies and How This Relates to Improvement of Safety in Decommissioning Projects (Bruce Lippy (OENHP)); PPPL's Safety Practices, Safety Records, and Corrective Actions to Address Safety Issues (Keith Rule (PPPL)); INEEL's Safety Practices in Decommissioning Projects and Safety-Enhancing D and D Technologies (Richard Meservey (BWXT)); Big Rock Point Restoration Project Decommissioning Successes from a Safety Culture Perspective (William Trubilowicz (Consumers PWR, Big Rock Point))

  15. Nuclear decommissioning planning, execution and international experience

    CERN Document Server

    2012-01-01

    A title that critically reviews the decommissioning and decontamination processes and technologies available for rehabilitating sites used for nuclear power generation and civilian nuclear facilities, from fundamental issues and best practices, to procedures and technology, and onto decommissioning and decontamination case studies.$bOnce a nuclear installation has reached the end of its safe and economical operational lifetime, the need for its decommissioning arises. Different strategies can be employed for nuclear decommissioning, based on the evaluation of particular hazards and their attendant risks, as well as on the analysis of costs of clean-up and waste management. This allows for decommissioning either soon after permanent shutdown, or perhaps a long time later, the latter course allowing for radioactivity levels to drop in any activated or contaminated components. It is crucial for clear processes and best practices to be applied in decommissioning such installations and sites, particular where any ...

  16. Decommissioning plans and activities in Slovenia

    International Nuclear Information System (INIS)

    With the ageing of nuclear facilities, or the reduced interest in their further operation, a new set of problems, related to the decommissioning of these facilities, has come into forefront. In many cases it turns out that the preparations for decommissioning have come too late, and that financial resources for covering decommissioning activities have not been provided. In this paper a presentation is given of current decommissioning experience in Slovenia. The main problems and difficulties in decommissioning of the Zirovski vrh Uranium Mine are exposed, and the lesson learned from this case is presented. The preparation of the decommissioning programme for the nuclear power plant Krsko is also described, and the situation at the TRIGA research reactor is briefly discussed. (author)

  17. Decommissioning scenario and waste management

    International Nuclear Information System (INIS)

    During the last 10 years the Marcoule site has been engaged in decommissioning, dismantling and waste retrieval programs that are scheduled to continue for another 30 years. The scope and complexity of the D and D program are in proportion with the former activity of the site. This context is an incentive for program management to focus on scenario and waste management to optimize the final cost and end time. (authors)

  18. The decommissioning of Berkeley II

    International Nuclear Information System (INIS)

    This paper describes the decommissioning progress at the Magnox site at Berkeley in Gloucestershire.Throughout the work at Berkeley the emphasis has been on conducting decommissioning safely. This has been reflected in the progress of decommissioning starting with removal of the fuel from site and thus much greater than 99% of the radioactive inventory. The major radioactive hazard is the Intermediate Level Waste in the form of fuel element debris (graphite struts and extraneous magnox components removed to increase the packing density of fuel elements in flasks going to Sellafield), miscellaneous activated components, sludges and resins. Approximately 1500 m3 of such material exists and is stored in underground waste vaults on site. Work is underway to recover and encapsulate the waste in cement so rendering it 'passively safe'. All work on site is covered by a nuclear safety case which has a key objective of minimising the radiological exposures that could accrue to workers. Reflecting this an early decision has been taken to leave work on the Reactor Pressure Vessels themselves for several decades. Also important in protection of the workforce has been control of asbestos.Much material has been removed with redundant plant and equipment, but a programme of remediation in line with government legislation has been required to ensure personnel safety throughout the decommissioning period and into Care and Maintenance.In addition to health and safety matters the site approach to environmental issues has been consistent. Formally such standards as ISO 14001 have been adhered to and the appropriate certification maintained. At a working level the principles of reduce, reuse and recycle have been inculcated

  19. Decommissioning - The keys to success

    International Nuclear Information System (INIS)

    The United Kingdom Atomic Energy Authority (UKAEA) owns and operates five sites across the United Kingdom. The Winfrith site in Dorset was established in the late 1950's as a centre for development of prototype reactors. During its history, nine research reactors have operated on the site together with: a fuel fabrication facility; a post irradiation examination facility; radiochemistry laboratories, etc. The largest reactor, a 100MWe Steam Generating Heavy Water Reactor, was closed down in 1990 and the last research reactor was closed in 1995. Since the early 1990's the site has been undergoing a programme of progressive decommissioning with a view to releasing the site for alternative use unrestricted by the site's nuclear history. Key drivers for the design of the programme were safety, minimising adverse environmental effects, minimising costs and ensuring stakeholder support. One requirement of the stakeholders was to ensure that the site continued to provide high quality employment. This was successfully achieved by developing a Science and Technology Park on the nuclear site. Over 40 companies are now located on the Park providing over 1000 jobs. This paper will focus on the lessons learnt from over a decade of experience of decommissioning at Winfrith and will attempt to identify the 'keys to successful decommissioning'. These 'keys' will include: defining the site end-point; planning the programme; defining the commercial strategy; cost estimation; evaluation and management of risks; safety and environmental management; and stakeholder engagement. In particular, the paper will explore the very close relationship between: funding profiles; cost estimation; risk management and commercial strategy. It will show that these aspects of the programme cannot be considered separately. The paper will attempt to show that, with careful planning; decommissioning can be achieved safety and give good value for money to the funding authority. (author)

  20. Integrated decommissioning management tools (IDMT)

    International Nuclear Information System (INIS)

    Full text: Nuclear Power Plant decommissioning requires a number of demolition activities related to civil works and systems as well as the construction of temporary facilities used for treatment and conditioning of the dismantled parts. The presence of a radiological, potentially hazardous, environment due to the specific configuration and history of the plant require a professional, expert and qualified approach approved by the national safety authority. Dismantling activities must be designed, planned and analysed in detail during an evaluation phase taking into account different scenarios generated by possible dismantling sequences and specific waste treatments to be implemented. The optimisation process of the activities becomes very challenging taking into account the requirement of the minimisation of the radiological impact on exposed workers and people during normal and accident conditions. While remote operated equipment, waste treatment and conditioning facilities may be designed taking into account this primary goal also a centralised management system and corresponding software tools have to be designed and operated in order to guarantee the fulfilment of the imposed limits as well as the traceability of wastes. Ansaldo Nuclear Division has been strongly involved in the development of a qualified and certified software environment to manage the most critical activities of a decommissioning project. The IDMT system (Integrated Decommissioning Management Tools) provide a set of stand alone user friendly applications able to work in an integrated configuration to guarantee waste identification, traceability during treatment and conditioning process as well as location and identification at the Final Repository site. Additionally, the system can be used to identify, analyse and compare different specific operating scenarios to be optimised in term of both economical and radiological considerations. The paper provides an overview of the different phases of decommissioning activities and a presentation of the most original concepts of the IDMT system. (authors)

  1. IDMT, Integrated Decommissioning Management Tools

    International Nuclear Information System (INIS)

    Nuclear Power Plant decommissioning requires a number of demolition activities related to civil works and systems as well as the construction of temporary facilities used for treatment and conditioning of the dismantled parts. The presence of a radiological, potentially hazardous, environment due to the specific configuration and history of the plant require a professional, expert and qualified approach approved by the national safety authority. Dismantling activities must be designed, planned and analysed in detail during an evaluation phase taking into account different scenarios generated by possible dismantling sequences and specific waste treatments to be implemented. The optimisation process of the activities becomes very challenging taking into account the requirement of the minimisation of the radiological impact on exposed workers and people during normal and accident conditions. While remote operated equipment, waste treatment and conditioning facilities may be designed taking into account this primary goal also a centralised management system and corresponding software tools have to be designed and operated in order to guarantee the fulfilment of the imposed limits as well as the traceability of wastes. Ansaldo Nuclear Division has been strongly involved in the development of a qualified and certified software environment to manage the most critical activities of a decommissioning project. The IDMT system (Integrated Decommissioning Management Tools) provide a set of stand alone user friendly applications able to work in an integrated configuration to guarantee waste identification, traceability during treatment and conditioning process as well as location and identification at the Final Repository site. Additionally, the system can be used to identify, analyse and compare different specific operating scenarios to be optimised in term of both economical and radiological considerations. The paper provides an overview of the different phases of decommissioning activities and a presentation of the most original concepts of the IDMT system. (authors)

  2. Desempenho em confinamento de machos bovinos inteiros Canchim, Aberdeen angus e cruzamentos recíprocos

    OpenAIRE

    Perotto Daniel; Moletta José Luiz; Lesskiu Carlos

    2002-01-01

    Foram analisados o consumo diário de matéria seca (MS) por 100kg de peso vivo (CMS), a conversão alimentar (CA) e o ganho de peso médio diário (GMD) de 118 machos bovinos inteiros Canchim (Cn), Aberdeen Angus (Ab) e cruzamentos recíprocos (CnAb (F1, 3/4Cn+1/4Ab, 5/8Cn+3/8Ab e 11/16Cn+5/16Ab) e AbCn (F1, 5/8Ab+3/8Cn e 11/16Ab+5/16Cn)). Esses animais foram alimentados em baias individuais por 84 a 95 dias com silagem de milho à vontade mais concentrado (17,8% de PB e 79% de NDT) fornecido à bas...

  3. Field studies; analysis of urban air in the city of Aberdeen for volatile organic compounds (VOCs)

    International Nuclear Information System (INIS)

    The development of suitable methodology described in this paper for twelve different VOCs or tropospheric interest is based on target compound analysis. Their characterization by GLC from more volatile to less volatile hydrocarbons adsorbed on charcoal with subsequent desorption in xylene solvent in described. The chromatography of this group of volatile organic compounds with detection limit sample injection volume and chromatographic performance of the packed column is critically discussed for urban air samples of Aberdeen City (UK), pumped sampling on charcoal was used with subsequent desorption into xylene. The only problem is the volume of solvent required in routine analysis, usually of the order of the milliliter, sine only a micro-litter of extracts is injected into the GLC, which reduces the sensitivity of the method compared to that of thermal desorption

  4. An apparatus for studying spallation neutrons in the Aberdeen Tunnel laboratory

    CERN Document Server

    Blyth, S C; Chen, X C; Chu, M C; Hahn, R L; Ho, T H; Hsiung, Y B; Hu, B Z; Kwan, K K; Kwok, M W; Kwok, T; Lau, Y P; Lee, K P; Leung, J K C; Leung, K Y; Lin, G L; Lin, Y C; Luk, K B; Luk, W H; Ngai, H Y; Ngan, S Y; Pun, C S J; Shih, K; Tam, Y H; Tsang, R H M; Wang, C H; Wong, C M; Wong, H L; Wong, H H C; Wong, K K; Yeh, M

    2013-01-01

    In this paper, we describe the design, construction and performance of an apparatus installed in the Aberdeen Tunnel laboratory in Hong Kong for studying spallation neutrons induced by cosmic-ray muons under a vertical rock overburden of 611 meter water equivalent (m.w.e.). The apparatus comprises of six horizontal layers of plastic-scintillator hodoscopes for determining the direction and position of the incident cosmic-ray muons. Sandwiched between the hodoscope planes is a neutron detector filled with 650 kg of liquid scintillator doped with about 0.06% of Gadolinium by weight for improving the e?ciency of detecting the spallation neutrons. Performance of the apparatus is also presented.

  5. Preliminary nuclear decommissioning cost study

    International Nuclear Information System (INIS)

    The decommissioning of a nuclear power plant may involve one or more of three possible options: storage with surveillance (SWS), restricted site release (RSR), and unrestricted site use(USU). This preliminary study concentrates on the logistical, technical and cost aspects of decommissioning a multi-unit CANDU generating station using Pickering GS as the reference design. The procedure chosen for evaluation is: i) removal of the fuel and heavy water followed by decontamination prior to placing the station in SWS for thiry years; ii) complete dismantlement to achieve a USU state. The combination of SWS and USU with an interim period of surveillance allows for radioactive decay and hence less occupational exposure in achieving USU. The study excludes the conventional side of the station, assumes waste disposal repositories are available 1600 km away from the station, and uses only presently available technologies. The dismantlement of all systems except the reactor core can be accomplished using Ontario Hydro's current operating, maintenance and construction procedures. The total decommissioning period is spread out over approximately 40 years, with major activities concentrated in the first and last five years. The estimated dose would be approximately 1800 rem. Overall Pickering GS A costs would be $162,000,000 (1980 Canadian dollars)

  6. Experience of TTR-1 decommissioning

    International Nuclear Information System (INIS)

    Toshiba Training Reactor-1 (TTR-1) was planned for improvement of technical level from the standpoint of nuclear reactor manufacturer, training of a nuclear engineer, and research of nuclear physics, radiochemistry, radiation shielding and others. TTR-1 was permitted for construction in May 1960, attained at the first criticality in March 1962 and has continued to operate over 40 years. TTR-1 was permanently shut down in March 2001, accomplishing the planned target. From the initial criticality to the shut down, total operating time amounts to 15,300 hours and 31 MWds. Decommissioning plan was submitted to the Ministry of Education, Culture, Sports, Science and Technology on August 8, 2001 and dismantling work was started. The spent fuel was transported outside the laboratory, and the first phase and the second phase dismantling work were completed at the end of February 2004. Some of the reactor equipments continue maintaining their performance, and waste materials generated from dismantling work are under the state of managed storage, until disposal of the dismantling radioactive waste becomes clear, when the third phase of dismantling work will be started. At the end of the third phase work, all the TTR-1 equipments are dismantled and all waste materials are removed from TTR-1, then decommissioning of TTR-1 is completed. The outline of the decommissioning plan, the actually performed dismantling work, and spent fuel transportation work is briefly described. (author)

  7. Decommissioning of naval nuclear ships

    International Nuclear Information System (INIS)

    During the next decade the two major nuclear powers will each have to decommission more than 100 naval nuclear vessels, in particular submarines. The problems connected with this task is considered in this report. Firstly the size of the task is considered, i.e. the number of nuclear vessels that has to be decommissioned. Secondly the reactors of these vessels, their fuel elements, their power level, the number of reactors per vessel and the amount of radioactivity to be handled are discussed. Thirdly the decommissioning procedures, i.e. The removal of fuel from the vessels, the temporary storage of the reactor fuel near the base, and the cleaning and disposal of the reactor and the primary circuit components are reviewed. Finally alternative uses of the newer submarines are briefly considered. It should be emphasizes that much of the detailed information on which this report is based, may be of dubious nature, and that may to some extent affect the validity of the conclusions of the report. (au)

  8. Decommissioning: a United Kingdom perspective

    Energy Technology Data Exchange (ETDEWEB)

    Haworth, A.; Reed, D.L.; Bleeze, A. [Health and Safety Executive, London (United Kingdom)

    1995-12-31

    The paper considers the United Kingdom legislative framework relevant to decommissioning of facilities on nuclear licensed sites. It describes the various legislative bodies involved in regulating this activity and the inspectorate concerned. The licensing regime is described in some detail highlighting the UK arrangements whereby a license is granted for the site upon which nuclear facilities are planned or exist. The license remains in place throughout the life of the plant on the site: from initial planning through to the end of decommissioning. A site (of part of) is not de-licensed until it can be stated that there has ceased to be any danger from ionising radiations from anything on the site (or appropriate part of the site). The final part of the paper considers the changes arising from the commercialization of the nuclear power industry in UK and the restatement of the Nuclear Installation Inspectorate`s policy on decommissioning which has arisen as a result of a review made in response to these changes. (author).

  9. San Onofre Unit 1 decommissioning

    International Nuclear Information System (INIS)

    Nuclear plant decommissioning presents several challenges in radiation protection. The plant demolition must consider radiation protection for workers, protection of the public, and careful material management. Decommissioning of the San Onofre Nuclear Generating Station (SONGS) Unit 1 presented some additional challenges. Including complete removal of above ground structures this can be accomplished safely and efficiently. None of the low-level radioactive waste is unique to decommissioning although transportation of large components can be a significant challenge. Proven techniques are available to handle Greater than Class C waste (highly activated reactor internals) and spent fuel. A considerable challenge is the disposing of the very large volume of potentially clean material. There is a high cost to survey and decontaminate materials. Moreover, in the US today there are no standards for the clearance of potentially contaminated volumetric materials. Careful planning is necessary to determine the most cost-effective means for waste management, whether it includes decontamination and surveys or simple disposal. Lastly, existing ALARA programs with some minor modifications provide sufficient worker and public protection from radiation

  10. Decommissioning: a United Kingdom perspective

    International Nuclear Information System (INIS)

    The paper considers the United Kingdom legislative framework relevant to decommissioning of facilities on nuclear licensed sites. It describes the various legislative bodies involved in regulating this activity and the inspectorate concerned. The licensing regime is described in some detail highlighting the UK arrangements whereby a license is granted for the site upon which nuclear facilities are planned or exist. The license remains in place throughout the life of the plant on the site: from initial planning through to the end of decommissioning. A site (of part of) is not de-licensed until it can be stated that there has ceased to be any danger from ionising radiations from anything on the site (or appropriate part of the site). The final part of the paper considers the changes arising from the commercialization of the nuclear power industry in UK and the restatement of the Nuclear Installation Inspectorate's policy on decommissioning which has arisen as a result of a review made in response to these changes. (author)

  11. Shippingport Station Decommissioning Project: overview and justification

    International Nuclear Information System (INIS)

    The purpose of this booklet is to brief the reader on the Shippingport Station Decommissioning Project and to summarize the benefits of funding the project in FY 1984. Background information on the station and the decommissioning project is provided in this section of the booklet; the need for a reactor decommissining demonstration is discussed in the next section; and a summary of how the Shippingport Station Decommissioning Project (SSDP) provides the needed demonstration is provided in the final section

  12. Status of the Fort St. Vrain decommissioning

    International Nuclear Information System (INIS)

    Fort St. Vrain is a high temperature gas cooled reactor. It has been shut down as a result of financial and technical difficulties. Fort St. Vrain has been planning for defueling and decommissioning for at least three years. The preliminary decommissioning plan, in accordance with the NRC's final rule, has been submitted and is being reviewed by the NRC. The basis of the preliminary decommissioning plan has been SAFSTOR. Public Service Company, who is the owner and operator of FSV, is scheduled to submit a proposed decommissioning plan to the NRC in the fourth quarter of 1990. PSC has gone out for bid on the decontamination and dismantlement of FSV. This paper includes the defueling schedule, the independent spent fuel storage installation status, the probability of shipping fuel to DOE, the status of the preliminary decommissioning plan submittal, the issuance of a possession only license and what are the results of obtaining this license amendment, preliminary decommissioning activities allowed prior to the approval of a proposed decommissioning plan, the preparation of a proposed decommissioning plan and the status of our decision to proceed with SAFSTOR or DECON as identified in the NRC's final decommissioning rule

  13. Decommissioning Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely

  14. European Decommissioning Academy (EDA). Ready to start

    International Nuclear Information System (INIS)

    According to analyses presented at EC meeting focused on decommissioning organized at 11 September 2012 in Brussels, it was stated that at least 2,000 new international experts for decommissioning will be needed in Europe up to 2025, which means about 150 each year. The article describes the European Decommissioning Academy (EDA) which is prepared for the first term in June 2015 in Slovakia. The main goal is a creation of new nuclear experts generation for decommissioning via the Academy, which will include lessons, practical exercises in laboratories as well as 2 days on-site training at NPP V-1 in Jaslovske Bohunice (Slovakia). Four days technical tour via most interesting European decommissioning facilities in Switzerland and Italy are planned as well. After the final exam, there is the option to continue in knowledge collection via participation at the 2nd Eastern and Central European Decommissioning (ECED) conference in Trnava (Slovakia). We would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future.

  15. European Decommissioning Academy (EDA). Ready to start

    Energy Technology Data Exchange (ETDEWEB)

    Slugen, Vladimir [Slovak University of Technology, Bratislava (Slovakia). Inst. of Nuclear and Physical Engineering

    2015-02-15

    According to analyses presented at EC meeting focused on decommissioning organized at 11 September 2012 in Brussels, it was stated that at least 2,000 new international experts for decommissioning will be needed in Europe up to 2025, which means about 150 each year. The article describes the European Decommissioning Academy (EDA) which is prepared for the first term in June 2015 in Slovakia. The main goal is a creation of new nuclear experts generation for decommissioning via the Academy, which will include lessons, practical exercises in laboratories as well as 2 days on-site training at NPP V-1 in Jaslovske Bohunice (Slovakia). Four days technical tour via most interesting European decommissioning facilities in Switzerland and Italy are planned as well. After the final exam, there is the option to continue in knowledge collection via participation at the 2nd Eastern and Central European Decommissioning (ECED) conference in Trnava (Slovakia). We would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future.

  16. Planning and management for reactor decommissioning

    International Nuclear Information System (INIS)

    This report describes decommissioning strategy, planning process, regulation, management and organization, radiological characterization and safety. Planning is used to identify, define and organize the requirements for decommissioning including decommissioning options, items to be accomplished (objective, scope), to solve problems of how it is to be accomplished (methods, means and procedures), questions of who will execute it (resources, organization and responsibilities, interfacing), and time when it will be executed (schedule for meeting the objectives). A plan is highly dependent on the quality of the management team assembled to carry it out. Radiological characterization involves a survey of existing data, calculation, in situ measurements and/or sampling and analyses. Using this databases decommissioning planner may assess options, considering: decontamination processes, dismantling procedures, tools required, radiological protection of workers and public/environment, waste classification, and resulting costs. Comparison and optimization of these factors will lead to selection of a decommissioning strategy, i.e. typically, immediate or deferred dismantling. The planning and implementation of decommissioning for nuclear reactors should be referred both recent dismantling techniques and many decommissioning experiences. The technical lessons learned from many projects will help in the planning for future decommissioning projects. And systematic planning and management are essential to successful completion of a decommissioning project. (author)

  17. Experiences in teaching decommissioning - 16179

    International Nuclear Information System (INIS)

    The paper describes the experience gained by the author in teaching decommissioning in the Highlands of Scotland. Initially when asked to teach the subject of decommissioning to students sitting for a BSc degree in 'Electrical or Mechanical Engineering with Decommissioning Studies', the author was taken aback, not having previously taught degree students and there was no precedent since there was no previous material or examples to build on. It was just as difficult for the students since whilst some had progressed from completing HND studies, the majority were employed at the Dounreay site and were mature students with families who were availing themselves of the opportunity for career advancement (CPD). Some of the students were from the UKAEA and its contractors whilst others were from Rolls-Royce working at Vulcan, the Royal Navy's establishment for testing nuclear reactors for submarines. A number of the students had not been in a formal learning environment for many years. The College which had originally been funded by the UKAEA and the nuclear industry in the 1950's was anxious to break into the new field of Decommissioning and were keen to promote these courses in order to support the work progressing on site. Many families in Thurso, and in Caithness, have a long tradition of working in the nuclear industry and it was thought at the time that expertise in nuclear decommissioning could be developed and indeed exported elsewhere. In addition the courses being promoted by the College would attract students from other parts so that a centre of excellence could be established. In parallel with formal teaching, online courses were also developed to extend the reach of the College. The material was developed as a mixture of power point presentations and formal notes and was obtained from existing literature, web searches and interactive discussions with people in the industry as well as case studies obtained from actual situations. Assignments were set and examination papers prepared which were validated by internal and external assessors. The first course was started in 2004 (believed to be unique at that time) and attracted eight students. Subsequent courses have been promoted as well as a BEng (Hons) course which also included a course on Safety and Reliability. (authors)

  18. Ensuring the radiation protection during radioactive sources decommissioning

    International Nuclear Information System (INIS)

    The radiation control always is carried out during facilities decommissioning. All staff involved during radioactive sources decommissioning were supplied with individual dosimeters and individual means of protection.

  19. Pre-decommissioning, during decommissioning, and post-decommissioning radiological characterization of shutdown research reactors and their sites

    International Nuclear Information System (INIS)

    The objective of this lecture is to provide guidance to national governments, regulatory bodies, and operators for the timely and safe decommissioning of research reactors and small nuclear facilities. The emphasis of this lecture will be on characterization in support of decommissioning the facility. It is understood that each facility brings with it a unique set of problems itself. This lecture presents a general overview of the process and some important aspects of the radiological characterization process before, during, and after decommissioning is completed. A graded approach to the effort and resources needed to address this aspect of a decommissioning project is recommended, taking into account the associated risks and hazards. A realistic decommissioning plan must be built upon taking adequate account of the facility radiological conditions

  20. Study of decommissioning cost evaluation technique for nuclear reactor dismantlement. Calculation of decommissioning cost by COSMARD

    International Nuclear Information System (INIS)

    A model for estimating decommissioning costs consisting of labor cost, device cost and expense, was developed for items which OECD/NEA had standardized, and was installed into the computer system for planning and management of reactor decommissioning (COSMARD). Input data files and databases for the decommissioning of JPDR were prepared, and the decommissioning cost was calculated with COSMARD. In addition, the decommissioning cost for a large scale BWR power plant was also calculated on the assumption of the advantage of scale. The calculations have shown that it is useful and efficient for studying the decommissioning costs for nuclear reactors to apply the COSMARD with database for cast estimation to the decommissioning cost calculation. (author)

  1. Decommissioning of Russian research facilities

    International Nuclear Information System (INIS)

    When the most of our research facilities were built and put in operation more than 30 years ago there had been neither requirements no regulations concerning their future decommissioning (D and D). And due to that fact nobody thought of that in the initial designs of these facilities. The situation changed when in 1994 a top-level safety standard 'Safety Provision for Safety of Research Reactors' was issued by Gosatomnadzor of Russia with a special chapter 7, devoted to D and D issues. Unfortunately, it was just one page of requirements pertaining RR D and D in general terms and was not specific. Only in 2001 Gosatomnadzor of Russia developed and issued a more specific standard 'Rules for Safety Decommissioning of Nuclear Research Facilities'. From the total number of 85 Nuclear Research Facilities, including 34 research reactors, 36 critical assemblies and 15 subcritical assemblies, we have now 7 facilities under decommissioning. The situation is inevitably changing over the time. In the end of 2003 the decision was made to permanently shutdown two RR: AM, graphite type with channels, 15 MBt; BR-10, LMFR type, 10 MBt, and to start preparatory work for their future decommissioning, starting from 2005. It needs to be mentioned that from this list we have 6 reactors with which we face many difficulties in developing decommissioning technologies, namely: for TVR reactor: handling of heavy water and high radiation field in the core; for MR reactor: very complex reactor with many former radioactive spills, which is required a careful and expensive D and D work; AM: graphite utilization problem; BR-10: a problem of coolant poisoned with other heavy metals (like lead, bismuth); IBR-30: the fuel cannot be removed from the core prior the D and D project starts; RG-1M: location is above Arctic Circle, problem of transfer of irradiated parts of the reactor. The decision was made to bury then on the site thus creating a shallow-land radwaste storage facility. The established D and D standard explains in more or less detail the procedures to be accomplished before the actual decommissioning process can start. Basically these are: remove fuel from the reactor core to an interim SF storage facility at the reactor; after specified time of cooling, remove the fuel from the reactor building; drain coolant by using operational manual and remove it from the reactor building; conduct Engineering and Radiation Monitoring of the facility to get initial data on radiation conditions; Develop a Principal D and D Programme; develop a D and D documentation; develop a D and D SAR. Only after these procedures and documents have been accomplished and prepared an operating organization may apply for a D and D license to be issued by Gosatomnadzor of Russia. When a D and D project is fully accomplished by an operating organization the final results/conditions at the former RR site shall be evidenced by a special commission, including a Gosatomnadzor of Russia representative. A Final Report on D and D with the radiation data achieved in the end of its implementation shall be written and submitted to Gosatomnadzor of Russia for review and making decision on taking a research facility out of regulatory control

  2. Project gnome decontamination and decommissioning plan

    International Nuclear Information System (INIS)

    The document presents the operational plan for conducting the final decontamination and decommissioning work at the site of the first U.S. nuclear detonation designed specifically for peaceful purposes and the first underground event on the Plowshare Program to take place outside the Nevada Test Site. The plan includes decontamination and decommissioning procedures, radiological guidelines, and the NV concept of operations

  3. 75 FR 80697 - Nuclear Decommissioning Funds

    Science.gov (United States)

    2010-12-23

    ... accounting is allowed a deduction for nuclear decommissioning costs no earlier than the taxable year in which... Effective/applicability date. Sec. 1.468A-1 Nuclear decommissioning costs; general rules. (a) Introduction... Treasury Department issued a notice of proposed rulemaking (REG-147290-05, 2008-10 IRB 576 [72 FR...

  4. Training of experts on NPP decommissioning

    International Nuclear Information System (INIS)

    The paper presents difficulties and problems in training of NPP decommissioning experts in Ukraine. The scientific and technical cluster is offered to be constructed as a territorial association of enterprises and organizations related to NPP decommissioning issues and spent nuclear fuel and radioactive waste management. The center is to be based on scientific and educational center in Slavutych, satellite city of Chornobyl NPP.

  5. FACILITATION OF DECOMMISSIONING LIGHT WATER REACTORS

    Energy Technology Data Exchange (ETDEWEB)

    Moore, Jr. EB; ,

    1979-12-01

    Information on design features, special equipment, and construction methods useful in the facilitation of decommissioning light water reactors is presented in this report. A wide range of facilitation methods--from improved documentation to special decommissioning tools and techniques--is discussed. In addition, estimates of capital costs, cost savings, and radiation dose reduction associated with these facilitation methods are given.

  6. Facilitation of decommissioning light water reactors

    International Nuclear Information System (INIS)

    Information on design features, special equipment, and construction methods useful in the facilitation of decommissioning light water reactors is presented. A wide range of facilitation methods - from improved documentation to special decommissioning tools and techniques - is discussed. In addition, estimates of capital costs, cost savings, and radiation dose reduction associated with these facilitation methods are given

  7. Survey of decontamination and decommissioning techniques

    International Nuclear Information System (INIS)

    Reports and articles on decommissioning have been reviewed to determine the current technology status and also attempt to identify potential decommissioning problem areas. It is concluded that technological road blocks, which limited decommissioning facilities in the past have been removed. In general, techniques developed by maintenance in maintaining the facility have been used to decommission facilities. Some of the more promising development underway which will further simplify decommissioning activities are: electrolytic decontamination which simplifies some decontaminating operations; arc saw and vacuum furnace which reduce the volume of metallic contaminated material by a factor of 10; remotely operated plasma torch which reduces personnel exposure; and shaped charges, water cannon and rock splitters which simplify concrete removal. Areas in which published data are limited are detailed costs identifying various components included in the total cost and also the quantity of waste generated during the decommissioning activities. With the increased awareness of decommissioning requirements as specified by licensing requirements, design criteria for new facilities are taking into consideration final decommissioning of buildings. Specific building design features will evolve as designs are evaluated and implemented

  8. Meeting the challenge of BNFL's decommissioning programme

    International Nuclear Information System (INIS)

    The paper reviews the co-ordinated and integrated programme, adopted by BNFL, in the decommissioning of its radioactive plants. It examines BNFL's approach to the challenges posed by the eventual decommissioning of its 120 plants, its overall strategies, the constraints and the progress achieved to date, drawing on real experience from the 22 completed projects and the 24 projects currently underway. (author)

  9. Interim Storage Facility decommissioning. Final report

    International Nuclear Information System (INIS)

    Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel

  10. Sustainable Decommissioning of Oil Fields and Mines

    OpenAIRE

    Environmental Resources Management

    2009-01-01

    The overall goal of the decommissioning of oil fields and mines initiative (the 'Initiative') is, in keeping with World Bank policy, to promote sustainable development by assisting governments to undertake and engage in earlier and more systematic, comprehensive, and responsive planning of the decommissioning and closure of mining and oil and gas production operations, as well as more effe...

  11. Review of plant design features facilitating decommissioning

    International Nuclear Information System (INIS)

    At the design stage it is necessary to define the decommissioning strategy. This offers the opportunity to influence the design and hopefully deduce the optimum dismantling sequence, in terms of cost, dose rate and time. The decommissioning activity will be some 50 years to 150 years in the future, though the strategy must be based on present known or developing technology. In the event, the developments in remote handling techniques must mean the assumptions in this paper are pessimistic. Throughout the paper, delayed decommissioning is assumed, though a major accident or pressure for early re-use of the site, could require earlier decommissioning. This aspect is not considered in the paper, nevertheless, the conclusions would not be invalidated by such a requirement. A schedule of design features which facilitate decommissioning and details of some specific items installed to aid decommissioning of Advanced Gas Cooled Reactors is presented. The problems of long term storage of decommissioning documents and the selection of material for storage, can be influenced at the design stage. Some suggestions regarding storage and eventual recovery of information to aid decommissioning is included. (author)

  12. 76 FR 3837 - Nuclear Decommissioning Funds; Correction

    Science.gov (United States)

    2011-01-21

    ... 23, 2010 (75 FR 80697) relating to deductions for contributions to trusts maintained for decommissioning nuclear power plants. DATES: This correction is effective on January 21, 2011, and is applicable... Internal Revenue Service 26 CFR Part 1 RIN 1545-BF08 Nuclear Decommissioning Funds; Correction...

  13. Decommissioning of nuclear ship 'Otto Hahn'

    International Nuclear Information System (INIS)

    The nuclear powered ship 'Otto Hahn' was commissioned in 1968, and ended its mission in 1979. The decommissioning was approved in December, 1980, and after the dismantling and removal of the reactor plant were completed, the decommissioning was recognized in September, 1982. The features of the method of decommissioning Otto Hahn were the carrying-out of the reactor pressure vessel together with the primary shielding tank as one body, and after the machinery, equipment and structures in the controlled area were removed or decontaminated, the ship was reconstructed to a diesel freighter. It is considered that the method of decommissioning of Otto Hahn and the data obtained by this work furnish much information for the decommissioning of nuclear power stations and nuclear powered ships hereafter. In this report, the course of decommissioning of Otto Hahn and its experience are synthetically summarized. The propulsion plant of Otto Hahn, the radiological condition, the conceptual design of decommissioning, the dismantling works, the procedures of permission and approval, the procedure for removing the control, the execution of decommissioning, and the removal of the controlled area are reported. (K.I.)

  14. Decommissioning strategy and waste management in Sweden

    International Nuclear Information System (INIS)

    The commercial nuclear power plants in Sweden will eventually be shut down and decommissioned. This paper describes the strategy in planning these future activities. It also describes the cost calculations and the funding mechanism. The paper contains the following sections: Nuclear power plants In Sweden; Decommissioning strategies; Waste management and availability of repositories; Cost calculations and funding; The current financing act

  15. Rancho Seco--Decommissioning Update

    International Nuclear Information System (INIS)

    The Rancho Seco Nuclear Generating Station ceased operation in June of 1989 and entered an extended period of SAFSTOR to allow funds to accumulate for dismantlement. Incremental dismantlement was begun in 1997 of steam systems and based on the successful completion of work, the Sacramento Municipal Utility District (SMUD) board of directors approved full decommissioning in July 1999. A schedule has been developed for completion of decommissioning by 2008, allowing decommissioning funds to accumulate until they are needed. Systems removal began in the Auxiliary Building in October of 1999 and in the Reactor Building in January of 2000. Systems dismantlement continues in the Reactor Building and should be completed by the end of 2003. System removal is near completion in the Auxiliary Building with removal of the final liquid waste tanks in progress. The spent fuel has been moved to dry storage in an onsite ISFSI, with completion on August 21, 2002. The spent fuel racks are currently being removed from the pool, packaged and shipped, and then the pool will be cleaned. Also in the last year the reactor coolant pumps and primary piping were removed and shipped. Characterization and planning work for the reactor vessel and internals is also in progress with various cut-up and/or disposal options being evaluated. In the year ahead the remaining systems in the Reactor Building will be removed, packaged and sent for disposal, including the pressurizer. Work will be started on embedded and underground piping and the large outdoor tanks. Building survey and decontamination will begin. RFP's for removal of the vessel and internals and the steam generators are planned to fix the cost of those components. If the costs are consistent with current estimates the work will go forward. If they are not, hardened SAFSTOR/entombment may be considered

  16. STANDARD OPERATING PROTOCOLS FOR DECOMMISSIONING

    International Nuclear Information System (INIS)

    Decommissioning projects at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites are conducted under project-specific decision documents, which involve extensive preparation time, public comment periods, and regulatory approvals. Often, the decision documents must be initiated at least one year before commencing the decommissioning project, and they are expensive and time consuming to prepare. The Rocky Flats Environmental Technology Site (RFETS) is a former nuclear weapons production plant at which hazardous substances and wastes were released or disposed during operations. As a result of the releases, RFETS was placed on the National Priorities List in 1989, and is conducting cleanup activities under a federal facilities compliance agreement. Working closely with interested stakeholders and state and federal regulatory agencies, RFETS has developed and implemented an improved process for obtaining the approvals. The key to streamlining the approval process has been the development of sitewide decision documents called Rocky Flats Cleanup Agreement Standard Operating Protocols or ''RSOPs.'' RSOPs have broad applicability, and could be used instead of project-specific documents. Although no two decommissioning projects are exactly the same and they may vary widely in contamination and other hazards, the basic steps taken for cleanup are usually similar. Because of this, using RSOPs is more efficient than preparing a separate project-specific decision documents for each cleanup action. Over the Rocky Flats cleanup life cycle, using RSOPs has the potential to: (1) Save over 5 million dollars and 6 months on the site closure schedule; (2) Eliminate preparing one hundred and twenty project-specific decision documents; and (3) Eliminate writing seventy-five closure description documents for hazardous waste unit closure and corrective actions

  17. AREVA decommissioning strategy and programme

    International Nuclear Information System (INIS)

    As with any industrial installation, a nuclear facility has an operating life that requires accounting for its shutdown. In compliance with its sustainable development commitments, AREVA accounts this via its own decommissioning resources to value and make sites fit for further use. These capabilities guarantee the reversibility of the nuclear industry. Thus, the nuclear site value development constitutes an important activity for AREVA, which contributes to the acceptance of nuclear in line with the AREVA continuous policy of sustainable development which is to be fully responsible from the creation, during the operation, to the dismantling of its facilities in all respects with safety, local acceptance and environment. AREVA has already performed a large variety of operation during the life-time of its installations such as heavy maintenance, equipment replacement, upgrading operation. Nowadays, a completely different dimension is emerging with industrial decommissioning operations of nuclear fuel cycle installations: enrichment gaseous diffusion plant, fuel assembly plants, recycling and reprocessing facilities. These activities constitute a major know-how for AREVA. For this reason, the group decided, beginning of 2008, to gather 4 projects in one business unit called Nuclear Site Value Development - a reprocessing plant UP2 400 on AREVA La Hague site, a reprocessing plant UP1 on AREVA Marcoule site, a MOX fuel plant on Cadarache and 2 sites (SICN Veurey and Annecy) that handled GCR fuel fabrication). The main objectives are to enhance the feed back, to contribute to performance improvements, to value professionals and to put innovation forward. The following article will describe in a first part the main decommissioning programmes managed by AREVA NC Nuclear Site Value Development Business Unit. The second part will deal with strategic approaches. A more efficient organization with integration of the supply chain and innovation will be part of the main drivers. (authors)

  18. Decommissioning of a University Cyclotron

    International Nuclear Information System (INIS)

    In the decommissioning of a university cyclotron, the cost estimate provided by a decommissioning company to carry out the entire project was in excess of Pounds 1million. This level of funding was not available, and a more modest budget of Pounds 125 thousand was provided (about US$ 250 000 or Euro 180 000). This made it essential that as much of the work as possible was carried out by existing staff. Whereas existing staff could be trained to draft all the required documentation, complete the characterization survey and deliver some aspects of the decontamination programme, their greatest contribution to the project was in sorting, segregation, measurement, packaging and consignment for disposal of all of the decommissioning wastes. This necessitated provision of additional training to existing operators. At an early stage it was identified that an experienced decommissioning consultant was needed to oversee the project. The Decommissioning Consultant appointed external contractors to carry out all the heavy dismantling and demolition work associated with the project. This work involved: -Assembly of a caged storage area adjacent to the cyclotron to hold the wastes from dismantling and demolition, pending characterization for segregation and disposal by existing staff at the facility; -Removal of the D's and cutting them up in situ ready for characterization for shipment to the low level waste repository; -Removal of all rotating machinery in the adjacent generator house, then dismantling the concrete block and brick wall between the inner vault and the generator house; -Removal of extra shielding supported by girder matrix to assist removal of the concrete block wall. Collect core samples of bricks and blocks for activity estimation by operators working at the facility; -Moving of the resonator into the generator house for dismantling, monitoring and characterization; -Dismantling of ancillary equipment such as beam lines, remote target handling system, vacuum tank and inner copper blankets; -Removal of water tanks above, after first removing the upper level shielding. The cost of this heavy dismantling work carried out by the external experienced contractors was Pounds 60 000 (approximately US$120 000 or Euro 87 000) and the work was completed over an eight month period. It was essential to have the services of an experienced Decommissioning Consultant to manage the project to secure value for money and optimized delivery of this aspect of the project. Whereas the magnitude of the heavy dismantling work required makes it unrealistic for the operators to undertake this work themselves, the situation may be different when considering decommissioning of a much smaller scale facility such as a radioimmunoassay laboratory. In such circumstances, removal of surface contamination may be all that is required, such that further removal of cupboards and benches, plumbing and electrical fittings can be carried out by routine tradesmen rather than specialist heavy demolition contractors. Where access to a new disposal option is required as a 'one off'; e.g. disposal of a single consignment of waste to a low level solid waste repository, the quality assurance documentation requirements may prove unduly onerous to a small facility. This was the experience of a university when it came to decommission a particle accelerator that had been used for isotope production and research. They wished to dispose of a single consignment of 15 t of solid low level waste in a 20 cubic metre 2/3 ISO container (the approved containers used at the repository). The waste had arisen from two streams - from the cyclotron and the target waste stream and had an overall activity of 1 GBq per t for beta/gammas and 73MBq per t for alphas. The decommissioning facility manager had to institute a whole series of new management and waste control procedures on-site, to include documented audits and training records, before his quality plan to make the 'one off' disposal to the low level waste repository was accepted. In total, it took just over a year to get an approved quality plan in place. In such circumstances, it might be better to ask the repository quality assurance department if they have an intermediary contractor, who is able to receive a one off waste consignment within their quality system for routing to disposal at the repository. If this is the way forward, ensure that the license revision identifies transfer of the waste to the intermediary contractor for final disposal at the repository.

  19. Decommissioning progress at Fort St Vrain

    International Nuclear Information System (INIS)

    The Fort St. Vrain Nuclear Generating Station in Colorado in the United States is well along in Decommissioning for release of the site from its Nuclear Regulatory Commission license. This decommissioning is being performed under a fixed price contract between the owner, Public Service Company of Colorado and a team of Westinghouse and Morrison-Knudsen. This paper will discuss the innovative decommissioning technique of filling the gas cooled reactor with water for shielding and contamination control and the other practical and readily available technologies used. This Decommissioning is demonstrating that a full size commercial nuclear reactor can be successfully decommissioned with a reasonable schedule, cost, and radiation dose to the work force. (Author)

  20. Decommissioning Project for the Research Reactor

    International Nuclear Information System (INIS)

    In 2008, tried to complete the whole decommissioning project of KRR-1 and KRR-2 and preparing work for memorial museum of KRR-1 reactor. Now the project is delayed for 3 months because of finding unexpected soil contamination around facility and treatment of. To do final residual radioactivity assessment applied by MARSSIM procedure. Accumulated decommissioning experiences and technologies will be very usefully to do decommissioning other nuclear related facility. At the decommissioning site of the uranium conversion plant, the decontamination of the dismantled carbon steel waste are being performed and the lagoon 1 sludge waste is being treated this year. The technologies and experiences obtained from the UCP dismantling works are expected to apply to other fuel cycle facilities decommissioning. The lagoon sludge treatment technology is the first applied technology in the actual field and it is expected that this technology could be applied to other country

  1. Decommissioning plan for TRIGA Mark-2

    International Nuclear Information System (INIS)

    Korea Research Reactor 1(KRR 1; TRIGA Mark-2) is the first reactor in Korea, but its decommissioning is underway due to its life. In this paper, presenting the reason and object of decommissioning KRR 1, then describing reactor structure and survey result of the facility, activation and contamination status around reactor and nearby equipment and vicinity. Estimating dose rate was evaluated for every work stage. Those of survey, evaluation and radiological status were considered to determine the safe and reasonable decommissioning methods. The order of decommissioning works are divided by section to minimize possible hazard. Proposed decommissioning plan is based on hazard and operability study to protect workers and residents from radiation expose. (author). 12 refs., 5 tabs., 6 figs

  2. Decommissioning the Trojan nuclear power plant

    International Nuclear Information System (INIS)

    The decommissioning of the Trojan Nuclear Plant (TNP) began in 1993 with the decision to cease operation of the plant. In the six years since the shutdown, a Decommissioning Plan has been developed, site radiological characterizations have been performed, the decommissioning option, DECON, was selected and plant dismantlement has begun. TNP has accomplished the dismantlement tasks using a number of innovative projects and developed a number of new decommissioning techniques. The innovative projects include removal of the large components from the reactor building, the disposal of the reactor vessel with the internal highly radioactive components, and embedded in-place pipe decontamination and survey. The new methods include shipping and disposing of components as a package and dismantling tanks from the bottom up using less dose and time than more traditional methods. This paper describes how these methods save time, radiation dose and result in an overall safe approach to decommissioning. (author)

  3. Decontamination and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    The objectives of this coordinated research programme (CRP) were to promote the exchange of information on the practical experience by Member States in decontamination and decommissioning. The scope of the programme included several areas of decontamination and decommissioning rather than focusing on a single aspect of it, in line with recommendation of the experts who participated in Phase 1 of the CRP. Experts felt that this format would generate better awareness of decontamination and decommissioning and would be more effective vehicle for the exchange of information by stimulating broader discussion on all aspects of decontamination and decommissioning. Special emphasis was given to the development of principles and methodologies to facilitate decommissioning and to the new methods and techniques for optimization of decontamination and disassembly of equipment. Refs, figs, tabs

  4. Cost estimation for decommissioning of research reactors

    International Nuclear Information System (INIS)

    In the case of research reactors, the limited data that is available tends to provide only overall decommissioning costs, without any breakdown of the main cost elements. In order to address this subject, it is important to collect and analyse all available data of decommissioning costs for the research reactors. The IAEA has started the DACCORD Project focused on data analysis and costing of research reactors decommissioning. Data collection is organized in accordance with the International Structure for Decommissioning Costing (ISDC), developed jointly by the IAEA, the OECD Nuclear Energy Agency and the European Commission. The specific aims of the project include the development of representative and comparative data and datasets for preliminary costing for decommissioning. This paper will focus on presenting a technique to consider several representative input data in accordance with the ISDC structure and using the CERREX (Cost Estimation for Research Reactors in Excel) software developed by IAEA. (author)

  5. Measuring and reporting on decommissioning progress

    International Nuclear Information System (INIS)

    One of the challenges facing AECL, as well as other organizations charged with the responsibility of decommissioning nuclear facilities, is the means by which to measure and report on decommissioning progress to various audiences which, in some cases, may only have a peripheral knowledge or understanding of the complexities associated with the decommissioning process. The reporting and measurement of decommissioning progress is important for a number of reasons, i.e., It provides a vehicle by which to effectively communicate the nature of the decommissioning process; It ensures that stakeholders and shareholders are provided with a transparent and understandable means for assessing value for money; It provides a means by which to integrate the planning, measurement, and operational aspects of decommissioning One underlying reason behind the challenge of reporting decommissioning progress lies in the fact that decommissioning programs are generally executed over periods of time that far exceed those generally associated with typical design and build projects. For example, a decommissioning program could take decades to complete in which case progress on the order of a few percent in any one year might be typical. However, such progress may appear low compared to that seen with more typical projects that can be completed in a matter of years. As a consequence, AECL undertook to develop a system by which to measure decommissioning progress in a straightforward, meaningful, and understandable fashion. The system is not rigorously objective, and there are subjective aspects that are necessitated by the need to keep the system readily understandable. It is also important to note that while the system is simple in concept, there is, nonetheless, significant effort involved in generating and updating the parameters used as input, and in the actual calculations. (author)

  6. Disposition of fuel elements from the Aberdeen and Sandia pulse reactor (SPR-II) assemblies

    Energy Technology Data Exchange (ETDEWEB)

    Mckerley, Bill [Los Alamos National Laboratory; Bustamante, Jacqueline M [Los Alamos National Laboratory; Costa, David A [Los Alamos National Laboratory; Drypolcher, Anthony F [Los Alamos National Laboratory; Hickey, Joseph [Los Alamos National Laboratory

    2010-01-01

    We describe the disposition of fuel from the Aberdeen (APR) and the Sandia Pulse Reactors (SPR-II) which were used to provide intense neutron bursts for radiation effects testing. The enriched Uranium - 10% Molybdenum fuel from these reactors was shipped to the Los Alamos National Laboratory (LANL) for size reduction prior to shipment to the Savannah River Site (SRS) for final disposition in the H Canyon facility. The Shipper/Receiver Agreements (SRA), intra-DOE interfaces, criticality safety evaluations, safety and quality requirements and key materials management issues required for the successful completion of this project will be presented. This work is in support of the DOE Consolidation and Disposition program. Sandia National Laboratories (SNL) has operated pulse nuclear reactor research facilities for the Department of Energy since 1961. The Sandia Pulse Reactor (SPR-II) was a bare metal Godiva-type reactor. The reactor facilities have been used for research and development of nuclear and non-nuclear weapon systems, advanced nuclear reactors, reactor safety, simulation sources and energy related programs. The SPR-II was a fast burst reactor, designed and constructed by SNL that became operational in 1967. The SPR-ll core was a solid-metal fuel enriched to 93% {sup 235}U. The uranium was alloyed with 10 weight percent molybdenum to ensure the phase stabilization of the fuel. The core consisted of six fuel plates divided into two assemblies of three plates each. Figure 1 shows a cutaway diagram of the SPR-II Reactor with its decoupling shroud. NNSA charged Sandia with removing its category 1 and 2 special nuclear material by the end of 2008. The main impetus for this activity was based on NNSA Administrator Tom D'Agostino's six focus areas to reenergize NNSA's nuclear material consolidation and disposition efforts. For example, the removal of SPR-II from SNL to DAF was part of this undertaking. This project was in support of NNSA's efforts to consolidate the locations of special nuclear material (SNM) to reduce the cost of securing many SNM facilities. The removal of SPR-II from SNL was a significant accomplishment in SNL's de-inventory efforts and played a key role in reducing the number of locations requiring the expensive security measures required for category 1 and 2 SNM facilities. A similar pulse reactor was fabricated at the Y-12 National Security Complex beginning in the late 1960's. This Aberdeen Pulse Reactor (APR) was operated at the Army Pulse Radiation Facility (APRF) located at the Aberdeen Test Center (ATC) in Maryland. When the APRF was shut down in 2003, a portion of the DOE-owned Special Nuclear Material (SNM) was shipped to an interim facility for storage. Subsequently, the DOE determined that the material from both the SPR-II and the APR would be processed in the H-Canyon at the Savannah River Site (SRS). Because of the SRS receipt requirements some of the material was sent to the Los Alamos National Laboratory (LANL) for size-reduction prior to shipment to the SRS for final disposition.

  7. Decommissioning of Salaspils nuclear reactor

    International Nuclear Information System (INIS)

    In May 1995, the Latvian Government decided to shut down the Research Reactor Salaspils (SRR) and to dispense with nuclear energy in future. The reactor has been out of operation since July 1998. A conceptual study for the decommissioning of SRR has been carried out by Noell-KRC-Energie- und Umwelttechnik GmbH from 1998-1999. he Latvian Government decided on 26 October 1999 to start the direct dismantling to 'green field' in 2001. The results of decommissioning and dismantling performed in 1999-2001 are presented and discussed. The main efforts were devoted to collecting and conditioning 'historical' radioactive waste from different storages outside and inside the reactor hall. All radioactive material more than 20 tons were conditioned in concrete containers for disposal in the radioactive waste depository 'Radons' in the Baldone site. Personal protective and radiation measurement equipment was upgraded significantly. All non-radioactive equipment and material outside the reactor buildings were free-released and dismantled for reuse or conventional disposal. Weakly contaminated material from the reactor hall was collected and removed for free-release measurements. The technology of dismantling of the reactor's systems, i.e. second cooling circuit, zero power reactors and equipment, is discussed in the paper. (author)

  8. Uranium hexafluoride production plant decommissioning

    International Nuclear Information System (INIS)

    The Institute of Energetic and Nuclear Research - IPEN is a research and development institution, located in a densely populated area, in the city of Sao Paulo. The nuclear fuel cycle was developed from the Yellow Cake to the enrichment and reconversion at IPEN. After this phase, all the technology was transferred to private enterprises and to the Brazilian Navy (CTM/SP). Some plants of the fuel cycle were at semi-industrial level, with a production over 20 kg/h. As a research institute, IPEN accomplished its function of the fuel cycle, developing and transferring technology. With the necessity of space for the implementation of new projects, the uranium hexafluoride (UF6) production plant was chosen, since it had been idle for many years and presented potential leaking risks, which could cause environmental aggression and serious accidents. This plant decommission required accurate planning, as this work had not been carried out in Brazil before, for this type of facility, and there were major risks involving gaseous hydrogen fluoride aqueous solution of hydrofluoric acid (HF) both highly corrosive. Evaluations were performed and special equipment was developed, aiming to prevent leaking and avoid accidents. During the decommissioning work, the CNEN safety standards were obeyed for the whole operation. The environmental impact was calculated, showing to be not relevant.The radiation doses, after the work, were within the limits for the public and the area was released for new projects. (author)

  9. The decommissioning NPP A-1

    International Nuclear Information System (INIS)

    Project of decommissioning NPP A-1 is split into 4 main groups of tasks. Tasks in group 1 are focused on the solution of selected problems that have immediate impact on the environment. It is mainly the solution of problems in the building of cleaning station of wastage water and in the building with underground storage tanks for wastage water and solid radwaste, including the prevention of wash-out and penetration of contaminated soil from these buildings into surface and underground waters. A part of addressing these tasks is a controlled of generated radwaste-predominatly sludge with various physical and chemical properties. Tasks in group 2- following the removal of spent fuel-are focused on the management of all radwaste in the long-term storage facility, in the short-term storage facility, equipment of transport and technology part, equipment in hot cells. Tasks in group 3 are focused on development of technology procedures for treatment and conditioning of sludge, contaminated soils and concrete crush, saturated ionexes and ash from incineration facility of the Bohunice radwaste treatment and conditioning complex. Tasks in group 4 are focused on the methodology. And technical support for particular activities applicable during decommissioning NPP

  10. Government Assigns New Supervisory Task. Safe Decommissioning

    International Nuclear Information System (INIS)

    When the Government decided to shutdown one of the two Barsebaeck reactors in February of 1998, it presented SKI with a task that came much earlier than expected; the supervision of the decommissioning of a reactor. As a result of proposals presented in Parliament, SKI began the formulation of a long-term strategy in 1997 for the inspection of a nuclear plant during the decommissioning process. As a preliminary task, SKI started a research programme dealing with the potential risks associated with the transition from normal operations through shutdown to final deconstruction of the power plant. Emphasis was laid on safety culture issues and on questions of organization, as opposed to an earlier stress on the purely technical aspects of decommissioning. After a long period of uncertainty, following much discussion, in July 1998 a Government decision was finally reached to shutdown the first reactor at Barsebaeck. This was carried out in November 1999. It is still uncertain as to when the other reactor will be decommissioned; a decision is expected at the earliest in 2004. This uncertainty, resulting from the prolonged decision making process, could be detrimental to the safety culture on the site; motivation could diminish, and key personnel could be lost. Decommissioning is a new phase in the life cycle of a plant, giving rise to new inspection issues of supervision. During the period of uncertainty, while awaiting SKI has identified ten key areas, dealing with the safety culture of the organization, in connection with the decommissioning of Barsebaeck 1. 1. Obtaining and retaining staff competence during decommissioning; 2. Sustaining organizational memory; 3. Identifying key organizational functions and management skills that are critical during the transition from operations to decommissioning. 4. Sustaining organizational viability and accountability for decommissioning; 5. Sustaining motivation and trust in management of dismantlement; 6. Overseeing contractors; 7. Decommissioning multi-unit sites when one unit continues to operate; 8. Delaying dismantling of decommissioning nuclear power plants; 9. Establishing organizational processes and control systems to identify and address emerging as well as known safety issues; 10. Determining and communicating the level of risk during decommissioning. The list of safety issues that can be linked to safety culture, and questions of organisation, illustrates the scope of supervision that must be performed during decommissioning of a nuclear power plant. Given the myriad of complex activities taking place, this focus is a useful way to assist the regulator to articulate concerns to the power plant management in terms of links to potential safety problems

  11. Planning of the BN-350 reactor decommissioning

    International Nuclear Information System (INIS)

    The experimental and commercial BN-350 NPP equipped with a fast neutron sodium cooled reactor is located in Kazakhstan near the Aktau city on the Caspian Sea coast. It was commissioned in 1973 and intended for weapon-grade plutonium production and as stream supply to a water desalination facility and the turbines of the Mangyshlak Atomic Energy Complex. Taking into account technical, financial and political issues, the Government of Kazakhstan enacted the Decree no. 456 'On Decommissioning of the Reactor BN-350 in the Aktau City of the Mangystau Region'. Because the decision on reactor decommissioning was adopted before the end of scheduled operation (2003), the plan to decommission the BN-350 reactor has not yet been developed. To determine the activities required for ensuring reactor safety and in preparation for decommission in the period prior, the development and ensuring approval by the Republic of Kazakhstan Government of the decommissioning plan, a 'Plan of Priority Actions for BN-350 Reactor Decommissioning' was developed and approved. Actions provided for in the plan include the following: Development of BN-350 Reactor Decommissioning Plan; Accident prevention during the period of transition; Unloading nuclear fuel from reactor and draining the coolant from the heat exchange circuits. Decommission is defined as a complex of administrative and technical actions taken to allow the removal of some or all of regulatory controls over a nuclear facility. These actions involve decontamination, dismantling and removal of radioactive materials, waste, components and structures. They are carried out to achieve a progressive and systematic reduction in radiological hazards and are undertaken on the basis of planning and assessment in order to ensure safety decommissioning operations. In accordance with the decision of Kazakhstan Government, three basic stages for BN-350 reactor decommissioning are envisaged: First stage - Placement of BN-350 into long-term storage SAFSTOR; Second stage - SAFSTOR; Third stage - Dismantling (partial or complete). According to international experience, the decommissioning of a nuclear reactor is an extremely expensive activity. Therefore, Kazakhstan organizations involved in the decommissioning are trying as much as possible to draw from the experience, technologies and financial and technical support of potential donor countries, In order ti achieve this goal, Kazakhstan, with the financial and technical support of the US, EC and Japan, is developing a BN-350 Decommissioning Plan for international peer review. The main objective of the plan is identify areas of potential technical support by technologically developed countries

  12. Decommissioning of nuclear power technological and research installations

    International Nuclear Information System (INIS)

    Strategy of reactor decommissioning was summarized on the World experience base. Analysis of Ukrainian NPP decommissioning process for three versions of the following nuclear power complex development is presented. Examples of organization and management in industrial NPP's decommissioning (USA, England, Japan, Russia) and research reactors (Russia, USA, Japan, Ukraine) are considered. Immediate dismantling during research reactor WWR-M decommissioning is proposed. 11 refs

  13. The decommissioning plan of the Nuclear Ship MUTSU

    International Nuclear Information System (INIS)

    This paper describes the review about the decommissioning plan and present state of the Nuclear Ship Mutsu. The decommissioning of the Mutsu is carried out by Removal and Isolation method. The procedure of the decommissioning works is presented in this paper. The decommissioning works started in April, 1992 and it takes about four years after her last experimental voyage. (author)

  14. Methodology and technology of decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older nuclear facilities which are or soon will be retired from service. In response to increased international interest in decommissioning and to the needs of Member States, the IAEA's activities in this area have increased during the past few years and will be enhanced considerably in the future. A long range programme using an integrated systems approach covering all the technical, regulatory and safety steps associated with the decommissioning of nuclear facilities is being developed. The database resulting from this work is required so that Member States can decommission their nuclear facilities in a safe time and cost effective manner and the IAEA can effectively respond to requests for assistance. The report is a review of the current state of the art of the methodology and technology of decommissioning nuclear facilities including remote systems technology. This is the first report in the IAEA's expanded programme and was of benefit in outlining future activities. Certain aspects of the work reviewed in this report, such as the recycling of radioactive materials from decommissioning, will be examined in depth in future reports. The information presented should be useful to those responsible for or interested in planning or implementing the decommissioning of nuclear facilities

  15. Decommissioning standards: the radioactive waste impact

    International Nuclear Information System (INIS)

    Several considerations are important in establishing standards for decommissioning nuclear facilities, sites and materials. The review includes discussions of some of these considerations and attempts to evaluate their relative importance. Items covered include the form of the standards, timing for decommissioning, occupational radiation protection, costs and financial provisions, and low-level radioactive waste. Decommissioning appears more closely related to radiation protection than to waste management, although it is often carried under waste management programs or activities. Basically, decommissioning is the removal of radioactive contamination from facilities, sites and materials so that they can be returned to unrestricted use or other actions designed to minimize radiation exposure of the public. It is the removed material that is the waste and, as such, it must be managed and disposed of in an environmentally safe manner. It is important to make this distinction even though, for programmatic purposes, decommissioning may be carried under waste management activities. It was concluded that the waste disposal problem from decommissioning activities is significant in that it may produce volumes comparable to volumes produced during the total operating life of a reactor. However, this volume does not appear to place an inordinate demand on shallow land burial capacity. It appears that the greater problems will be associated with occupational exposures and costs, both of which are sensitive to the timing of decommissioning actions

  16. Waste management in decommissioning projects at KAERI

    International Nuclear Information System (INIS)

    Two decommissioning projects are carried out at the KAERI (Korean Atomic Energy Research Institute), one for the Korea research reactors, KRR-1 and KRR-2, and another for the uranium conversion plant (UCP). The concept of the management of the wastes from the decommissioning sites was reviewed with a relation of the decommissioning strategies, technologies for the treatment and the decontamination, and the characteristics of waste. All the liquid waste generated from KRR-1 and KRR-2 decommissioning site is evaporated by a solar evaporation facility and all the liquid waste from the UCP is treated together with lagoon sludge waste. The solid wastes from the decommissioning sites are categorized into three groups; not contaminated, restricted releasable and radioactive waste. The not-contaminated waste will be reused and/or disposed at an industrial disposal site, and the releasable waste is stored for the future disposal at the KAERI. The radioactive waste is packed in containers, and will be stored at the decommissioning sites till they are sent to a national repository site. The reduction of the radioactive solid waste is one of the strategies for the decommissioning projects and could be achieved by the repeated decontamination. By the achievement of the minimization strategy, the amount of radioactive waste was reduced and the disposal cost will be reduced, but the cost for manpower, for direct materials and for administration was increased

  17. Ecological risk assessment of depleted uranium in the environment at Aberdeen Proving Ground

    International Nuclear Information System (INIS)

    A preliminary ecological risk assessment was conducted to evaluate the effects of depleted uranium (DU) in the Aberdeen Proving Ground (APG) ecosystem and its potential for human health effects. An ecological risk assessment of DU should include the processes of hazard identification, dose-response assessment, exposure assessment, and risk characterization. Ecological risk assessments also should explicitly examine risks incurred by nonhuman as well as human populations, because risk assessments based only on human health do not always protect other species. To begin to assess the potential ecological risk of DU release to the environment we modeled DU transport through the principal components of the aquatic ecosystem at APG. We focused on the APG aquatic system because of the close proximity of the Chesapeake Bay and concerns about potential impacts on this ecosystem. Our objective in using a model to estimate environmental fate of DU is to ultimately reduce the uncertainty about predicted ecological risks due to DU from APG. The model functions to summarize information on the structure and functional properties of the APG aquatic system, to provide an exposure assessment by estimating the fate of DU in the environment, and to evaluate the sources of uncertainty about DU transport

  18. Genetic variability in calving success in Aberdeen Angus cows under extensive recording.

    Science.gov (United States)

    Urioste, J I; Chang, Y M; Naya, H; Gianola, D

    2007-09-01

    Data from 2032 Uruguayan Aberdeen Angus cows under extensive management and recording practices were analysed with Bayesian threshold-liability sire models, to assess genetic variability in calving success (CS), defined as a different binary trait for each of the second (CS2), third (CS3) and fourth (CS4) calving opportunities. Sire (herd) variances ranged from 0.08 to 0.11 (0.10 to 0.20) and heritability from 0.27 to 0.35, with large credibility intervals. Correlations between herd effects on CS at different calving opportunities were positive. Genetic correlation between CS2 and CS4 was positive (0.68), whereas those involving adjacent calving opportunities (CS2-CS3 and CS3-CS4) were negative, at -0.39 and -0.54, respectively. The residual correlation CS2-CS3 was negative (-0.32). The extent of uncertainty associated with the posterior estimates of the parameters was further evaluated through simulation, assuming different true values (-0.4, -0.2, +0.2 and +0.4) for the genetic correlations and changes in the degree of belief parameters of the inverse Wishart priors for the sire covariance matrix. Although inferences were not sharp enough, CS appears to be moderately heritable. The quality of data recording should be improved, in order to effect genetic improvement in female fertility. PMID:22444852

  19. Neuroblastoma with neuronal differentiation in the spinal cord in an Aberdeen Angus heifer calf.

    Science.gov (United States)

    Steinberg, H; Peek, S F; Nelson, K M

    2006-03-01

    A 5-month-old, female, Aberdeen Angus heifer presented to the veterinary medical teaching hospital for evaluation of slowly progressive hindlimb ataxia. The calf was clinically normal until 4 months of age, following routine pregnancy and delivery. Neurologic examination revealed marked symmetric spastic hindlimb paraparesis. Thoracolumbar radiographs and cerebrospinal fluid (CSF) analysis were unremarkable. A presumptive diagnosis of T3-L3 myelopathy was made, and neurologic status remained static for 3 months with broad-spectrum antibiotic and nonsteroidal anti-inflammatory therapy. Additional diagnostic tests were refused, and a necropsy was performed following euthanasia. A moderately well delineated, reddish-tan, soft mass 18 mm in diameter replaced 80% of the fourth lumbar spinal cord segment. Histologic examination revealed two distinct features: undifferentiated, primitive, polygonal-to-round cells with typical morphologic characteristics of primitive neuroectoderm; and interspersed areas containing myelinated axons and cells with neuronal differentiation. Immunohistochemical examination confirmed the presence of primitive neuroepithelium and cells with neuronal differentiation. PMID:16537939

  20. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 1: Remedial investigation results

    International Nuclear Information System (INIS)

    This report presents the results of the remedial investigation (RI) conducted at J-Field in the Edgewood Area of Aberdeen Proving Ground (APG), a U.S. Army installation located in Harford County, Maryland. Since 1917, activities in the Edgewood Area have included the development, manufacture, and testing of chemical agents and munitions and the subsequent destruction of these materials at J-Field by open burning and open detonation. These activities have raised concerns about environmental contamination at J-Field. This RI was conducted by the Environmental Conservation and Restoration Division, Directorate of Safety, Health and Environmental Division of APG, pursuant to requirements outlined under the Comprehensive Environmental Response, Compensation, and Liability Act, as amended (CERCLA). The RI was accomplished according to the procedures developed by the U.S. Environmental Protection Agency (EPA 1988). The RI provides a comprehensive evaluation of the site conditions, nature of contaminants present, extent of contamination, potential release mechanisms and migration pathways, affected populations, and risks to human health and the environment. This information will be used as the basis for the design and implementation of remedial actions to be performed during the remedial action phase, which will follow the feasibility study (FS) for J-Field

  1. Spatial relationships among soil biota in a contaminated grassland ecosystem at Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Kuperman, R. [Army ERDEC, Aberdeen Proving Ground, MD (United States); Williams, G. [Argonne National Lab., IL (United States); Parmelee, R. [Ohio State Univ., Columbus, OH (United States)

    1995-12-31

    Spatial relationships among soil nematodes and soil microorganisms were investigated in a grassland ecosystem contaminated with heavy metals in the US Army`s Aberdeen Proving Ground. The study quantified fungal and bacterial biomass, the abundance of soil protozoa, and nematodes. Geostatistical techniques were used to determine spatial distributions of these parameters and to evaluate various cross-correlations. The cross-correlations among soil biota numbers were analyzed using two methods: a cross general relative semi-variogram and an interactive graphical data representation using geostatistically estimated data distributions. Both the visualization technique and the cross general relative semi-variogram and an interactive graphical data representation using geostatistically estimated data distributions. Both the visualization technique and the cross general relative semi-variogram showed a negative correlation between the abundance of fungivore nematodes and fungal biomass, the abundance of bacterivore nematodes and bacterial biomass, the abundance of omnivore/predator nematodes and numbers of protozoa, and between numbers of protozoa and both fungal and bacterial biomass. The negative cross-correlation between soil biota and metal concentrations showed that soil fungi were particularly sensitive to heavy metal concentrations and can be used for quantitative ecological risk assessment of metal-contaminated soils. This study found that geostatistics are a useful tool for describing and analyzing spatial relationships among components of food webs in the soil community.

  2. Hydrogeologic and chemical data for the O-Field area, Aberdeen Proving Ground, Maryland

    International Nuclear Information System (INIS)

    O-Field, located at the Edgewood area of Aberdeen Proving Ground, Maryland, was periodically used for disposal of munitions, waste chemicals, and chemical-warfare agents from World War II through the 1950's. This report includes various physical, geologic, chemical, and hydrologic data obtained from well-core, groundwater, surface water, and bottom-sediment sampling sites at and near the O-Field disposal area. The data are presented in tables and hydrographs. Three site-location maps are also included. Well-core data include lithologic logs for 11 well-cluster sites, grain-size distributions, various chemical characteristics, and confining unit characteristics. Groundwater data include groundwater chemistry, method blanks for volatile organic carbon, available data on volatile and base/neutral organics, and compilation of corresponding method blanks, chemical-warfare agents, explosive-related products, radionuclides, herbicides, and groundwater levels. Surface-water data include field-measured characteristics; concentrations of various inorganic constituents including arsenic; selected organic constituents with method blanks; detection limits of organics; and a compilation of information on corresponding acids, volatiles, and semivolatiles; and method blanks corresponding to acids, volatiles, and semivolatiles. A set of 15 water-level hydrographs for the period March 1986 through September 1987 also is included in the report. 3 refs., 18 figs., 24 tabs

  3. Contamination source review for Building E3162, Edgewood Area, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Miller, G.A.; Draugelis, A.K.; Rueda, J.; Zimmerman, R.E.

    1995-09-01

    This report was prepared by Argonne National Laboratory (ANL) to document the results of a contamination source review for Building E3162 at the Aberdeen Proving Ground (APG) in Maryland. The report may be used to assist the US Army in planning for the future use or disposition of this building. The review included a historical records search, physical inspection, photographic documentation, geophysical investigation, and collection of air samples. The field investigations were performed by ANL during 1994 and 1995. Building E3162 (APG designation) is part of the Medical Research Laboratories Building E3160 Complex. This research laboratory complex is located west of Kings Creek, east of the airfield and Ricketts Point Road, and south of Kings Creek Road in the Edgewood Area of APG. The original structures in the E3160 Complex were constructed during World War 2. The complex was originally used as a medical research laboratory. Much of the research involved wound assessment involving chemical warfare agents. Building E3162 was used as a holding and study area for animals involved in non-agent burns. The building was constructed in 1952, placed on inactive status in 1983, and remains unoccupied. Analytical results from these air samples revealed no distinguishable difference in hydrocarbon and chlorinated solvent levels between the two background samples and the sample taken inside Building E3162.

  4. Environmental geophysics at the Southern Bush River Peninsula, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Davies, B.E.; Miller, S.F.; McGinnis, L.D. [and others

    1995-05-01

    Geophysical studies have been conducted at five sites in the southern Bush River Peninsula in the Edgewood Area of Aberdeen Proving Ground, Maryland. The goals of the studies were to identify areas containing buried metallic objects and to provide diagnostic signatures of the hydrogeologic framework of the site. These studies indicate that, during the Pleistocene Epoch, alternating stands of high and low sea level resulted in a complex pattern of channel-fill deposits. Paleochannels of various sizes and orientations have been mapped throughout the study area by means of ground-penetrating radar and EM-31 techniques. The EM-31 paleochannel signatures are represented onshore either by conductivity highs or lows, depending on the depths and facies of the fill sequences. A companion study shows the features as conductivity highs where they extend offshore. This erosional and depositional system is environmentally significant because of the role it plays in the shallow groundwater flow regime beneath the site. Magnetic and electromagnetic anomalies outline surficial and buried debris throughout the areas surveyed. On the basis of geophysical measurements, large-scale (i.e., tens of feet) landfilling has not been found in the southern Bush River Peninsula, though smaller-scale dumping of metallic debris and/or munitions cannot be ruled out.

  5. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 1: Remedial investigation results

    Energy Technology Data Exchange (ETDEWEB)

    Yuen, C. R.; Martino, L. E.; Biang, R. P.; Chang, Y. S.; Dolak, D.; Van Lonkhuyzen, R. A.; Patton, T. L.; Prasad, S.; Quinn, J.; Rosenblatt, D. H.; Vercellone, J.; Wang, Y. Y.

    2000-03-14

    This report presents the results of the remedial investigation (RI) conducted at J-Field in the Edgewood Area of Aberdeen Proving Ground (APG), a U.S. Army installation located in Harford County, Maryland. Since 1917, activities in the Edgewood Area have included the development, manufacture, and testing of chemical agents and munitions and the subsequent destruction of these materials at J-Field by open burning and open detonation. These activities have raised concerns about environmental contamination at J-Field. This RI was conducted by the Environmental Conservation and Restoration Division, Directorate of Safety, Health and Environmental Division of APG, pursuant to requirements outlined under the Comprehensive Environmental Response, Compensation, and Liability Act, as amended (CERCLA). The RI was accomplished according to the procedures developed by the U.S. Environmental Protection Agency (EPA 1988). The RI provides a comprehensive evaluation of the site conditions, nature of contaminants present, extent of contamination, potential release mechanisms and migration pathways, affected populations, and risks to human health and the environment. This information will be used as the basis for the design and implementation of remedial actions to be performed during the remedial action phase, which will follow the feasibility study (FS) for J-Field.

  6. Decommissioning of French nuclear submarines

    International Nuclear Information System (INIS)

    Since the beginning of the sixties, France has developed a fleet of nuclear powered vessels. Insofar as the ships of the 2. generation are being built, the older ones are decommissioned and enter the dismantling process. The average rate is presently one submarine decommissioned every two or three years. The overall strategy for the decommissioning of French nuclear submarines can be brought down to 3 phases: 1. Level 1 dismantling which essentially consists in: - unloading the spent fuel and storing it in a pool ; - possibly emptying the circuits which contain radioactive liquids. The level 1 is easily achieved, as it is not very different from the plant situation during ship overhaul or major refits. 2. Level 2 dismantling which consists in isolating the nuclear reactor compartment from the rest of the submarine and conditioning it for interim storage on a ground facility located inside Cherbourg Naval Dockyard. The rest of the ship is decontaminated, controlled and set for scrap like any conventional submarine. Up to now, the policy has been to keep the reactor compartment in this intermediate storage facility for at least 20 years, a duration calculated to allow enough time for short life corrosion products to disappear and hence, reduce the radioactive dose to workers during the level 3 dismantling operations. 3. Level 3 dismantling of the nuclear reactor compartment after a storage period. These operations consist in cutting into pieces all remaining structures and equipment, conditioning and sending them to ANDRA for disposal. The SSBN Le Redoutable, first French nuclear submarine which was removed from active service en 1991, underwent the first two phases but, forward and stern parts after cutting of the reactor compartment have been sealed and turned into a museum which is now part of 'La Cite de la Mer' in Cherbourg. Among the three other SSBNs removed from active service, two are at the end of phase 1 just before the separation of the reactor compartment and one is waiting for phase 2. What kind of waste is produced and in what quantities? What means are used to condition and treat this waste? We propose giving some answers to these questions, by discussing firstly the spent fuels (the only high-level activity waste), and secondly the solid and liquid waste of low and medium activity

  7. Deactivation, Decontamination and Decommissioning Project Summaries

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, David Shane; Webber, Frank Laverne

    2001-07-01

    This report is a compilation of summary descriptions of Deactivation, Decontamination and Decommissioning, and Surveillance and Maintenance projects planned for inactive facilities and sites at the INEEL from FY-2002 through FY-2010. Deactivations of contaminated facilities will produce safe and stable facilities requiring minimal surveillance and maintenance pending further decontamination and decommissioning. Decontamination and decommissioning actions remove contaminated facilities, thus eliminating long-term surveillance and maintenance. The projects are prioritized based on risk to DOE-ID, the public, and the environment, and the reduction of DOE-ID mortgage costs and liability at the INEEL.

  8. Pipeline Decommissioning Trial AWE Berkshire UK - 13619

    Energy Technology Data Exchange (ETDEWEB)

    Agnew, Kieran [AWE, Aldermaston, Reading, RG7 4PR (United Kingdom)

    2013-07-01

    This Paper details the implementation of a 'Decommissioning Trial' to assess the feasibility of decommissioning the redundant pipeline operated by AWE located in Berkshire UK. The paper also presents the tool box of decommissioning techniques that were developed during the decommissioning trial. Constructed in the 1950's and operated until 2005, AWE used a pipeline for the authorised discharge of treated effluent. Now redundant, the pipeline is under a care and surveillance regime awaiting decommissioning. The pipeline is some 18.5 km in length and extends from AWE site to the River Thames. Along its route the pipeline passes along and under several major roads, railway lines and rivers as well as travelling through woodland, agricultural land and residential areas. Currently under care and surveillance AWE is considering a number of options for decommissioning the pipeline. One option is to remove the pipeline. In order to assist option evaluation and assess the feasibility of removing the pipeline a decommissioning trial was undertaken and sections of the pipeline were removed within the AWE site. The objectives of the decommissioning trial were to: - Demonstrate to stakeholders that the pipeline can be removed safely, securely and cleanly - Develop a 'tool box' of methods that could be deployed to remove the pipeline - Replicate the conditions and environments encountered along the route of the pipeline The onsite trial was also designed to replicate the physical prevailing conditions and constraints encountered along the remainder of its route i.e. working along a narrow corridor, working in close proximity to roads, working in proximity to above ground and underground services (e.g. Gas, Water, Electricity). By undertaking the decommissioning trial AWE have successfully demonstrated the pipeline can be decommissioned in a safe, secure and clean manor and have developed a tool box of decommissioning techniques. The tool box of includes; - Hot tapping - a method of breaching the pipe while maintaining containment to remove residual liquids, - Crimp and shear - remote crimping, cutting and handling of pipe using the excavator - Pipe jacking - a way of removing pipes avoiding excavations and causing minimal disturbance and disruption. The details of the decommissioning trial design, the techniques employed, their application and effectiveness are discussed and evaluated here in. (authors)

  9. Modelling of nuclear power plant decommissioning financing

    International Nuclear Information System (INIS)

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. (authors)

  10. Stakeholder involvement in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Significant numbers of nuclear facilities will need to be decommissioned in the coming decades. In this context, NEA member countries are placing increasing emphasis on the involvement of stakeholders in the associated decision procedures. This study reviews decommissioning experience with a view to identifying stakeholder concerns and best practice in addressing them. The lessons learnt about the end of the facility life cycle can also contribute to better foresight in siting and building new facilities. This report will be of interest to all major players in the field of decommissioning, in particular policy makers, implementers, regulators and representatives of local host communities

  11. Decommissioning and reclamation of ANHUA uranium mine

    International Nuclear Information System (INIS)

    Since the late 1980s a number of uranium production facilities in China were closed and are in various stages of decommissioning. To date 5 mines have been decommissioned. ANHUA mine is situated in west part of Hunan province in South China. The production of uranium ore began in 1974 and stopped in 1986. Decommissioning and reclamation programme started in July 1992 and completed in May 1997. This paper describes the experience in sealing of drift entrances, covering of waste rock piles and rehabilitation of cadmium contaminated farmland with replantation. (author)

  12. Development of a Decommissioning Certificate Program; TOPICAL

    International Nuclear Information System (INIS)

    A Decommissioning Certificate Program has been developed at Washington State University Tri-Cities (WSU TC) in conjunction with Bechtel Hanford, Inc. (BHI), and the U.S. Department of Energy (DOE)to address the increasing need for qualified professionals to direct and manage decommissioning projects. The cooperative effort between academia, industry, and government in the development and delivery of this Program of education and training is described, as well as the Program's design to prepare students to contribute sooner, and at a higher level, to decommissioning projects

  13. Considerations about the European Decommissioning Academy (EDA)

    International Nuclear Information System (INIS)

    The concept of the European Decommissioning Academy, to be launched in Slovakia in June 2015, is described. The main goal is to educate a new generation of experts in the decommissioning of nuclear facilities, with focus on VVER type reactors. This year the Academy activities will include lessons, practical exercises in laboratories, and 2 days on-site training at the Jaslovske Bohunice V-1 nuclear power plant. A 4-days' visit to major European decommissioning facilities in Switzerland and Italy is also planned. (orig.)

  14. Pipeline Decommissioning Trial AWE Berkshire UK - 13619

    International Nuclear Information System (INIS)

    This Paper details the implementation of a 'Decommissioning Trial' to assess the feasibility of decommissioning the redundant pipeline operated by AWE located in Berkshire UK. The paper also presents the tool box of decommissioning techniques that were developed during the decommissioning trial. Constructed in the 1950's and operated until 2005, AWE used a pipeline for the authorised discharge of treated effluent. Now redundant, the pipeline is under a care and surveillance regime awaiting decommissioning. The pipeline is some 18.5 km in length and extends from AWE site to the River Thames. Along its route the pipeline passes along and under several major roads, railway lines and rivers as well as travelling through woodland, agricultural land and residential areas. Currently under care and surveillance AWE is considering a number of options for decommissioning the pipeline. One option is to remove the pipeline. In order to assist option evaluation and assess the feasibility of removing the pipeline a decommissioning trial was undertaken and sections of the pipeline were removed within the AWE site. The objectives of the decommissioning trial were to: - Demonstrate to stakeholders that the pipeline can be removed safely, securely and cleanly - Develop a 'tool box' of methods that could be deployed to remove the pipeline - Replicate the conditions and environments encountered along the route of the pipeline The onsite trial was also designed to replicate the physical prevailing conditions and constraints encountered along the remainder of its route i.e. working along a narrow corridor, working in close proximity to roads, working in proximity to above ground and underground services (e.g. Gas, Water, Electricity). By undertaking the decommissioning trial AWE have successfully demonstrated the pipeline can be decommissioned in a safe, secure and clean manor and have developed a tool box of decommissioning techniques. The tool box of includes; - Hot tapping - a method of breaching the pipe while maintaining containment to remove residual liquids, - Crimp and shear - remote crimping, cutting and handling of pipe using the excavator - Pipe jacking - a way of removing pipes avoiding excavations and causing minimal disturbance and disruption. The details of the decommissioning trial design, the techniques employed, their application and effectiveness are discussed and evaluated here in. (authors)

  15. Modelling of nuclear power plant decommissioning financing.

    Science.gov (United States)

    Bemš, J; Knápek, J; Králík, T; Hejhal, M; Kubančák, J; Vašíček, J

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. PMID:25979740

  16. Bankruptcy potential threatens decommissioning funds, says NRC

    International Nuclear Information System (INIS)

    Electric utilities and the Nuclear Regulatory Commission (NRC) disagreed at an America Nuclear Society seminar on how reactor decommissioning should be financed. Industry and state regulators claim it should be handled by standard depreciation methods without involving the NRC, which argues that it must guard against safety risks from industry bankruptices and premature decommissioning. Both sides agreed that funds must be collected, but disagreed on the best method. Their options include the deposit method, external sinking fund, internal reserve, and insurance or surety bond. The NRC feels that too many utilities face possible bankruptcy unrelated to decommissioning or accidents, and that this possibility should outweigh other considerations. 1 table

  17. UK policy for nuclear decommissioning: viewpoint

    International Nuclear Information System (INIS)

    The importance of the United Kingdom Government formulating a policy for the decommissioning of nuclear installations is stressed in this article because of the UK's aging nuclear reactors, especially the Magnox type reactors, the decommissioning of which is likely to cause particular difficulties. Funds have not, so far, been properly set aside, as estimated costs continue to rise, nor have actual management strategies been developed. The author raises ethical, environmental, technical and economic objections to current plans to postpone decommissioning until 100 years after reactors are closed. (UK)

  18. TA-2 Water Boiler Reactor Decommissioning Project

    International Nuclear Information System (INIS)

    This final report addresses the Phase 2 decommissioning of the Water Boiler Reactor, biological shield, other components within the biological shield, and piping pits in the floor of the reactor building. External structures and underground piping associated with the gaseous effluent (stack) line from Technical Area 2 (TA-2) Water Boiler Reactor were removed in 1985--1986 as Phase 1 of reactor decommissioning. The cost of Phase 2 was approximately $623K. The decommissioning operation produced 173 m3 of low-level solid radioactive waste and 35 m3 of mixed waste. 15 refs., 25 figs., 3 tabs

  19. Social effects of decommissioning Trawsfynydd Power Station

    International Nuclear Information System (INIS)

    The decision to close Trawsfynydd in 1993 had significant implications for the staff and local community. The site is situated within a National Park and local employment opportunities are limited. The staff and local communities were consulted regarding the issues arising from closure and decommissioning. This consultation influenced the decommissioning strategy for the site, with emphasis placed on the mitigation of the effects of closure. Subsequent studies have shown that the adopted strategies have served to limit the social and economic effects. The experience at Trawsfynydd has proved to be generally applicable at other decommissioning sites. (author)

  20. Development of a Decommissioning Certificate Program

    International Nuclear Information System (INIS)

    A Decommissioning Certificate Program has been developed at Washington State University Tri-Cities (WSU TC) in conjunction with Bechtel Hanford, Inc. (BHI), and the U.S. Department of Energy (DOE)to address the increasing need for qualified professionals to direct and manage decommissioning projects. The cooperative effort between academia, industry, and government in the development and delivery of this Program of education and training is described, as well as the Program's design to prepare students to contribute sooner, and at a higher level, to decommissioning projects

  1. Decommissioning and decontrolling the R1-reactor

    International Nuclear Information System (INIS)

    Sweden's first nuclear reactor - the research reactor R1 - situated in bedrock under the Royal Technical Institute of Stockholm, has in the period 1981-1983 been subject to a complete decommissioning. The National Institute for Radiation Protection has followed the work in detail, and has after the completion of the decommissioning performed measurements of radioactivity on site. The report gives an account of the work the Institute has done in preparation for- and during decommissioning and specifically report on the measurements for classification of the local as free for non-nuclear use. (aa)

  2. Counting the real cost of decommissioning

    International Nuclear Information System (INIS)

    In our review of the recent UK National Audit Office's (NAO's) study into the economics of nuclear decommissioning (PiE150/1), we reported that the NAO's analysis - particularly of the uncertainties of the process-tended to suggest a final decommissioning figure rather higher than the Pound 18bn of undiscounted industry estimates. Nuclear Electric took exception to this, and to other aspects of our report. In the article, the company's Waste and Decommissioning Manager, presents his personal view of the issues and says much of our report needs to be taken lying down. (author)

  3. Decommissioning the Research Nuclear Reactor Vvr-S Magurele - Analyze, Justification and Selection of Decommissioning Strategy

    Science.gov (United States)

    Dragusin, M.; Popa, V.; Boicu, A.; Tuca, C.; Iorga, I.; Mustata, C.

    2004-09-01

    The decommissioning of Research Nuclear Reactor VVR-S Magurele - Bucharest involves the removal of the radioactive and hazardous materials to permit the facility to be released without representing a further risk to human health and the environment [1-3]. A very important aspect of decommissioning is the analyze, justification and selection of the decommissioning strategy. Two strategies: DECON (Immediate Dismantling) and SAFSTOR (Safe Enclosure) are in study (see Table 1)... Note from Publisher: This article contains the abstract and references only.

  4. Decommissioning of NS OTTO HAHN

    International Nuclear Information System (INIS)

    With NS OTTO HAHN for the first time a nuclear propelled merchant vessel has been regularly decommissioned after more than 10 years of successful operation. Based on the concept of the total decontamination about 1100 ts of contaminated and decontaminated components have been dismantled and removed from board ship. 260 ts of contaminated components packed in 10 ft containers and 400-liter drums and the 480 ts RPV unit are stored at the GKSS site for post investigations. A total mass of about 370 ts has been decontaminated by mechanical and chemical procedures below the required radiological limits. The nuclear status of OTTO HAHN has been removed by the competent licensing authority in June 1982 so that the vessel is now offered for sale for conventionel operations. 8 references, 11 figures

  5. Decommissioning cost estimates based on the international structure for decommissioning costing

    International Nuclear Information System (INIS)

    Decommissioning cost estimates is essential part of decommissioning planning in all stages of nuclear installation lifetime. It has been recognized that there is a variety of formats, content and practice in decommissioning costing, due to the specific national requirement or to different assumptions. These differences make the process of decommissioning costing less transparent and more complicated to review. To solve these issues the document: 'A Proposed Standardised List of Items for Costing Purposes in the Decommissioning of Nuclear Installation' (known as 'Yellow Book') was jointly published by IAEA, OECD/NEA and EC in 1999. After a decade, the document was revised and issued by same organizations under the title: 'International Structure for Decommissioning Costing (ISDC) of Nuclear Installation. ISDC as the list of typical decommissioning activities (could be used also a check-list) provides s general cost structure suitable for use for all types of nuclear installations i.e. power plants, research reactors, fuel cycle facilities or laboratories. The purpose of the ISDC, is to facilitate the communication and to promote uniformity and to provide a common platform in presenting the decommissioning costs. Clear definition of ISDC items supports the common understanding of cost items, i.e. what is behind the cost. ISDC decommissioning activities are organised in a hierarchical structure, with the 1st and 2nd levels being aggregations of basic activities identified at the 3rd level. At (author)

  6. ECED 2013: Eastern and Central Europe Decommissioning. International Conference on Decommissioning of Nuclear Facilities. Conference Guide and Book of Abstracts

    International Nuclear Information System (INIS)

    The Conference included the following sessions: (I) Opening session (2 contributions); (II) Managerial and Funding Aspects of Decommissioning (5 contributions); (III) Technical Aspects of Decommissioning I (6 contributions); (IV) Experience with Present Decommissioning Projects (4 contributions); (V) Poster Session (14 contributions); (VI) Eastern and Central Europe Decommissioning - Panel Discussion; (VII) Release of Materials, Waste Management and Spent Fuel Management (6 contributions); (VIII) Technical Aspects of Decommissioning II (5 contributions).

  7. Decommissioning of DR 1, Final report

    International Nuclear Information System (INIS)

    The report describes the decommissioning activities carried out at the 2kW homogeneous reactor DR 1 at Risoe National Laboratory. The decommissioning work took place from summer 2004 until late autumn 2005. The components with the highest activity, the core vessel the recombiner and the piping and valves connected to these, were dismantled first by Danish Decommissioning's own technicians. Demolition of the control rod house and the biological shield as well as the removal of the floor in the reactor hall was carried out by an external demolition contractor. The building was emptied and left for other use. Clearance measurements of the building showed that radionuclide concentrations were everywhere below the clearance limit set by the Danish nuclear regulatory authorities. Furthermore, measurements on the surrounding area showed that there was no contamination that could be attributed to the operation and decommissioning of DR 1. (au)

  8. Nuclear submarine decommissioning and related environmental problems

    International Nuclear Information System (INIS)

    The issue of nuclear powered submarines occupies a particular place among the problems related to nuclear wastes. Nuclear submarines that were withdrawn from military service as well as those intended fro utilization represent a potential source of both nuclear and radiation hazard. By the beginning of 1966 more than one hundred and fifty nuclear powered vessels were decommissioned in Russia both for the reason of expiration of their service life and due to treaties on reduction of strategic offensive weapons. By 200 this number is expected to increase to one hundred and seventy-eighty units. According to published data the number of nuclear submarines decommissioned in USA to date exceeds twenty units. Major problems associated with utilization of nuclear submarines are related to safety and special security measures are to undertaken for decommissioned nuclear submarines. One of the most significant problems is related with management and/or storage of spent fuel from decommissioned nuclear submarines

  9. Decommissioning of DR 1, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Lauridsen, Kurt

    2006-01-15

    The report describes the decommissioning activities carried out at the 2kW homogeneous reactor DR 1 at Risoe National Laboratory. The decommissioning work took place from summer 2004 until late autumn 2005. The components with the highest activity, the core vessel the recombiner and the piping and valves connected to these, were dismantled first by Danish Decommissioning's own technicians. Demolition of the control rod house and the biological shield as well as the removal of the floor in the reactor hall was carried out by an external demolition contractor. The building was emptied and left for other use. Clearance measurements of the building showed that radionuclide concentrations were everywhere below the clearance limit set by the Danish nuclear regulatory authorities. Furthermore, measurements on the surrounding area showed that there was no contamination that could be attributed to the operation and decommissioning of DR 1. (au)

  10. Health physics considerations in decontamination and decommissioning

    International Nuclear Information System (INIS)

    These proceedings contain papers on legal considerations, environmental aspects, decommissioning equipment and methods, instrumentation, applied health physics, waste classification and disposal, and project experience. Separate abstracts have been prepared for individual papers

  11. The total decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    The following nuclear facilities in the Federal Republic of Germany are now ready for total decommissioning: the power plant Niederaichbach (KKN), the nuclear ship Otto Hahn and the research reactor FR2. Planning work on KKN commenced in 1979 and the approval procedure was begun in early 1980 when the approval contract was submitted. At the beginning of 1980 the contract for decommissioning the nuclear facilities on the Otto Hahn was awarded. Approval was received in December 1980 and work was begun on decommissioning the plant. FR2 is still in operation and will be shut down at the end of 1981. Planning work for decommissioning the nuclear part began at the end of 1980. The planning and the methods which are intended to be used for the three plants are described. (orig.)

  12. Safety issues in decommissioning, strategies and regulation

    International Nuclear Information System (INIS)

    Many plants throughout the world are undergoing decommissioning. There are some differences in the safety issues associated with decommissioning as compared with operations. These pose challenges to operators, regulators and those responsible for developing policies and strategies.The paper aims to set the scene for future discussion by identifying these issues. This includes regulatory systems, regulating the changing situation and factors that need to be taken into account in developing decommissioning strategies. In particular, the situation in the absence of a disposal route for waste and issues associated with care and maintenance periods are discussed.A key point that is identified is that well considered and justified strategies need to be developed to act as the basis for detailed decommissioning plans. (author)

  13. Decommissioning and disposal costs in Switzerland

    International Nuclear Information System (INIS)

    Introduction Goal: Secure sufficient financial resources. Question: How much money is needed? Mean: Concrete plans for decommissioning and waste disposal. - It is the task of the operators to elaborate these plans and to evaluate the corresponding costs - Plans and costs are to be reviewed by the authorities Decommissioning Plans and Costs - Comprise decommissioning, dismantling and management (including disposal) of the waste. - New studies 2001 for each Swiss nuclear power plant (KKB 2 x 380 MWe, KKM 370 MWe, KKG 1020 MWe, KKL 1180 MWe). - Studies performed by NIS (D). - Last developments taken into account (Niederaichbach, Gundremmingen, Kahl). Decommissioning: Results and Review Results: Total cost estimates decreasing (billion CHF) 1994 1998 2001 13.7 13.1 11.8 Lower costs for spent fuel conditioning and BE/HAA/LMA repository (Opalinus Clay) Split in 2025: 5.6 bil. CHF paid by NPP 6.2 billion CHF in Fund Review: Concentrates on disposal, ongoing

  14. The cost of decommissioning uranium mill tailings

    International Nuclear Information System (INIS)

    This report identifies several key operations that are commonly carried out during decommissioning of tailings areas in the Canadian environment. These operations are unit costed for a generic site to provide a base reference case. The unit costs have also been scaled to the quantities required for the decommissioning of four Canadian sites and these scaled quantities compared with site-specific engineering cost estimates and actual costs incurred in carrying out the decommissioning activities. Variances in costing are discussed. The report also recommends a generic monitoring regime upon which both short- and longer-term environmental monitoring costs are calculated. Although every site must be addressed as a site-specific case, and monitoring programs must be tailored to fit a specific site, it would appear that for the conventional decommissioning and monitoring practices that have been employed to date, costs can be reasonably estimated when site-specific conditions are taken into account

  15. Waste Management for Decommissioning of Nuclear Power Plants: An EPRI Decommissioning Program Report - Waste Management for Decommissioning of Nuclear Power Plants. An EPRI Decommissioning Project Report

    International Nuclear Information System (INIS)

    The Electric Power Research Institute (EPRI) is a non-profit research organization that conducts research related to the generation, delivery, use, and environmental impacts of electricity. EPRI also conducts research for the safe and optimized decommissioning of nuclear power plants through its Decommissioning and Remediation Technology Program. The decommissioning of a nuclear power plant involves the safe disposition of a large quantity of radioactive, hazardous and conventional waste. The logistics of characterizing, staging, packaging and shipment of this waste needs to be carefully planned so as to support the decommissioning project schedule. The most efficient decommissioning and waste management process is one in which effective waste management and disposal options are available as the waste is being generated so as not to delay or impede the progress of decommissioning. As the cost of waste disposal is a large component of the total decommissioning budget, the optimal treatment and disposal option needs to be chosen for each type of waste. Waste must be generated, classified, and segregated in such as manner as to take advantage of all available disposal pathways: clearance, very low level waste, non-radioactive/hazardous waste, and low level waste disposal sites. This approach will help to avoid the unnecessary use of scarce disposal capacity for the higher activity waste. There has been a number of nuclear power plant decommissioning projects successfully completed in the United States. These projects have used various waste disposal options and developed successful methods for handling the large quantities of waste created by the decommissioning. Additionally, decommissioning projects in Europe are in progress or in the planning stages such that strategies for the handling of decommissioning waste are being developed and/or implemented to address the regulatory requirements and disposal options available in these countries. EPRI is preparing a report on decommissioning waste management experiences that will provide summaries of: - Waste management experiences in the United States during power plant decommissioning projects. - Waste management plans and experiences for some of the decommissioning projects in other countries that are in progress where these plans have been developed or are being implemented. In line with the subject of this symposium, this paper will focus on the disposition of metal waste from decommissioning including the following: - Experiences in the U.S where disposal costs are relatively low and large components can often be disposed of in one piece in shallow land burial. These factors and lack of clearance levels have limited the cost benefit of metal recycle in the United States. - In other countries, particularly in Europe, relatively high waste disposal costs and established clearance levels have resulted in the development of processing methods to reduce the volume of radioactive waste requiring disposal. How clearance, decontamination and metal melting contribute to these developments will be discussed in this paper. In summary, how volume reduction techniques including contaminated metal processing have helped reduce the total quantity of waste resulting from decommissioning will be discussed. (authors)

  16. Fatores de correção para perímetro escrotal ao sobreano para tourinhos mestiços Aberdeen Angus x Nelore Adjustment factors for scrotal circumference at yearling for crossbred Aberdeen Angus x Nelore young bulls

    OpenAIRE

    Lopes, J S; P.R.N. Rorato; Weber, T.; J.G. Comin; R.O Araújo

    2009-01-01

    Obtiveram-se fatores de correção (FC) para o perímetro escrotal ao sobreano (PES) para os efeitos de grupo genético (GG), heterozigose individual (HI), peso ao sobreano (PS) e idade do animal à pesagem de sobreano (IDS), utilizando-se registros de peso corporal e medidas de perímetro escrotal obtidos de 11.662 tourinhos das raças Aberdeen Angus, Nelore e de produtos do cruzamento entre elas, criados nas regiões Sul, Sudeste e Centro-Oeste do Brasil, nascidos entre 1987 e 2001. Os coeficientes...

  17. Regulation of decommissioning in the United Kingdom

    International Nuclear Information System (INIS)

    Since 1940, the United Kingdom's (UK) nuclear programme has included the decommissioning of Research Reactors; Fuel Conversion, Enrichment and Fabrication Plants; Power Reactors, and Waste Treatment Plants. The newly formed Nuclear Decommissioning Authority (NDA) has developed a programme for all of the UK's civil nuclear liabilities including five Magnox reactors that are currently undergoing decommissioning, two undergoing defuelling and four due to cease operation over the next 5 years. The UK Health and Safety Executive's (HSE) Nuclear Installations Inspectorate (NII) regulates safety and the management of radioactive waste at nuclear licensed sites in the United Kingdom. The main legislation is the Health and Safety at Work Act 1974 (HSAW74) and its associated statutory provisions, which include the Nuclear Installations Act (as amended) 1965 (NIA 65). Additionally, NII enforces the Nuclear Reactors (Environmental Impact Assessment for Decommissioning) Regulations 1999. Under NIA65, no site may be used for installing or operating any nuclear installation unless a site licence has been granted by the HSE. NIA65 allows HSE to attach conditions to the site licence in the interests of safety, or with respect to the handling, treatment and disposal of nuclear matter, including radioactive waste. These licence conditions include decommissioning arrangements, supervision and control, emergency arrangements, training, operating rules and operating instructions. NII is reviewing the regulation of decommissioning Magnox power reactors, to ensure its approach to regulation remains proportionate and consistent. The review includes consideration of hazard levels and associated risks at such sites; public expectations of regulators; regulation of the health and safety of workers; environmental impact assessment and management; and the need to optimise the effectiveness of NII's inspectors. The paper summarises UK's approach to regulation of decommissioning nuclear facilities and presents the considerations included within the review of regulation of decommissioning Magnox power reactors. (author)

  18. Russian nuclear-powered submarine decommissioning

    International Nuclear Information System (INIS)

    Russia is facing technical, economic and organizational difficulties in dismantling its oversized and unsafe fleet of nuclear powered submarines. The inability of Russia to deal effectively with the submarine decommissioning crisis increases the risk of environmental disaster and may hamper the implementation of the START I and START II treaties. This paper discusses the nuclear fleet support infrastructure, the problems of submarine decommissioning, and recommends international cooperation in addressing these problems

  19. Decommissioning of a 5 MW research reactor

    International Nuclear Information System (INIS)

    The complete decommissioning of a research reactor is described. Planning and execution of all activities, including schedules, budgets, waste management, health physics and subcontracted operations are presented. Flexibility in operations was obtained by using the operating staff as the decommissioning progressed. Totals for waste shipments and costs are given. Final site conditions are presented along with a description of the subsequent use of the facility. (author)

  20. SGDes project. Decommissioning management system of Enresa

    International Nuclear Information System (INIS)

    ENRESA, the public company responsible for managing radioactive waste produced in spain and nuclear facilities decommissioning work, has developed a management information system (SGDes) for the decommissioning of nuclear power plants, critical for the company. SGDes system is capable of responding to operational needs for efficient, controlled and secure way. Dismantling activities require a rigorous operations control within highly specialized, process systematization and safety framework, both the human and technological point of view. (Author)

  1. Decommissioning of the BR3 PWR

    Energy Technology Data Exchange (ETDEWEB)

    Massaut, V.; Klein, M

    1998-07-01

    The objectives, programme and main achievements of SCK-CEN's decommissioning programme in 1997 are summarised. Particular emphasis is on the BR3 decommissioning project. In 1997, auxiliary equipment and loops were dismantled; concrete antimissile slabs were decontaminated; the radiology of the primary loop was modelled; the quality assurance procedure for dismantling loops and equipment were implemented; a method for the dismantling of the reactor pressure vessel was selected; and contaminated thermal insulation of the primary loop containing asbestos was removed.

  2. Decommissioning of the BR3 PWR

    International Nuclear Information System (INIS)

    The objectives, programme and main achievements of SCK-CEN's decommissioning programme in 1997 are summarised. Particular emphasis is on the BR3 decommissioning project. In 1997, auxiliary equipment and loops were dismantled; concrete antimissile slabs were decontaminated; the radiology of the primary loop was modelled; the quality assurance procedure for dismantling loops and equipment were implemented; a method for the dismantling of the reactor pressure vessel was selected; and contaminated thermal insulation of the primary loop containing asbestos was removed

  3. Decommissioning Project Manager's Implementing Instructions (PMII)

    International Nuclear Information System (INIS)

    Decommissioning Project personnel are responsible for complying with these PMII. If at any time in the performance of their duties a conflict between these instructions and other written or verbal direction is recognized or perceived, the supervisor or worker shall place his/her work place in a safe condition, stop work, and seek resolution of the conflict from the Decommissioning Project Manager or his designee

  4. Risk Management of Large Component in Decommissioning

    International Nuclear Information System (INIS)

    The need for energy, especially electric energy, has been dramatically increasing in Korea. Therefore, a rapid growth in nuclear power development has been achieved to have about 30% of electric power production. However, such a large nuclear power generation has been producing a significant amount of radioactive waste and other matters such as safety issue. In addition, owing to the severe accidents at the Fukushima in Japan, public concerns regarding NPP and radiation hazard have greatly increased. In Korea, the operation of KORI 1 has been scheduled to be faced with end of lifetime in several years and Wolsong 1 has been being under review for extending its life. This is the reason why the preparation of nuclear power plant decommissioning is significant in this time. Decommissioning is the final phase in the life-cycle of a nuclear facility and during decommissioning operation, one of the most important management in decommissioning is how to deal with the disused large component. Therefore, in this study, the risk in large component in decommissioning is to be identified and the key risk factor is to be analyzed from where can be prepared to handle decommissioning process safely and efficiently. Developing dedicated acceptance criteria for large components at disposal site was analyzed as a key factor. Acceptance criteria applied to deal with large components like what size of those should be and how to be taken care of during disposal process strongly affect other major works. For example, if the size of large component was not set up at disposal site, any dismantle work in decommissioning is not able to be conducted. Therefore, considering insufficient time left for decommissioning of some NPP, it is absolutely imperative that those criteria should be laid down

  5. Risk Management of Large Component in Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Nah, Kyung Ku; Kim, Tae Ryong [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2014-10-15

    The need for energy, especially electric energy, has been dramatically increasing in Korea. Therefore, a rapid growth in nuclear power development has been achieved to have about 30% of electric power production. However, such a large nuclear power generation has been producing a significant amount of radioactive waste and other matters such as safety issue. In addition, owing to the severe accidents at the Fukushima in Japan, public concerns regarding NPP and radiation hazard have greatly increased. In Korea, the operation of KORI 1 has been scheduled to be faced with end of lifetime in several years and Wolsong 1 has been being under review for extending its life. This is the reason why the preparation of nuclear power plant decommissioning is significant in this time. Decommissioning is the final phase in the life-cycle of a nuclear facility and during decommissioning operation, one of the most important management in decommissioning is how to deal with the disused large component. Therefore, in this study, the risk in large component in decommissioning is to be identified and the key risk factor is to be analyzed from where can be prepared to handle decommissioning process safely and efficiently. Developing dedicated acceptance criteria for large components at disposal site was analyzed as a key factor. Acceptance criteria applied to deal with large components like what size of those should be and how to be taken care of during disposal process strongly affect other major works. For example, if the size of large component was not set up at disposal site, any dismantle work in decommissioning is not able to be conducted. Therefore, considering insufficient time left for decommissioning of some NPP, it is absolutely imperative that those criteria should be laid down.

  6. Russian nuclear-powered submarine decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Bukharin, O. [Princeton Univ., NJ (United States); Handler, J. [Greenpeace International`s Disarmament Campaign, Washington, DC (United States)

    1995-11-01

    Russia is facing technical, economic and organizational difficulties in dismantling its oversized and unsafe fleet of nuclear powered submarines. The inability of Russia to deal effectively with the submarine decommissioning crisis increases the risk of environmental disaster and may hamper the implementation of the START I and START II treaties. This paper discusses the nuclear fleet support infrastructure, the problems of submarine decommissioning, and recommends international cooperation in addressing these problems.

  7. Applicability of EPRI Decommissioning Pre-Planning Manual to International Decommissioning Projects

    International Nuclear Information System (INIS)

    Industry models for planning the efficient decommissioning of a nuclear power plant continue to evolve. Effective planning is a key to cost control, a critical aspect of decommissioning. In 2001, the Electric Power Research Institute (EPRI) published the 'Decommissioning Pre-Planning Manual', referred to as the 'Manual'. The goal of the Manual was to develop a framework for use in pre-planning the decommissioning of a nuclear power plant. The original research was based on information collected during the active decommissioning of power reactors in New England, and the ongoing decommissioning planning of another reactor still in operation. The research team identified thirty-two (32) major Decommissioning Tasks that support the strategic and tactical planning that can be conducted in advance of plant shutdown. The Decommissioning Tasks were organized in a logical sequence of execution, and sorted in common discipline groupings. Owners of U.S. nuclear plants that have shut down prematurely during the past 5 years have found the EPRI Decommissioning Pre-Planning Manual useful in developing their transition plans from an operating to shutdown facility. Concurrently, during the past 15 years, the IAEA has published numerous technical and safety reports on nuclear reactor decommissioning planning and execution. IAEA's goal is to provide its global members with useful and timely guidance for the planning and execution of nuclear decommissioning projects. This information has been used extensively by international nuclear plant operators. One of the key objectives will be to develop a road-map linking the 32 EPRI Decommissioning Tasks with the comparable (or equivalent) topics covered in the IAEA library of decommissioning knowledge. The logical and convenient structure of the Manual will be cross-referenced to the IAEA topics to aid in organizing the development of decommissioning plans. The road-map will serve to provide a basis for improved communication and collaboration between U.S. and international decommissioning planners. The paper will also provide a summary of changes that have occurred since the Manual was published in 2001. Major differences and gaps between the Manual and the IAEA will be identified, with recommendations for future development provided. (authors)

  8. Decommissioning cost estimating and contingency application

    International Nuclear Information System (INIS)

    The funding of nuclear power plant decommissioning has matured into an integral part of utility planning. State public utility commission regulators and the US Nuclear Regulatory Commission have recognized the need to assure the availability of funds to safely decommission these facilities at the end of their useful lives. The cost estimates for decommissioning need to reflect the changes in labor and material costs due to inflation, changes in waste disposal costs for packaging, transporting and burying radioactive materials, and the site-specific factors for each unit that account for differences in plant design and construction. Decommissioning activities involve remote tooling to segment the reactor vessel and internals, decontamination of contaminated systems to reduce occupational exposure, controlled blasting to demolish concrete structures, and removal and disposal of radioactive wastes by controlled burial. The unforeseeable problems encountered in performing these activities result in additional costs that are accounted for through contingency. The recent progress in nuclear power plant decommissioning cost estimation and contingency application are discussed. The important factor to be included in planning for the establishment of a decommissioning fund are identified, and typical results of recent estimates are provided. The nuclear industry is probably one of the first industries to plan for the eventual retirement of its facilities, and the public needs to be aware of these efforts

  9. The Importance of Experience Based Decommissioning Planning

    International Nuclear Information System (INIS)

    Decommissioning of a nuclear facility is an extensive and multidisciplinary task, which involves the management and technical actions associated with ceasing operation and thereafter the step-by-step transfer of the facility from an operating plant to an object under decommissioning. The decommissioning phase includes dismantling of systems and components, decontamination and clearance, demolition of buildings, remediation of any contaminated ground and finally a survey of the site. Several of these activities generate radioactive or potentially radioactive waste, which has to be managed properly prior to clearance or disposal. What makes decommissioning of nuclear installations unique is to large extent the radioactive waste management. No other industries have that complex regulatory framework for the waste management. If decommissioning project in the nuclear industry does not consider the waste aspects to the extent required, there is a large risk of failure causing a reduced trust by the regulators and other stakeholders as well as cost and schedule overruns. This paper will give an overview of important aspects and findings gathered during decades of planning and conducting decommissioning and nuclear facility modernization projects. (authors)

  10. An outsider`s view of decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Wilkie, T. [The Independent and The Independent on Sunday Newspapers, London (United Kingdom)

    1996-10-01

    The decommissioning of nuclear facilities is not just a technical or even a financial issue. Presenting decommissioning as a technically difficult task overcome by superhuman effort on the part of the industry will not gain much credit amongst sophisticated consumers who now require that any complex technology will work and work safely. Any engineering problems are surmountable given the money to find the solution. Some of the financial aspects of decommissioning are worrying, however, given their open-ended nature. The cost of waste disposal is one of these. Despite a lapse of fifty years since the start-up of its first reactor, the United Kingdom is unlikely to have available a repository for the disposal of intermediate level waste until about 2020. Waste disposal is a large consideration in decommissioning and the industry`s forecasts of cost in this area lack credibility in the light of a poor track record in financial prediction. Financial engineering in the form of the segregated fund set up in March 1996 to cover the decommissioning of nuclear power stations in the United Kingdom is likely to provide only short term reassurance in the light of doubts about a credible future for nuclear power. This lack of confidence over the wider problems of nuclear power creates particular problems for decommissioning which go beyond technical difficulties and complicate financial considerations. (UK).

  11. Safety in decommissioning of research reactors

    International Nuclear Information System (INIS)

    This Guide covers the technical and administrative considerations relevant to the nuclear aspects of safety in the decommissioning of reactors, as they apply to the reactor and the reactor site. While the treatment, transport and disposal of radioactive wastes arising from decommissioning are important considerations, these aspects are not specifically covered in this Guide. Likewise, other possible issues in decommissioning (e.g. land use and other environmental issues, industrial safety, financial assurance) which are not directly related to radiological safety are also not considered. Generally, decommissioning will be undertaken after planned final shutdown of the reactor. In some cases a reactor may have to be decommissioned following an unplanned or unexpected event of a series or damaging nature occurring during operation. In these cases special procedures for decommissioning may need to be developed, peculiar to the particular circumstances. This Guide could be used as a basis for the development of these procedures although specific consideration of the circumstances which create the need for them is beyond its scope

  12. Investigation on decommissioning of smelting conversion facilities

    International Nuclear Information System (INIS)

    To carry out decommissioning of smelting and conversion plant (containing apparatuses) in future, it is required to develop planned businesses. As JNC constructed a general WBS on the decommissioning on last fiscal years, further detailed investigations on WBS is necessary for promotion of its operations. Therefore, aiming at construction of detailed WBS with less than the fourth level, intention of updating on subdivision and radioactive decommission, and addition of data on determining methods on polluting condition of uranium series wastes, here were reported results on four items, such as reviewing of WBS on the decommissioning, construction of detailed WBS with less than the fourth level, updating of databases on subdivision and decommission, and data addition on determining methods on polluting conditions of uranium series wastes to the subdivision and the decommission databases. On this fiscal year, it was carried out investigation on contents of WBS on the 'Construction of investigating items on subdivision and removal engineerings (sixteen sheets of construction figure)' to consult WBS with less than the fourth level for eight sheets of figure in details on the second item, to carry out literature retrieval on reuse since 1998, to input sixty extracted data to database on the third item, and to carry out literature retrieval on the determining method since 1990, to input eight extracted data to database by preparing a new term in 'testing'. (G.K.)

  13. Online prediction of fatty acid profiles in crossbred Limousin and Aberdeen Angus beef cattle using near infrared reflectance spectroscopy

    OpenAIRE

    Prieto, Nuria; Ross, D. W.; Navajas, E. A.; Richardson, R. I.; Hyslop, J. J.; Simm, G; Roehe, R.

    2011-01-01

    The objective of this study was to examine the online use of near infrared reflectance (NIR) spectroscopy to estimate the concentration of individual and groups of fatty acids (FA) as well as intramuscular fat (IMF) in crossbred Aberdeen Angus (AAx) and Limousin (LIMx) cattle. This was achieved by direct application of a fibre-optic probe to the muscle immediately after exposing the meat surface in the abattoir at 48 h post mortem. Samples of M. longissimus thoracis from 88 AAx and 106 LIMx w...

  14. Potential health impacts from range fires at Aberdeen Proving Ground, Maryland.

    Energy Technology Data Exchange (ETDEWEB)

    Willians, G.P.; Hermes, A.M.; Policastro, A.J.; Hartmann, H.M.; Tomasko, D.

    1998-03-01

    This study uses atmospheric dispersion computer models to evaluate the potential for human health impacts from exposure to contaminants that could be dispersed by fires on the testing ranges at Aberdeen Proving Ground, Maryland. It was designed as a screening study and does not estimate actual human health risks. Considered are five contaminants possibly present in the soil and vegetation from past human activities at APG--lead, arsenic, trichloroethylene (TCE), depleted uranium (DU), and dichlorodiphenyltrichloroethane (DDT); and two chemical warfare agents that could be released from unexploded ordnance rounds heated in a range fire--mustard and phosgene. For comparison, dispersion of two naturally occurring compounds that could be released by burning of uncontaminated vegetation--vinyl acetate and 2-furaldehyde--is also examined. Data from previous studies on soil contamination at APG are used in conjunction with conservative estimates about plant uptake of contaminants, atmospheric conditions, and size and frequency of range fires at APG to estimate dispersion and possible human exposure. The results are compared with US Environmental Protection Agency action levels. The comparisons indicate that for all of the anthropogenic contaminants except arsenic and mustard, exposure levels would be at least an order of magnitude lower than the corresponding action levels. Because of the compoundingly conservative nature of the assumptions made, they conclude that the potential for significant human health risks from range fires is low. The authors recommend that future efforts be directed at fire management and control, rather than at conducting additional studies to more accurately estimate actual human health risk from range fires.

  15. Work plan for conducting an ecological risk assessment at J-Field, Aberdeen Proving Ground, Maryland

    Energy Technology Data Exchange (ETDEWEB)

    Hlohowskyj, I.; Hayse, J.; Kuperman, R. [Argonne National Lab., IL (United States). Environmental Assessment Div.] [and others

    1995-03-01

    The Environmental Management Division of Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation and feasibility study (RI/FS) of the J-Field area at APG pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. J-Field is within the Edgewood Area of APG in Harford County, Maryland, and activities at the Edgewood Area since World War II have included the development, manufacture, testing, and destruction of chemical agents and munitions. The J-Field site was used to destroy chemical agents and munitions by open burning and open detonation. This work plan presents the approach proposed to conduct an ecological risk assessment (ERA) as part of the RI/FS program at J-Field. This work plan identifies the locations and types of field studies proposed for each area of concern (AOC), the laboratory studies proposed to evaluate toxicity of media, and the methodology to be used in estimating doses to ecological receptors and discusses the approach that will be used to estimate and evaluate ecological risks at J-Field. Eight AOCs have been identified at J-Field, and the proposed ERA is designed to evaluate the potential for adverse impacts to ecological receptors from contaminated media at each AOC, as well as over the entire J-Field site. The proposed ERA approach consists of three major phases, incorporating field and laboratory studies as well as modeling. Phase 1 includes biotic surveys of the aquatic and terrestrial habitats, biological tissue sampling and analysis, and media toxicity testing at each AOC and appropriate reference locations. Phase 2 includes definitive toxicity testing of media from areas of known or suspected contamination or of media for which the Phase 1 results indicate toxicity or adverse ecological effects. In Phase 3, the uptake models initially developed in Phase 2 will be finalized, and contaminant dose to each receptor from all complete pathways will be estimated.

  16. Potential health impacts from range fires at Aberdeen Proving Ground, Maryland

    International Nuclear Information System (INIS)

    This study uses atmospheric dispersion computer models to evaluate the potential for human health impacts from exposure to contaminants that could be dispersed by fires on the testing ranges at Aberdeen Proving Ground, Maryland. It was designed as a screening study and does not estimate actual human health risks. Considered are five contaminants possibly present in the soil and vegetation from past human activities at APG--lead, arsenic, trichloroethylene (TCE), depleted uranium (DU), and dichlorodiphenyltrichloroethane (DDT); and two chemical warfare agents that could be released from unexploded ordnance rounds heated in a range fire--mustard and phosgene. For comparison, dispersion of two naturally occurring compounds that could be released by burning of uncontaminated vegetation--vinyl acetate and 2-furaldehyde--is also examined. Data from previous studies on soil contamination at APG are used in conjunction with conservative estimates about plant uptake of contaminants, atmospheric conditions, and size and frequency of range fires at APG to estimate dispersion and possible human exposure. The results are compared with US Environmental Protection Agency action levels. The comparisons indicate that for all of the anthropogenic contaminants except arsenic and mustard, exposure levels would be at least an order of magnitude lower than the corresponding action levels. Because of the compoundingly conservative nature of the assumptions made, they conclude that the potential for significant human health risks from range fires is low. The authors recommend that future efforts be directed at fire management and control, rather than at conducting additional studies to more accurately estimate actual human health risk from range fires

  17. Problems in decommissioning uranium exploration facility and monitoring parameters after decommission

    International Nuclear Information System (INIS)

    This paper discussed the problems in the decommission of uranium exploration facilities. Tailings with the uranium over cut-off grade was suggested to fill back to the pit, while those under cut-off grade can be buried in shallow depth. The parameters to monitor the facility after decommission was also discussed in the paper. (author)

  18. International Atomic Energy Agency activities in decommissioning

    International Nuclear Information System (INIS)

    Full text: The International Atomic Energy Agency (IAEA) has been addressing the safety and technical issues of decommissioning for over 20 years, but their focus has been primarily on planning. Up to know, the activities have been on an ad hoc basis and sometimes, important issues have been missed. A new Action Plan on the Decommissioning of Nuclear Facilities has recently been approved by the Agency's board of Governors which will focus the Agency's efforts and ensure that our Member States' concerns are addressed. The new initiatives associated with this Action Plan will help ensure that decommissioning activities in the future are performed in a safe and coherent manner. The International Atomic Energy Agency (IAEA) has been preparing safety and technical documents concerning decommissioning since the mid-1980's. There have been over 30 documents prepared that provide safety requirements, guidance and supporting technical information. Many of these documents are over 10 years old and need updating. The main focus in the past has been on planning for decommissioning. During the past five years, a set of Safety Standards have been prepared and issued to provide safety requirements and guidance to Member States. However, decommissioning was never a real priority with the Agency, but was something that had to be addressed. To illustrate this point, the first requirements documents on decommissioning were issued as part of a Safety Requirements [1] on pre-disposal management of radioactive waste. It was felt that decommissioning did not deserve its own document because it was just part of the normal waste management process. The focus was mostly on waste management. The Agency has assisted Member States with the planning process for decommissioning. Most of these activities have been focused on nuclear power plants and research reactors. Now, support for the decommissioning of other types of facilities is being requested. The Agency is currently providing technical assistance to Bulgaria, China, Georgia, Kazakhstan, Latvia, Lithuania, Philippines, Romania, Serbia and Montenegro, Slovakia, Tajikistan and Ukraine. This list of countries requesting assistance from the Agency continues to grow every year. A recently published Safety Guide entitled 'Application of the Concepts of Exclusion, Exemption and Clearance' (RS-G-1.7) [2] provides guidance to national authorities and operating organizations on the application of the concepts of exclusion, exemption and clearance as established in the Basic Safety Standards [3]. It provides specific values of activity concentrations for both radionuclides of natural origin and those of artificial origin that may be used for bulk amounts of material for the purposes of applying exemption. The document also provides guidance on the application of these values for clearance

  19. Risk reduction approach to decommissioning hazards of nuclear facilities

    International Nuclear Information System (INIS)

    Highlights: • Risk reduction approach to decommissioning hazards of nuclear facilities. • Radiological and non-radiological hazards of decommissioning activities of nuclear facilities. • Risk assessment for decommissioning hazards. • Countermeasures to radiological hazards and non-radiological hazards. - Abstract: Decommissioning activities include radiological hazards and non-radiological hazards. Radiological hazards are mainly due to radiation exposure whereas non-radiological hazards are mainly due to industrial hazards such as fire, explosions, toxic materials, and electrical and physical hazards. Based on characteristics of decommissioning activities, risk calculation method of decommissioning hazards and countermeasures of radiological hazards and non-radiological hazards were suggested

  20. Securing decommissioning funds. Why organization matters?

    International Nuclear Information System (INIS)

    Full text: Securing decommissioning funds requires that the financial resources set aside for the purpose of decommissioning be managed prudently. Decommissioning of nuclear power plant is prescribed by National Atomic Laws or by other nuclear legislation. It is a mandatory operation. The operators of nuclear power plants set money aside for that purpose. This is known as 'Decommissioning reserve fund'. Decommissioning implies costs very distant in time. Thus, it is obvious, from an economic point of view, that the funds set aside should be managed. As decommissioning is mandatory, the funds accumulated should be secured. In others words, they should be available when needed. Availability of funds is influenced by endogenous and exogenous factors. Endogenous factors are a matter of design of the reserve funds. They include the management of the funds, its monitoring and control... Availability of funds is influenced by these factors, depending on the rules to which the behaviour of the manager of the funds is subjected. In contrast, exogenous factors deal with the energy context. These factors are mainly the electricity sector organisation and/or the overall economic situation. They are decisive factors of the economic performance of the reserve fund for a given design. Therefore, the requirement of availability of funds, when needed, is a matter of compatibility between the design of the decommissioning funds and the electricity context. Put differently, reserve fund's design need to be consistent with the electricity context's features in respect of the availability of funds. Current reserve funds were designed in a context of monopoly regime. In this context, availability of decommissioning funds was not questionable. At least, as far as the design of the reserve funds is concerned. This is because nuclear generator didn't confront any competition pressure. Electricity prices were set trough rate base mechanism, and all the business risks were borne by the customers. Because of electricity sector restructuring, businesses are no longer protected from market sanctions and stock market volatility. The objective of this paper is to evaluate the compatibility of the design of reserve fund models with the liberalised electricity context. The paper first considers the design of reserve funds and concludes that there is no single design. Based on the variety of design, section two assess their respective compatibility with the new electricity context. It appears that the monitoring and control of the management of the funds are the main determinant of compatibility. The paper concludes that, as secure funding is a dimension of safe decommissioning, there is a necessity for an optimal design of decommissioning funds model. The paper also suggests that external management solution improve the credibility of decommissioning commitment. This paper has completed two objectives. Firstly, it has highlighted the diversity of designs of the decommissioning reserve funds. We have seen that the reserve funds are organised differently, regarding the key features of their design, namely the collection of funds, the management of the funds collected, and the monitoring and control of that management. Secondly, and in respect of the objective to ensure the availability of the funds when needed, the paper has shown that current designs of decommissioning reserve funds are not equally compatible with the constraints of the electricity sector liberalisation. In fact, the new electricity context is characterised by electricity price volatility with, at some conditions, harmful effects on the financial viability of electric companies. The paper has shown that external fund designs offer a satisfactory compatibility with these constraints. This is because the design of external funds imposes clear limitations on the behaviour of the manager of the funds. Therefore, the paper suggests that in a context of liberalised electricity market, external funds model improves the credibility of the commitment to handle the financial burden of decommissioning

  1. Decommissioning Challenges, strategy and programme development

    International Nuclear Information System (INIS)

    This document gathers 4 short articles. The first one presents the IAEA decommissioning activities. These activities include: -) the development and implementation of the international action on decommissioning, -) the provision of experts and equipment to assist member states, -) networking activities such as training or exchange of knowledge and experience. The second article presents the work program of the Nea (nuclear energy agency) in the field of decommissioning and reports on the lessons that have been learnt. Among these lessons we can quote: -) selecting a strategy for decommissioning and funding it adequately, -) regulating the decommissioning of nuclear activities, -) thinking of the future in terms of reusing materials, buildings and sites, -) involving local and regional actors in the decommissioning process from decision-making to dismantling work itself, and -) increasing transparency in decision-making in order to build trust. The third article presents the management of radioactive wastes in France. This management is based on the categorization of wastes in 6 categories according to both the activity level and the radioactive half-life T: 1) very low activity, 2) low activity and T 31 years, 4) intermediate activity and T 31 years, and 6) high activity. For categories 1, 2, 3 and 5, the waste treatment process and the disposal places have been operating for a long time while for categories 4 and 6, the disposal places are still being studied: low-depth repository and deep geological repository respectively. The last article presents the action of the US Department of energy in decommissioning activities and environmental remediation, the example of the work done at the ancient nuclear site of Rocky Flats gives an idea of the magnitude and complexity of the operations made. (A.C.)

  2. Decommissioning of fast reactors after sodium draining

    International Nuclear Information System (INIS)

    Acknowledging the importance of passing on knowledge and experience, as well mentoring the next generation of scientists and engineers, and in response to expressed needs by Member States, the IAEA has undertaken concrete steps towards the implementation of a fast reactor data retrieval and knowledge preservation initiative. Decommissioning of fast reactors and other sodium bearing facilities is a domain in which considerable experience has been accumulated. Within the framework and drawing on the wide expertise of the Technical Working Group on Fast Reactors (TWG-FR), the IAEA has initiated activities aiming at preserving the feedback (lessons learned) from this experience and condensing those to technical recommendations on fast reactor design features that would ease their decommissioning. Following a recommendation by the TWG-FR, the IAEA had convened a topical Technical Meeting (TM) on 'Operational and Decommissioning Experience with Fast Reactors', hosted by CEA, Centre d'Etudes de Cadarache, France, from 11 to 15 March 2002 (IAEA-TECDOC- 1405). The participants in that TM exchanged detailed technical information on fast reactor operation and decommissioning experience with various sodium cooled fast reactors, and, in particular, reviewed the status of the various decommissioning programmes. The TM concluded that the decommissioning of fast reactors to reach safe enclosure presented no major difficulties, and that this had been accomplished mainly through judicious adaptation of processes and procedures implemented during the reactor operation phase, and the development of safe sodium waste treatment processes. However, the TM also concluded that, on the path to achieving total dismantling, challenges remain with regard to the decommissioning of components after sodium draining, and suggested that a follow-on TM be convened, that would provide a forum for in-depth scientific and technical exchange on this topic. This publication constitutes the Proceedings of this follow-up TM held in Cadarache, France, 26-30 September 2005

  3. Decommissioning: Think about the back end first

    International Nuclear Information System (INIS)

    Full text: Decommissioning is different from operating a nuclear plant.While both involve a reactor, the priorities and activities differ. This summary will address the keys to successful decommissioning as learned from decommissioning Fermi 1. This project shows that plants can be decommissioned after a safe storage period. Fermi 1 was a sodium cooled fast breeder reactor that was permanently shut down in 1972. Decommissioning is under way now following a safe storage period. The four keys to successful decommissioning are: Thinking about the back end first; Planning where you are going; Evaluating how you will get there; Assessing the journey. The most important key is to think about the back end first: think about the waste that will be generated before work is started. This waste needs to be assessed from more than just the radiological standpoint. For example, some paints at Fermi 1 contain lead and/or PCBs. Work was stopped earlier this year when more paint was found to have PCBs than expected from earlier sampling. A hazards assessment programme was prepared and arrangements made for waste disposal of painted equipment, piping and structural members before dismantling resumed of any materials where the paint could contain PCBs. In planning the removal of sodium residues, the by-products from the reaction of the residues in situ needed to be addressed. Plans were made for contaminated hydrogen gas and caustic before starting the processing. Waste needs to be characterized before it is produced for both radiological and hazardous constituents. Good planning that integrates waste management with activity planning is essential for success. To plan where the project is going, first the end state needs to be determined. Then steps to get the facility in the desired condition can be evaluated. The steps need to be communicated, then scheduled.The schedule needs to be communicated for success. Safety is the key to evaluating how the end state will be reached. Safety is more important during decommissioning than plant operation. There are more challenges and people are performing hazardous activities daily. The hazards need to be evaluated for each activity and work planned to minimize hazards. As decommissioning proceeds, what has been learned at the facility and by others needs to be assessed.Then, what should continue to be done and what should be changed to be safer or more efficient can be identified. The biggest lesson from the Fermi 1 decommissioning project is that hazardous materials and conditions need to be considered first before starting work activities to ensure that waste can be disposed of and people will go home safely at the end of every day. (author)

  4. Germany: Management of decommissioning waste in Germany

    International Nuclear Information System (INIS)

    Over the past two decades, Germany has gained a substantial amount of experience in the decommissioning of nuclear facilities of different types and sizes. Many research reactors and all prototype nuclear power plants, as well as a few larger nuclear power plants and fuel cycle facilities, are currently at varying stages of decommissioning. Several facilities have been fully dismantled and the sites have been cleared for reuse. The decommissioning projects comprise 18 power and prototype reactors, 33 research reactors and 11 fuel cycle facilities which are being or have been decommissioned. In the future, further nuclear power plants will be shut down and decommissioned in accordance with Germany?s energy policy to phase out the use of nuclear power for commercial electricity generation as given in the April 2002 amendment of the Atomic Energy Act. Radioactive waste, from operations as well as from decommissioning activities, is to be conditioned in such a way as to comply with the waste acceptance requirements of a repository. In Germany, all types of radioactive waste (i.e., short-lived and long-lived) are to be disposed of in deep geological formations. A distinction is being made for heat generating waste (i.e., high level waste) and waste with negligible heat generation (i.e., low level and intermediate level waste). Radioactive decommissioning waste is waste with negligible heat generation. Waste acceptance requirements of a repository are of particular importance for the conditioning of radioactive waste, including decommissioning waste. The waste acceptance requirements, as they resulted from the Konrad licensing procedure, are being applied by the waste generators for the conditioning of decommissioning waste. Compliance with these requirements must be demonstrated through the waste package quality control, even if the waste will be disposed of in the future. In 2002 the Konrad repository was licensed for the disposal of all types of waste with negligible heat generation. Konrad is an abandoned iron-ore mine to be reconstructed for use as disposal facility. It is not yet in operation as the license is actually examined by court. Dismissal of legal action is an important prerequisite for the realization of the Konrad project. Furthermore, the Federal Government needs to take a final decision on the reconstruction and operation of the Konrad repository. (author)

  5. Productive performance and carcass traits of Nellore x Aberdeen Angus and Nellore x Red Angus heifers under tropical conditions

    Directory of Open Access Journals (Sweden)

    Paulo Sérgio Andrade Moreira

    2015-08-01

    Full Text Available Background: Angus breed strains (Black and Red perform differently under tropical conditions. Objective: to evaluate differences among F1 Nellore x Aberdeen Angus and F1 Nellore x Red Angus regarding productive performance and carcass traits under tropical conditions. Methods: forty-one heifers were used to assess the effect of both genetic groups on productive performance and carcass traits. The performance parameters evaluated were final live body weight and average daily gain. The carcass traits were: 1 hot and cold carcass weight and cold carcass dressing percentage, 2 carcass conformation and fatting (both ranging from 1 to 5, 3 back fat thickness, 4 rib eye area, 5 cutability, and 6 total usable meat, and commercial cut yield. Animals were divided in two groups and fed Megathyrsus maximum grass in three pens for 28 days. After this period, animals were relocated in a feedlot system for 84 days, and weighed at the beginning and at the end. All data were subjected to analysis of variance with initial live weight as a covariate. Results: differences were found between groups for productive performance and carcass traits such as back fat, and rib eye area. However, no difference was observed for conformation, fatting, ease of cutability, total usable meat, and Brazilian commercial cuts. Conclusion: F1 Nellore x Aberdeen Angus heifers had increased growth performance and carcass traits under tropical conditions.

  6. Closing responsibilities: decommissioning and the law

    International Nuclear Information System (INIS)

    Laws change over time, with the times. Interpretations of old laws shift and the need for new laws emerges. There are endless reasons for these necessary changes, but the basic impetus is the changing nature of societal circumstance. Fifty years ago there were no laws directly governing nuclear power in any way. Today we know that nuclear power touches people from their wallets to their descendants. Currently, many laws related to nuclear power are in place, laws which protect all sectors of society from electricity generating bodies to a newborn child, and the Chernobyl accident has broadened the legal ramifications of nuclear power even more. This expanding body of nuclear law reflects our expanding understanding of nuclear power from its technical beginnings to its societal consequences and implications. The law is now beginning to reflect the growing significance of decommissioning. What are the relationships between decommissioning and the existing laws, government agencies, and policies? Ironically, although the UK will lead the world in addressing decommissioning responsibilities, there are no explicit laws in place to govern the process. In the absence of specific legislation governing decommissioning, the primary responsibilities fall to the operators of the power plants, a circumstance not lost on those involved in privatization. In this chapter, the wide and varied legal ramifications of decommissioning are examined. (author)

  7. Economical aspect of the decommissioning for NPP

    International Nuclear Information System (INIS)

    The estimated, analysed and founding of the economical aspect at decommissioning of Nuclear Power Plant (NPP) have been studied. The data that have been obtained from literature, then the calculation and analysing have been done base to the future condition. The cost for NPP decommissioning depend on the internal factor such as type, capacity and safe storage time, and the external factor such as policy, manpower and the technology preparation. The successfulness of funding, depend on the rate of inflation, discount rate of interest and the currency fluctuation. For the internal factor, the influence of the type of the reactor (BWR or PWR) to the decommissioning cost is negligible, the big reactor capacity (±1100 MW), and the safe storage between 30 to 100 years are recommended, and for the external factor, specially Indonesia, to meet the future need the ratio of decommissioning cost and capital cost will be lower than in develop countries at the present (10%). The ratio between decommissioning fund and electricity generation cost relatively very low, are more less than 1.79 % for 30 years safe storage, and discount rate of interest 3%, or more less than 0.30 % for safe storage 30 years, and discount rate of interest 6%. (author)

  8. Verification for radiological decommissioning - Lessons learned

    International Nuclear Information System (INIS)

    During the past 10 years, the Environmental Survey and Site Assessment Program (ESSAP) at Oak ridge Associated Universities has performed radiological surveys to confirm the adequacy of cleanup and/or decommissioning actions at sites and facilities where radioactive materials have been handled. These surveys are part of the independent oversight programs of the US Department of Energy (DOE) and the US Nuclear Regulatory Commission (NRC). Results of verification activities have been discouraging. Numerous independent surveys have identified residual contamination requiring further remediation; in some cases, initial decontamination and postremedial action monitoring were totally inadequate. While participating in decommission projects, ESSAP learned valuable lessons and has given this information to regulating agencies and decommissioning sites. The goal of this presentation is to highlight the difficulties encountered by ESSAP in its involvement with NRC and DOE decommissioning projects. Decommissioning projects require teamwork, and success depends to a large degree on the communication, cooperation, and coordination of efforts among the individual organizations involved. This information could be used by organizations involved in future decontamination projects to avoid some of the pitfalls associated with this process

  9. Management of Sellafield site decommissioning - recent experiences

    International Nuclear Information System (INIS)

    History of the British Nuclear Site Sellafield - located in Western Cambria goes back to 1940, when it served for military and energy independence tasks in the Great Britain. Since then Sellafield served as the major British nuclear site providing wide range of services to the British nuclear industry, including fuel and waste storage/management, nuclear fuel reprocessing, electricity production and decommissioning. Currently the Sellafield site is one of the largest site under decommissioning facing serious challenges associated with the process and cost management. In November 2008 the Nuclear Management Partners, the consortium consisting URS Washington Group, AMEC and AREVA NC, were awarded the contract as the new Parent Body Organization of Sellafield Ltd. that provides management expertise and governance to the client (Nuclear Decommissioning Authority). Since 2008 AMEC has gained extensive experiences from management of complex decommissioning projects that are applicable across different geographies and projects of similar nature. Presentation describes the development of the process system of the project management from the side of PBO as well as complex scheme of the Sellafield site decommissioning project. (author)

  10. Legislative conditions for decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Decommissioning nuclear facilities, like building and operating them, is associated with legal conditions spelt out in the German Atomic Energy Act and other applicable legal regulations. Under the Atomic Energy Act, the basis is the required permit for decommissioning with the main requirement that all necessary precautions against damage have been taken in the light of the state of the art. Applicability needs to be examined in each individual case, and every decommissioning step must reduce the risk potential by further removing radioactive plant components. Considerable expense is entailed by the Environmental Impact Assessment (EIA) required under the directives of the European Union. The directive in existence so far required an EIA only for the construction and operation of nuclear power plants, and was executed in Germany with the EIA Act of 1990. This EU directive is being extended so as to include also decommissioning activities; the integration of this extension into national law in Germany is still in the stage of a ministerial draft bill. In the licensing procedure under the Atomic Energy Act, the basic question arises with respect to the demolition of plants whether the 'entire range planned' of decommissioning measures requires a step-by-step procedure with a so-called positive overall decision. This question arises out of the comparison between the construction phase and the demolition phase. Basically, in very few special cases, an analogy can be drawn to the requirement of a preliminary positive overall decision. (orig.)

  11. Panel Discussion - Eastern and Central Europe decommissioning

    International Nuclear Information System (INIS)

    In conjunction with technical session 'Experience with Present Decommissioning Projects' the Panel Discussion is organized in the frame of ECED 2013 Conference. The main purposes of the panel was to analyse more in details the information given in the previous session and mainly to answer the questions from the audience. The panel was focused on the on-going decommissioning projects and on the projects in the final phase of preparation in the region of Eastern and Central Europe as follows: - Ignalina Nuclear Power Plant in Lithuania - RBMK-1500 reactors; - Chernobyl Nuclear Power Plant in Ukraine - RBMK-1000 reactors; - Kozloduy Nuclear Power Plant in Bulgaria - VVER-440 reactors; - Metsamor Armenian Nuclear Power Plant - VVER-440 reactors; - Greifswald Nuclear Power Plant in Germany (former East Germany) - VVER-440 reactors; - V1 Nuclear Power Plant in Slovakia - VVER-440 reactors; - A1 Nuclear Power Plant in Slovakia - Heavy Water Gas Cooled Reactor; shutdown after accident. The panel speakers listed the skilled and experienced representatives from all above mentioned countries and from Russian Federation where many decommissioning projects are ongoing or under preparation. The region of Eastern and Central Europe has actually become very important in the field of decommissioning and the lessons learned from the performed projects could make a significant base for decommissioning projects worldwide.

  12. Decommissioning of the Iraq former nuclear complex

    International Nuclear Information System (INIS)

    Available in abstract form only. Full text of publication follows: A number of sites in Iraq have some degree of radiological contamination and require decommissioning and remediation in order to ensure radiological safety. Many of these sites in Iraq are located at the nuclear research centre at Al Tuwaitha. The International Atomic Energy Agency (IAEA) Board of Governors has approved a project to assist the Government of Iraq in the evaluation and decommissioning of former facilities that used radioactive materials. The project is divided into three phases: Phase 1: collect and analyze all available data and conduct training of the Iraqi staff, Phase 2: develop a decommissioning and remediation plan, and Phase 3: implement field activities relating to decommissioning, remediation and site selection suitable for final disposal of waste. Four working groups have been established to complete the Phase 1 work and significant progress has been made in drafting a new nuclear law which will provide the legal basis for the licensing of the decommissioning of the former nuclear complex. Work is also underway to collect and analysis existing date, to prioritize future activities and to develop a waste management strategy. This will be a long-term and costly project. (authors)

  13. Decommissioning and radioactive waste management. The European Commission overview

    International Nuclear Information System (INIS)

    In this lecture author deals with the European Commission overview on the decommissioning and radioactive waste management. Financial support of European Commission of decommissioning of the Ignalina NPP, Bohunice V1 NPP and Kozloduy Units 1 and 2 is presented.

  14. Technical and cost aspects of radioactive wastes from decommissioning

    International Nuclear Information System (INIS)

    The OECD Nuclear Energy Agency's Co-operative Programme on Decommissioning was established in 1985 to share the experience and information emerging from on-going decommissioning projects within member countries. The main aim of the programme is to gather and collate such data, which can then provide the basis for planning the future industrial phase of decommissioning of commercial nuclear plants. Starting with 10 decommissioning projects in 1985, today the programme has 35 participating projects from 12 countries. Apart from exchanging valuable information, task groups have been set up for in-depth analysis and studies of areas of common interest, among which are the recycling of material from decommissioning projects and decommissioning costs. This paper will describe the structure and mode of operation of the programme. Some of the results of the work in the task groups will be presented, with particular emphasis on the management of materials from decommissioning and on decommissioning costs. (author)

  15. Treatment of mine-water from decommissioning uranium mines

    International Nuclear Information System (INIS)

    Treatment methods for mine-water from decommissioning uranium mines are introduced and classified. The suggestions on optimal treatment methods are presented as a matter of experience with decommissioned Chenzhou Uranium Mine

  16. Decommissioning of research nuclear reactor WWR-S Bucharest. Analysis, justification and selection of decommissioning strategy

    International Nuclear Information System (INIS)

    The decommissioning of Research Nuclear Reactor WWR-S Bucharest involves the removal of the radioactive and hazardous materials to enable the facility to be released and not represent a further risk to human health and the environment. The National Institute of Physics and Nuclear Engineering has overall responsibilities in decommissioning including actions of contractors, submit a decommissioning plan to the regulatory body for approval and no decommissioning activities shall begin without the appropriate approval of the regulatory body. A very important aspect of decommissioning is analysis, justification and selection of decommissioning strategy. There are three strategies: Immediate Dismantling, Safe Enclosure, and Entombment. These strategies have been analyzed taking into account: - Future use of site and facilities; - Infrastructure of the specific site and facilities; - Waste storage and disposal options; - Financial aspects; - Geographical Location; - National, Local and International Legislation; - Facility characterization; Identification of decommissioning objectives; - Description of alternatives: scope, features, specific end points, release criteria, risks and safety issues, effectiveness, feasibility, nature and amount of waste of generated and disposal plans, material recycling/reusing opportunities, cost, schedule, comparative analysis; - Rationale for selecting the preferred alternative. (authors)

  17. Eastern and Central Europe Decommissioning, ECED 2015 - Book of Abstracts

    International Nuclear Information System (INIS)

    Scientific conference deals with problems of reactor decommissioning and radioactive waste management in the Central Europe. The Conference included the following sessions: (1): Characterisation and Radioactive Waste Management; (2) Managerial Aspects of Decommissioning; (3) JAVYS Experience with Back-End of Nuclear Power Engineering - Progress in Last 2 Years; (4) Decommissioning Planning and Costing and Education; (5) Technical Aspects of Decommissioning; (6) Radioactive Waste Management; (4) Poster Session. The Book of Abstracts contains two invitation speeches and 30 abstracts.

  18.  Heavy Lift Methods in Decommissioning of Installations

    OpenAIRE

    Breidablikk, Line Småge

    2010-01-01

     In this report decommissioning of offshore petroleum platforms have been investigated. It treats decommissioning in general, the process of a typical project. A variety of suitable lifting vessels have been presented, and some concepts of removal have been evaluated.

    Decommissioning is important to go through with because of the environment and the use of the area after the petroleum activities ceases. Other ocean users benefit from the decommissioning because the area can ...

  19. The Importance of Decommissioning Planning for African Countries

    International Nuclear Information System (INIS)

    Many countries in Africa have facilities that will require eventual decommissioning. If the entire life cycle of a nuclear facility is considered, decommissioning is just the last activity. The IAEA has published a number of documents that can be used during the decommissioning process, from initial planning to final release of the site. These documents are discussed briefly in this paper and further discussion is provided that will explain why planning for decommissioning should start now.

  20. Decommissioning three nuclear reactors at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Three nuclear reactors, including the historic water boiler reactor, were decommissioned at Los Alamos National Laboratory (LANL). The decommissioning of the facilities involved removing the reactors and their associated components. Planning for the decommissioning operation included characterizing the facilities, estimating the costs of decommissioning operations, preparing environmental documentation, establishing systems to track costs and work progress, and preplanning to correct health and safety concerns in each facility

  1. Colloquium on the decommissioning of the NS Otto Hahn

    International Nuclear Information System (INIS)

    After successful conclusion of the decommissioning of NS Otto Hahn during the summer of 1982 a specialists meeting was organized by GKSS-Forschungszentrum Geesthacht GmbH in order to give information about planning, procedures used and experience resulting from the decommissioning process. The state-of-the-art decommissioning techniques as used for this first German nuclear powered merchant ship are shown by experts from licensing authorities, the decommissioning company and the ship operator. (orig./HP)

  2. Researches Regarding the Results of the Fattening and the Quality of the Crossbreeds, Between the Aberdeen Angus and the F1 Crossbreeds

    Directory of Open Access Journals (Sweden)

    radu moldovan

    2013-10-01

    Full Text Available In the present paper has been kept track of the capacities of crossbreeding local breeds, to increase the beef production, which can assure the improvement of the carcass quality, according to the EU standards, as well as knowing the possibilities to enhance the production value of the beef obtained by crossbreeding, according to the EU standards and ragulations. The biological material that has been studied, is represented by a 22 young cattle, obtained from the crossbreeding of Aberdeen Angus with F1 crossbred cows, resulting from local breeds, that were crossbred with Aberdeen Angus and raised in the S.C. Aberdeen Angus farm. By analysing the average values regarding the weight of the crossbreeds at the age of 14 months, we can establish, that most of the individuals have exceeded 600 kg, some of them even 700 kg, with an average daily weight of 1478 g. Overall, the crossbreeds Aberdeen Angus X F1, have beef production qualities, that are oprimally correlated, developing remarkable quantitative and qualitative abilities.

  3. Intelligence, Social Class of Origin, Childhood Behavior Disturbance and Education as Predictors of Status Attainment in Midlife in Men: The Aberdeen Children of the 1950s Study

    Science.gov (United States)

    von Stumm, Sophie; Macintyre, Sally; Batty, David G.; Clark, Heather; Deary, Ian J.

    2010-01-01

    In a birth cohort of 6281 men from Aberdeen, Scotland, social class of origin, childhood intelligence, childhood behavior disturbance and education were examined as predictors of status attainment in midlife (46 to 51 years). Social class of origin, intelligence and behavior disturbance were conceptualized as correlated predictors, whose effects…

  4. Detritiation studies for JET decommissioning

    International Nuclear Information System (INIS)

    JET is the world largest tokamak and has the capacity of operating with a tritium plasma. Three experimental campaigns, the Preliminary Tritium Experiment (0.1g T2) in 1991, the Trace Tritium Experiment (5g T2) in 2005, and the large experiment, the Deuterium-Tritium Experiment (DTE1) (100g T2) in 1997, were carried out at JET with tritium plasmas. In DTE1 about 35 grams of tritium were fed directly into the vacuum vessel, with about 30% of this tritium being retained inside the vessel. In several years time JET will cease experimental operations and enter a decommissioning phase. In preparation for this the United Kingdom Atomic Energy Authority, the JET Operator, has been carrying out studies of various detritiation techniques. The materials which have been the subject of these studies include solid materials, such as various metals (Inconel 600 and 625, stainless steel 316L, beryllium, ''oxygen-free'' copper, aluminium bronze), carbon fibre composite tiles, ''carbon'' flakes and dust present in the vacuum vessel and also soft housekeeping materials. Liquid materials include organic liquids, such as vacuum oils and scintillation cocktails, and water. Detritiation of gas streams was also investigated. The purpose of the studies was to select and experimentally prove primary and auxiliary technologies for in-situ detritiation of in-vessel components and ex-situ detritiation of components removed from the vessel. The targets of ex-vessel detritiation were a reduction of the tritium inventory in and the rate of tritium out-gassing from the materials, and conversion, if possible, of intermediate level waste to low level waste and a reduction in volume of waste for disposal. The results of experimental trials and their potential application are presented. (orig.)

  5. Fertility traits in spring-calving Aberdeen Angus cattle. 1. Model development and genetic parameters.

    Science.gov (United States)

    Urioste, J I; Misztal, I; Bertrand, J K

    2007-11-01

    Calving records (n = 6,763) obtained from first, second, and third parities of 3,442 spring-calving, Uruguayan Aberdeen Angus cows were used to estimate heritabilities and genetic correlations for the linear trait calving day (CD) and the binary trait calving success (CS), using models that considered CD and CS at 3 calving opportunities as separate traits. Three approaches were defined to handle the CD observations on animals that failed to calve: 1) the cows were assigned a penalty value of 21 d beyond the last observed CD record within contemporary group (PEN); 2) the censored CD values were randomly obtained from a truncated normal distribution (CEN); and 3) the CD records were treated as missing, and the parameters were estimated in a joint threshold-linear analysis including CS traits (TLMISS). The models included the effects of contemporary group (herd x year of calving x mating management), age at calving (3 levels), physiological status at mating (nonlactating or lactating), animal additive genetic effects, and residual. Estimates of heritability for CD traits in the PEN and CEN data sets ranged from 0.20 to 0.31, with greater values in the first calving opportunity. Genetic correlations were positive and medium to high in magnitude, 0.57 to 0.59 in the PEN data set and 0.38 to 0.91 in the CEN data set. In the TLMISS data set, heritabilities ranged from 0.19 to 0.23 for CD and 0.37 to 0.42 for CS. Genetic correlations between CD traits varied between 0.82 and 0.88; between CS traits, genetic correlations varied between 0.56 and 0.80. Negative (genetically favorable), medium to high genetic correlations (-0.54 to -0.91) were estimated between CD and CS traits, suggesting that CD could be used as an indicator trait for CS. Data recording must improve in quality for practical applications in genetic evaluation for fertility traits. PMID:17504968

  6. Desempenho em confinamento de machos bovinos inteiros Canchim, Aberdeen angus e cruzamentos recíprocos

    Directory of Open Access Journals (Sweden)

    Perotto Daniel

    2002-01-01

    Full Text Available Foram analisados o consumo diário de matéria seca (MS por 100kg de peso vivo (CMS, a conversão alimentar (CA e o ganho de peso médio diário (GMD de 118 machos bovinos inteiros Canchim (Cn, Aberdeen Angus (Ab e cruzamentos recíprocos (CnAb (F1, 3/4Cn+1/4Ab, 5/8Cn+3/8Ab e 11/16Cn+5/16Ab e AbCn (F1, 5/8Ab+3/8Cn e 11/16Ab+5/16Cn. Esses animais foram alimentados em baias individuais por 84 a 95 dias com silagem de milho à vontade mais concentrado (17,8% de PB e 79% de NDT fornecido à base de 1% do peso vivo do animal por dia. As características foram analisadas por um modelo que incluiu os efeitos fixos de ano do confinamento, grupo genético, período e ano x período e o efeito aleatório de animal dentro de grupo genético dentro de ano. A relação MS do concentrado:MS da silagem foi incluída como co-variável no modelo. Posteriormente, as características foram analisadas por um modelo de regressão que incluiu coeficientes representando as frações esperadas de Ab nos genótipos dos animais e das mães e as heterozigoses individual e materna. As médias para CMS, CA e GMD foram 2,44kg de MS/100kg de PV/dia, 6,97kg de MS/kg de GMD e 1,435kg/dia, respectivamente. O grupo genético influenciou o CMS (P<0,01 e o GMD (P<0,06. O Ab igualou-se ao AbCn apresentando maior CMS e menor GMD que o Cn e o CnAb. Não houve heterose para qualquer das características indicando que o cruzamento alternado Cn x Ab seria igual à média das raças paternas.

  7. Fertility traits in spring-calving Aberdeen Angus cattle. 2. Model comparison.

    Science.gov (United States)

    Urioste, J I; Misztal, I; Bertrand, J K

    2007-11-01

    The aim of this study was to investigate the possible superiority of a threshold-linear (TL) approach for calving day (CD) and calving success (CS) analysis in beef cattle over 2 multiple-trait (MT), censored models, considering CD at the first 3 calving opportunities. The CD observations on animals that failed to calve in the latter models were defined as cows being assigned a penalty value of 21 d beyond the last observed CD record within contemporary group (PEN model) or censored CD values that were randomly obtained from a truncated normal distribution (CEN-model). In the TL model, CD records were treated as missing if a cow failed to calve, and parameters were estimated in a TL analysis including CS traits (TLMISS-model). The models included the effects of contemporary group (herd x year of calving x mating management), age at calving, physiological status at mating (lactating or nonlactating cow), animal additive genetic effects, and residual. Field data included 6,763 calving records obtained from first, second, and third parities of 3,442 spring-calving Uruguayan Aberdeen Angus cows. Models were contrasted using a data splitting technique, analyzing correlations between predicted breeding values (PBV) for each pair of subsamples, by rank correlations between PBV obtained with the different models, and by inspecting percentage of sires selected in common using the different approaches at 10 and 25% hypothetical percentages of animals selected. Breeding value correlations of CD between the subsamples for the TLMISS approach were greater (0.67 to 0.68) than correlations for the censored MT models (0.49 to 0.54). Average correlations between PBV of CD in 1 subsample obtained by CEN (PEN, TLMISS) and PBV of CS in the other subsample were -0.53 (-0.55, -0.60) in the first calving opportunity (CO), -0.54 (-0.58, -0.63) in the second CO, and -0.50 (-0.49, -0.58) in the third CO. Rank correlations between PBV for CD in PEN and CEN were high (0.93 to 0.97), but correlations of either method with PBV of CD in TLMISS ranged from 0.50 to 0.71. Common identification of bulls for the top 10% of sires (25% of sires), when selected with PEN/CEN models or the TLMISS model, varied between 50 (44%) and 60 (52%). The use of the TL animal model for genetic evaluation seems attractive for genetic evaluation of fertility traits in beef cattle. PMID:17686900

  8. Research nuclear installations: planning for decommissioning

    International Nuclear Information System (INIS)

    A large variety of the research nuclear installations (RNI) makes it difficult to develop unified technical solutions for their decommissioning. The analysis of domestic and foreign experience allows to draw a conclusion on possibility of development of the general approaches and methodical recommendations about planning of these works. The basis for program developing is the input information specific to every installation: data on equipment that is to be dismantled, systems of infrastructural support to RNI operations, site, accumulated radioactive wastes, radiation situation and etc. The key to success of the program is development of a general strategy for RNI decommissioning which consists in a choice of option of the final RNI site state and the ways of its achievement, as well as the corresponding general sequence and main work stages. The planning of decommissioning must include risk assessment and development of corresponding counter-measures

  9. The Ministry of Dilemmas [decommissioning nuclear submarines

    International Nuclear Information System (INIS)

    A consultant for Greenpeace, the anti-nuclear campaigners, looks at the United Kingdom Government's problems with decommissioning of its nuclear submarine fleet as the vessels become obsolete, and at the transport and storage of spent fuels from the submarine's propulsion reactors. It is argued that no proper plans exist to decommission the vessels safely. The Ministry of Defence sites such as Rosyth and Devonport are immune from inspection by regulatory bodies, so there is no public knowledge of any potential radioactive hazards from the stored out-of-service carcasses, floating in dock, awaiting more active strategies. The author questions the wisdom of building new nuclear submarines, when no proper program exists to decommission existing vessels and their operational waste. (U.K.)

  10. Site Decommissioning Management Plan. Supplement 1

    International Nuclear Information System (INIS)

    The Nuclear Regulatory Commission (NRC) staff has identified 51 sites contaminated with radioactive material that require special attention to ensure timely decommissioning. While none of these sites represent an immediate threat to public health and safety, they have contamination that exceeds existing NRC criteria for unrestricted use. All of these sites require some degree of remediation, and several involve regulatory issues that must be addressed by the Commission before they can be released for unrestricted use and the applicable licenses terminated. This report contains the NRC stairs strategy for addressing the technical, legal, and policy issues affecting the timely decommissioning of the 51 sites and describes the status of decommissioning activities at the sites. This is supplement number one to NUREG-1444, which was published in October 1993

  11. Decommissioning trust funds ordered by PSC

    International Nuclear Information System (INIS)

    The Wisconsin public service commission ordered four electric utilities to set up external trust funds for decommissioning expenses instead of collecting the money from its ratepayers to offset current borrowing needs. The change is to assure that funds will be available when they are needed for the Point Beach 1 and 2 and the Kewaunee plants, which are due for relicensing and possible decommissioning in 2007 and 2008. The external fund will be available at a time when ratepayers will likely be paying for replacement power plants. Critics claim the order will cost utility customers $800 million over the next 23 years, and note that Wisconsin Electric Power Co. has a reputation for financial health. One area of concern is the treatment of funds already collected for decommissioning

  12. The economics and financing of decommissioning

    International Nuclear Information System (INIS)

    Economics and financing have the most immediate interest to the public. Largely this interest stems from the effect of decommissioning on current utility rates, but there are other related issues as well. These include the question of whether adequate funds will be available when needed, how they will be collected and invested, and what constitute reasonable contingency factors and discount rates. Preliminary examination of the economics of decommissioning raises more questions than it answers. Each country or area of a country (as in the USA) will be faced with establishing its own policies. Whichever methods and logic are finally applied to the economics of decommissioning in the United Kingdom, the public will eventually pay. For this reason, a clear working knowledge of the principal elements of this consideration is important. (author)

  13. Decommissioning of the Loviisa power plant

    International Nuclear Information System (INIS)

    In accordance with the provisions laid in the decision of the Ministry for Trade and Industry Imatran Voima Oy has revised the decommissioning plan for the Loviisa power plant, and submitted it to the authorities for review in December 1993. The plan outlines the technical measures needed to dismantle the radioactive parts of the Loviisa power plant, explains how the resulting waste will be packed and disposed of, and estimates how many people will be needed for the decommissioning waste will be. A general timetable and a cost estimate have also been drawn up on the basis of a detailed working plan. In this report the plan has been revised for cost estimate, activity inventory of the decommissioning waste and radiation dose caused by dismantling work. (orig.). (11 refs., 10 figs., 8 tabs.)

  14. Platform decommissioning: Socio-economic impacts

    Energy Technology Data Exchange (ETDEWEB)

    Scheelhaase, Janina D.

    1998-12-01

    The object of this presentation is to evaluate the socio-economic effects of the decommissioning of steel jacket platforms in the North Sea and in the North East Atlantic in the period up to 2020 in their entirety. It is focused on two different decommissioning options, namely total and partial removal of installations. Partial removal applies only to installations in water deeper than 75 meters. All other installations, i.e those in waters shallower than 75 meters, have to be totally removed and brought onshore for disposal. Areas being analyzed cover costs of different decommissioning options, effects of the different options on employment, fiscal aspects of the different options, and aspects of recycling onshore. 6 figs., 13 tabs.

  15. Reactor decommissioning in a deregulated market

    International Nuclear Information System (INIS)

    This paper seeks to summarise BNFL's experience with regard to recent developments in reactor decommissioning and demonstrate how commercial projects in crucial areas of strategy development, project implementation and site restoration are beginning to reduce the risks and uncertainties associated with this important aspect of the nuclear power generation industry. Although the reactor decommissioning market cannot yet be regarded as mature, the key elements of strategy development, waste treatment, dismantling and delicensing have been separately demonstrated as achievable. Together with the implementation of the right organisation, and the developing technology, the risks are being reduced. As more decommissioning projects are delivered, the risks will be reduced further and the confidence of the regulator in the process will improve. This paper sets out to demonstrate this viewpoint. (author)

  16. Decommissioning of a university research reactor.

    Science.gov (United States)

    Abelquist, E W; Huda, A; State, S; Takahashi, J

    1994-07-01

    The objective of the UCLA Boelter Reactor Decommissioning Project was the release of the Boelter reactor facility for unrestricted use. The facility included a 100 kW Argonaut type research reactor that operated from 1963 to 1985, providing general reactor research. The decommissioning was planned as a two-phase program. Phase I involved removal of the reactor core structure for better access and assessment of the biological shield. Phase II decommissioning activities included structural steel removal, activated concrete removal, process equipment pit piping dismantlement, and clean concrete removal. The final release survey of the Boelter reactor facility demonstrated that all areas satisfied the project's release criteria. The total person-Sv for the project was 3.87 x 10(-2) (3.87 person-rem), most of which was received during the structural steel and activated concrete removal tasks and the disassembly of the reactor core. PMID:8200806

  17. Decommissioning of an old teletherapy cobalt machine

    International Nuclear Information System (INIS)

    The first teletherapy cobalt machine in Albania (Tirana University Hospital Center 'Mother Teresa') began operation in 1966. This was a Jupiter-Junior F machine (Monza, Italy) with a 120 TBq (3000 Ci) cobalt source. The machine worked for 28 years and the source was replaced every 5 years. The decommissioning of the machine was decided as result of its mechanical parts deteriorating. An agreement has been the reached between Albanian Government and IAEA for this decommissioning. Local and foreign specialists have participated in the decommissioning process. The source with an activity about 60 TBq was sent abroad for interim storage and the mechanical parts of the machine were controlled carefully because of their eventual radioactive contamination. (author)

  18. Narbalek uranium mine: from EIS to decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Waggitt, P.W. [Environment Australia, Office of the Supervising Scientist, Darwin, Northern Terrritory (Australia)

    2000-07-01

    The Nabarlek uranium mine operated in Northern Australia from 1979 until 1989 and was the first of the 'new generation' of uranium mines to go through the cycle of EIS, operation and decommissioning. The paper describes the environmental and operational approval processes, the regulatory regime and the decommissioning procedures at the mine. The mine was located on land owned by indigenous Aboriginal people and so there were serious cultural considerations to be taken into account throughout the mine's life. Site work for decommissioning and rehabilitation was completed in 1995 but revegetation assessment has continued until the present time (1999). The paper concludes with the latest assessment and monitoring data and discusses the lessons learned by all parties from the completion of the cycle of mine life 'from cradle to grave'. (author)

  19. Mound's decommissioning experience, tooling, and techniques

    International Nuclear Information System (INIS)

    Monsanto Research Corporation (MRC), which operates Mound for the Department of Energy (DOE), has been decommissioning radioactively contaminated facilities since 1949. We are currently decommissioning three plutonium-238 contaminated facilities (approximately 50,000 ft2) that contained 1100 linear ft of gloveboxes; 900 linear ft of conveyor housing; 2650 linear ft of dual underground liquid waste lines; and associated contaminated piping, services, equipment, structures, and soil. As of June 1982, over 29,000 Ci of plutonium-238 have been removed in waste and scrap residues. As a result of the current and previous decommissioning projects, valuable experience has been gained in tooling and techniques. Special techniques have been developed in planning, exposure control, contamination control, equipment removal, structural decontamination, and waste packaging

  20. Decommissioning of DR 2. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Strufe, N.

    2009-02-15

    This report describes the work of dismantling and demolishing reactor DR 2, the waste volumes generated, the health physical conditions and the clearance procedures used for removed elements and waste. Since the ultimate goal for the decommissioning project was not clearance of the building, but downgrading the radiological classification of the building with a view to converting it to further nuclear use, this report documents how the lower classification was achieved and the known occurrence of remaining activity. The report emphasises some of the deliberations made and describes the lessons learned through this decommissioning project. The report also intends to contribute towards the technical basis and experience basis for further decommissioning of the nuclear facilities in Denmark. (au)

  1. Nuclear data requirements for fission reactor decommissioning

    International Nuclear Information System (INIS)

    The meeting was attended by 13 participants from 8 Member States and 2 International Organizations who reviewed the status of the nuclear data libraries and computer codes used to calculate the radioactive inventory in the reactor unit components for the decommissioning purposes. Nuclides and nuclear reactions important for determination of the radiation fields during decommissioning and for the final disposal of radioactive waste from the decommissioned units were identified. Accuracy requirements for the relevant nuclear data were considered. The present publication contains the text of the reports by the participants and their recommendations to the Nuclear Data Section of the IAEA. A separate abstract was prepared for each of these reports. Refs, figs and tabs

  2. Narbalek uranium mine: from EIS to decommissioning

    International Nuclear Information System (INIS)

    The Nabarlek uranium mine operated in Northern Australia from 1979 until 1989 and was the first of the 'new generation' of uranium mines to go through the cycle of EIS, operation and decommissioning. The paper describes the environmental and operational approval processes, the regulatory regime and the decommissioning procedures at the mine. The mine was located on land owned by indigenous Aboriginal people and so there were serious cultural considerations to be taken into account throughout the mine's life. Site work for decommissioning and rehabilitation was completed in 1995 but revegetation assessment has continued until the present time (1999). The paper concludes with the latest assessment and monitoring data and discusses the lessons learned by all parties from the completion of the cycle of mine life 'from cradle to grave'. (author)

  3. Platform decommissioning: Socio-economic impacts

    International Nuclear Information System (INIS)

    The object of this presentation is to evaluate the socio-economic effects of the decommissioning of steel jacket platforms in the North Sea and in the North East Atlantic in the period up to 2020 in their entirety. It is focused on two different decommissioning options, namely total and partial removal of installations. Partial removal applies only to installations in water deeper than 75 meters. All other installations, i.e those in waters shallower than 75 meters, have to be totally removed and brought onshore for disposal. Areas being analyzed cover costs of different decommissioning options, effects of the different options on employment, fiscal aspects of the different options, and aspects of recycling onshore. 6 figs., 13 tabs

  4. Decommissioning of DR 2. Final report

    International Nuclear Information System (INIS)

    This report describes the work of dismantling and demolishing reactor DR 2, the waste volumes generated, the health physical conditions and the clearance procedures used for removed elements and waste. Since the ultimate goal for the decommissioning project was not clearance of the building, but downgrading the radiological classification of the building with a view to converting it to further nuclear use, this report documents how the lower classification was achieved and the known occurrence of remaining activity. The report emphasises some of the deliberations made and describes the lessons learned through this decommissioning project. The report also intends to contribute towards the technical basis and experience basis for further decommissioning of the nuclear facilities in Denmark. (au)

  5. The total decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    The following nuclear facilities in the Federal Republic of Germany are now ready for total decommissioning: the power plant Niederaichbach (KK00, the nuclear ship 'Otto Hahn' and the research reactor FR2. Planning work on KKN commenced in 1979 and the approval was begun in early 1980 when the approval contract was submitted. At the beginning of 1980 the contract for decommissioning the nuclear facilities on the 'Otto Hahn' was awarded. Approval was received in December 1980 and work was begun on decommissioning the plant. FR2 is still in operation and will be shut down at the end of 1980. The planning and the methods which are intended to be used for the three plants are described. (orig.)

  6. Decommissioning of reactor facilities (2). Required technology

    International Nuclear Information System (INIS)

    Decommissioning of reactor facilities was planned to perform progressive dismantling, decontamination and radioactive waste disposal with combination of required technology in a safe and economic way. This article outlined required technology for decommissioning as follows: (1) evaluation of kinds and amounts of residual radioactivity of reactor facilities with calculation and measurement, (2) decontamination technology of metal components and concrete structures so as to reduce worker's exposure and production of radioactive wastes during dismantling, (3) dismantling technology of metal components and concrete structures such as plasma arc cutting, band saw cutting and controlled demolition with mostly remote control operation, (3) radioactive waste disposal for volume reduction and reuse, and (4) project management of decommissioning for safe and rational work to secure reduction of worker's exposure and prevent the spreading of contamination. (T. Tanaka)

  7. Technical and legal aspects of the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Many of the plants licensed at the start of nuclear power programmes will require decommissioning in the 1990's and this issue should now be confronted by the nuclear industry, its regulators and governments. This paper deals with the United States programme and experience in the decommissioning of nuclear installations and describes alternative decommissioning methods including safety and financial aspects. (NEA)

  8. Waste from decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    This report is based on the assumption that all twelve nuclear power plants will be shut down no later than A.D. 2010, as was decided by the parliament after the referendum on the future of nuclear power in Sweden. The recent 'Party agreement on the energy policy' of January 15, 1991 does, indeed, leave the door open for an extension of the operational period for the nuclear reactors. This will, however, not change the recommendations and conclusions drawn in this report. The report consists of two parts. Part 1 discusses classification of waste from decommissioning and makes comparisons with the waste arising from reactor operation. Part 2 discusses the documentation required for decommissioning waste. Also this part of the report draws parallels with the documentation required by the authorities for the radioactive waste arising from operation of the nuclear power plants. To some extent these subjects depend on the future use of the nuclear power plant sites after decommissioning of the plants. The options for future site use are briefly discussed in an appendix to the report. There are many similarities between the waste from reactor operations and the waste arising from dismantling and removal of decommissioned nuclear power plants. Hence it seems natural to apply the same criteria and recommendations to decommissioning waste as those presently applicable to reactor waste. This is certainly true also with respect to documentation, and it is strongly recommended that the documentation requirements on decommissioning waste are made identical, or at least similar, to the documentation requirements for reactor waste in force today. (au)

  9. Decommissioning of a Rare Earths Extraction Facility

    International Nuclear Information System (INIS)

    The occupational and environmental radiation exposures and radiation safety issues associated with the decommissioning of a rare earths and thorium extraction facility are presented. This plant was in continuous operation during the period 1952-1988, chemically processing monazite for the separation of rare earths and thorium. It was decommissioned over a nine month period during the early 1990s. Operations at the plant over the years had resulted in buildup of activity on equipment surfaces, floors, pipes, walls and associated structures. The reaction tanks had accumulated elevated levels of activity as a result of impregnation of radionuclides into the rubber linings and pitting of surfaces due to chemical corrosion. Gamma exposure levels, airborne radioactivity and concentration of radionuclides in sludge and wastes for disposal are presented. The sequence of systematic decommissioning operations is outlined. The solid, liquid and gaseous effluents generated are characterized and quantified. Personal radiation exposures for the decommissioning and waste disposal operations are estimated. Novel methods of decontamination and recycling of large metallic objects and building surfaces are presented as a means of optimizing the quantity of waste as well as radiation exposures. The total effective doses received by the workers from external and internal exposures over the duration of the decommissioning operations were assessed to be in the range of 0.20-8.94 mSv, with a mean value of 7.2 mSv. After completion of the decommissioning operations, the groundwater was monitored for a number of years to check for contamination from the waste disposal sites. The 228Ra concentrations in the groundwater were very low. (author)

  10. Decommissioning of the Olkiluoto nuclear power plant

    International Nuclear Information System (INIS)

    A conceptual plan is presented for the decommissioning of the Olkiluoto nuclear power plant. Deferred dismantlement after a storage period of 30 years is the main alternative. No detailed work plan for the demolition of structures is included. However, the world-wide development of demolition techniques for nuclear facilities has proven that the task can be performed using the existing technology. The decommissioning waste will be packed into concrete containers and wooden boxes. The total package volume is estimated at 8.000 and 30.000 m3 depending on the treatment method. The higher figure stands for packing without any volume reduction. The activated reactor core components (fuel channels, control rods, neutron flux detectors) from the operational time of the Olkiluoto power plant are included in the decommissioning plan. The total activity of the contaminated and activated structures to be dismantled will be about 1x1016 Bq after 30 years from the shut-down. The corresponding figure for the activated core components will be about 2x1016 Bq. The radiation doses to personnel can be kept very low if the surface contamination of the large systems remains at a low level as it has done so far. The decommissioning waste is planned to be disposed of at the Olkiluoto site next to the reactor waste repository in the granitic bedrock at a depth of 50-100 m. The decommissioning waste repository will consist of two silos for the low-level waste and a hall for the activated metal waste. The barriers in the case of the metal waste hall will consist of the waste packages themselves, of 0.75 and 1 m thick concrete walls, of the 1 m thick bentonite/crushed rock backfill, and of the bedrock. The dismantlement will be finished by the year 2050, and the repository can be closed and sealed by 2055. The estimated decommissioning cost is FIM 808 million including the long-term storage and disposal

  11. Decision framework for platform decommissioning in California.

    Science.gov (United States)

    Bernstein, Brock B

    2015-10-01

    This article describes the overall decision framework for eventual decisions about decommissioning the 27 operating oil and gas platforms offshore southern California. These platforms will eventually reach the end of their useful lifetimes (estimated between 2015 and 2030, although specific dates have not been determined). Current law and regulations allow for alternative uses in lieu of the complete removal required in existing leases. To prepare for eventual decommissioning, the California Natural Resources Agency initiated an in-depth process to identify and investigate issues surrounding possible decommissioning alternatives. The detailed evaluation of alternatives focused on 2-complete removal and artificial reefing that included partial removal to 85 feet below the waterline. These were selected after a comparison of the technical and economic feasibility of several potential alternatives, availability of a legal framework for implementation, degree of interest from proponents, and relative acceptance by state and federal decision makers. Despite California's history of offshore oil and gas production, only 7 decommissioning projects have been completed and these were all relatively small and close to shore. In contrast, nearly 30% of the California platforms are in water depths (as much as 1200 feet) that exceed any decommissioning project anywhere in the world. Most earlier projects considered an artificial reefing alternative but none were implemented and all platforms were completely removed. Future decisions about decommissioning must grapple with a more complex decision context involving greater technological and logistical challenges and cost, a wider range of viable options, tradeoffs among environmental impacts and benefits, and an intricate maze of laws, regulations, and authorities. The specific engineering differences between complete and partial removal provide an explicit basis for a thorough evaluation of their respective impacts. PMID:26259879

  12. Nuclear power plants. Safe and efficient decommissioning

    International Nuclear Information System (INIS)

    The process of dismantling a nuclear power plant consists of several phases that involve significant challenges along the way for authorities, operators, and suppliers. It is necessary to ensure safety at all times and to achieve certainty in respect of key project parameters, especially time and cost. Therefore, careful planning as well as detailed knowledge of local standards and regulations, best available techniques and practical implementation strategies are crucial. Independent expertise and knowledge service can be utilised for demanding projects worldwide. This guarantees safety for people and the environment in every phase of decommissioning. The article gives an overview on different decommissioning options and their challenges.

  13. Ignalina NPP pre-decommissioning projects

    International Nuclear Information System (INIS)

    Description of the main projects for the preparation to the decommissioning of unit 1 of Ignalina NPP is presented. These projects are to be financed by international donors as one of the conditions to shutdown unit before the year 2005. These projects were presented during Donors conference held in 21-22 June 2000 in Vilnius. The conference was organized jointly by Lithuanian Government and European Commission. Projects are devoted to the construction of radioactive waste management facilities and improvement of existing waste management practices at Ignalina NPP as well for the general management of decommissioning process preparation of necessary documentation

  14. Nuclear power plants. Safe and efficient decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Huger, Helmut [TUEV SUED Energietechnik GmbH, Filderstadt (Germany). Div. of Radiation Protection, Waste Management and Decommissioning; Woodcock, Richard [TUEV SUED Nuclear Technologies, Warrington, Cheshire (United Kingdom). Environment and Radioactive Waste Management

    2016-02-15

    The process of dismantling a nuclear power plant consists of several phases that involve significant challenges along the way for authorities, operators, and suppliers. It is necessary to ensure safety at all times and to achieve certainty in respect of key project parameters, especially time and cost. Therefore, careful planning as well as detailed knowledge of local standards and regulations, best available techniques and practical implementation strategies are crucial. Independent expertise and knowledge service can be utilised for demanding projects worldwide. This guarantees safety for people and the environment in every phase of decommissioning. The article gives an overview on different decommissioning options and their challenges.

  15. Optimization in the decommissioning of uranium tailings

    International Nuclear Information System (INIS)

    This report examines in detail the problem of choosing the optimal decommissioning approach for uranium and mill tailings sites. Various decision methods are discussed and evaluated, and their application in similar decision problems are summarized. This report includes, by means of a demonstration, a step by step guide of how a number of selected techniques can be applied to a decommissioning problem. The strengths and weaknesses of various methods are highlighted. A decision system approach is recommended for its flexibility and incorporation of many of the strengths found in other decision methods

  16. MCNP calculations in decommissioning of VVER-440

    International Nuclear Information System (INIS)

    The paper briefly describes the issue of neutron fluence and radionuclide inventory determination in components of decommissioned nuclear power plants with emphasis on VVER-440 reactor type. According to induced activity calculation, it will be possible to optimize the time frame and choose the appropriate dismantling procedure during the disposal of reactor internal and external components in the decommissioning of a nuclear power plant. Prerequisite for this calculation is the collection of reactor operation data. In this paper, abilities of MCNP5 and MCNPX codes in this field are presented. (authors)

  17. Decommissioning operations at Fort St. Vrain

    International Nuclear Information System (INIS)

    A team of Westinghouse Electric Corporation and the Morrison Knudsen-Ferguson Group initiated the Decommissioning of the Fort St. Vrain Nuclear Generating Station in August, 1992. The High Temperature Gas Cooled Reactor consists primarily of the core components, steam generators and helium circulators housed within the Prestressed Concrete Reactor Vessel. For dismantling, the Reactor Vessel has been filled with water and access to the interior region gained through the top head. The radioactive internal components are being removed using long handled underwater tooling, loaded into shielded transfer casks for packing in shipping casks and containers. Operations have proceeded to where the decommissioning is approximately 50% complete

  18. Cost Estimation for Research Reactor Decommissioning

    International Nuclear Information System (INIS)

    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 purpose of this publication is to develop a costing methodology and a software tool in order to support cost estimation for research reactor decommissioning. The costing methodology is intended for the preliminary cost estimation stages for research reactor decommissioning with limited inventory data and other input data available. Existing experience in decommissioning costing is considered. As the basis for the cost calculation structure, the costing model uses the International Structure for Decommissioning Costing (ISDC) that is recommended by the IAEA, the Organisation for Economic Co-operation and Development/Nuclear Energy Agency, and the European Commission as the general platform for decommissioning cost estimation purposes. Use of the ISDC based model facilitates the preliminary costing stages in the absence of decommissioning plans. For proper establishment of the costing case, the intended decommissioning strategy is used. The model should be flexible as to the extent and details of the inventory data. The impact of individual inventory items (working constraints) should be respected. Implementing the ISDC as the basis for the cost calculation structure ensures compatibility with the IAEA classification scheme for radioactive waste. The developed tool is intended for experts who are familiar with the facility, such as the former or actual operators of research reactors. A basic knowledge of decommissioning issues is recommended. (author)

  19. Decommissioning of the Salaspils Research Reactor

    OpenAIRE

    Abramenkovs Andris

    2011-01-01

    In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor and to dispense with nuclear energy in the future. The reactor has been out of operation since July 1998. A conceptual study on the decommissioning of the Salaspils Research Reactor was drawn up by Noell-KRC-Energie- und Umwelttechnik GmbH in 1998-1999. On October 26th, 1999, the Latvian government decided to start the direct dismantling to “green-field” in 2001. The upgrading of the decommissioning ...

  20. A Quality Assurance Program for decommissioning

    International Nuclear Information System (INIS)

    Defining the Quality Assurance Program for the US Department of Energy Shippingport Station Decommissioning Project (SSDP) was a unique opportunity because this is the first full-sized commercial nuclear power plant to be decommissioned. General Electric Company defined a Quality Assurance Program that provided adequate control, yet was stripped down to the essentials. The Program is designed to provide a flexible degree of monitoring of subcontractor work, built around a core of radiation safety monitoring, detailed planning, inspection and auditing, and operated with a minimum of dedicated personnel. This paper will concentrate on the traditional quality assurance activities, leaving radiation and environmental monitoring for other presentations

  1. Funding for reactor decommissioning: the NRC perspective

    International Nuclear Information System (INIS)

    The cost of decommissioning a nuclear power plant is discussed. Four funding approaches that have received the most attention from the NRC are: prepayment into a trust fund of estimated decommissioning funds at the start of facility operation; annual contributions into a trust fund outside the control of the utility over the estimated life of a facility; internal reserve or sinking fund amortizations over the estimated life of a facility; and insurance or other surety mechanisms used separately or in conjunction with any of the first three mechanisms

  2. The Fort St. Vrain decommissioning project

    International Nuclear Information System (INIS)

    Decommissioning of the Fort St. Vrain 330MW High Temperature Gas Cooled Reactor was completed on 5th August 1997, eight years after permanent shutdown. Early dismantling was chosen as the appropriate decommissioning option. The major stages in the process are described. They were: irradiated fuel removal and storage; removal of radioactive components; top head removal; core support floor removal; removal of reactor vessel components; decontamination of the prestressed concrete reactor vessel; radiological surveys. A high level of safety and radiological protection was achieved throughout the operation. (UK)

  3. The Fort St. Vrain decommissioning project

    Energy Technology Data Exchange (ETDEWEB)

    Fisher, M.J.

    1997-11-01

    Decommissioning of the Fort St. Vrain 330MW High Temperature Gas Cooled Reactor was completed on 5th August 1997, eight years after permanent shutdown. Early dismantling was chosen as the appropriate decommissioning option. The major stages in the process are described. They were: irradiated fuel removal and storage; removal of radioactive components; top head removal; core support floor removal; removal of reactor vessel components; decontamination of the prestressed concrete reactor vessel; radiological surveys. A high level of safety and radiological protection was achieved throughout the operation. (UK).

  4. The Morsleben radwaste repository. Preparing for decommissioning

    International Nuclear Information System (INIS)

    The publication is intended to illustrate with a brief chronology the history and the present situation of the Morsleben radwaste repository, including specific aspects such as the geology of the site and construction and engineering activities, the particulars of waste form emplacement and log-term storage conditions, topical issues relating to radiological safety during operation and after decommissioning. The brochure is designed for the general audience interested in background information on all aspects of the uses, operation and decommissioning of a radwaste repository in Germany. (orig./CB)

  5. Knowledge management during decommissioning of Chornobyl NPP

    International Nuclear Information System (INIS)

    The article deals with issues on knowledge management during decommissioning by the example of the Chornobyl NPP. This includes how the duration of decommissioning stage, change in organization goal and final state of the site influence on human resources and knowledge management system. The main attention is focused on human assets and intellectual strength of Chornobyl NPP. Mathematical dependencies are proposed to substantiate numerical values. An analysis is given for the current situation, and forecast estimates for values dynamics is performed. The conclusion gives solutions on providing experienced staff in the future.

  6. Decommissioning of a tritium-contaminated laboratory

    International Nuclear Information System (INIS)

    A tritium laboratory facility at the Los Alamos National Laboratory, Los Alamos, New Mexico, was decommissioned in 1979. The project involved dismantling the laboratory equipment and disposing of the equipment and debris at an on-site waste disposal/storage area. The laboratory was constructed in 1953 and was in service for tritium research and fabrication of lithium tritide components until 1974. The major features of the laboratory included some 25 meters of gloveboxes and hoods, associated vacuum lines, utility lines, exhaust ducts, electrodryers, blowers, and laboratory benches. This report presents details on the decommissioning, health physics, waste management, environmental surveillance, and costs for the operation

  7. Good practices in decommissioning planning and pre-decommissioning activities for the Magurele VVR-S nuclear research reactor

    OpenAIRE

    Dragusin Mitica; Pavelescu Octavian Alexandru; Iorga Ioan

    2011-01-01

    The VVR-S Nuclear Research Reactor at the “Horia Hulubei” National Institute of Physics and Nuclear Engineering in Magurele, Bucharest, will be decommissioned applying the immediate dismantling strategy. The implementation of the decommissioning project started in 2010 and is planned for completion within 11 years. Good practices in decommissioning planning, organization, funding, and logistics are described in this paper.

  8. Good practices in decommissioning planning and pre-decommissioning activities for the Magurele VVR-S nuclear research reactor

    International Nuclear Information System (INIS)

    The VVR-S Nuclear Research Reactor at the 'Horia Hulubei' National Institute of Physics and Nuclear Engineering in Magurele, Bucharest, will be decommissioned applying the immediate dismantling strategy. The implementation of the decommissioning project started in 2010 and is planned for completion within 11 years. Good practices in decommissioning planning, organization, funding, and logistics are described in this paper. (author)

  9. The institutional framework of decommissioning in Italy

    International Nuclear Information System (INIS)

    Full text: Decommissioning of the NPP is generally viewed in a negative framework. On the contrary, it is an activity which aims is said to obtain the final removal of the risk factors from the environment. It is the last step of the production cycle, whose importance is underlined by the Regulation recently issued for the correct management of resources in the territory. Decommissioning NPP involves the final arrangements of the radioactive wastes, produced either during the past operation period or resulting from the dismantling operation. All the radioactive wastes must be conditioned and maintained in safe conditions. Radioactive waste management is no longer a problem for those countries that decided to face it, that is the majority of the industrialised countries. Correct technological solutions exist, due exist, respectful of the environment, of the people, of the ethical principles. The centrality of the problem is also decreed by the fact that sometimes now, the European Commission has been working on the issue of the directive on waste management, an effort which Italy has strongly supported, also during the Presidency period. Decommissioning on NPP is moreover an activity that implies advanced technological solutions, multilateral overlapping programs, working of style situations. Not many countries have completed yet (the) decommissioning of their plants: such activity should therefore be seen as an opportunity for the growth and the assertion of the Italian industry, also in view of the potential new market and the alliance with European industries. Of the 530 nuclear reactors present in world today, approximately 100 are undergoing decommissioning. In the next 2 years another 100 will reach the end of their operative life. Probably after the necessary system improvement many of them will continue to work, but it is clear that the international market of the decommissioning will continue to grow in the next years. Italy can play an important role in this scenario: the decommissioning program produced by Sogin can therefore be a springboard for specific activities. Decommissioning of the Italian NPP will cost a total of approximately 3.5 billions euro. This amount of money will be founded by the electricity market (electricity bill): in order to optimise this huge amount, the efficiency and efficacy of the decommissioning program must be guaranteed. For this reason in 2003 the Italian government gave a significant drive for the centralisation of all the activities and responsibilities to a unique operator, also assigning Sogin with the management of the ENEA fuel cycle plants and related companies. Decommissioning program for Italian nuclear plants have been issued since 1999 and have under-gone the complex licensing procedure foreseen by a specific regulation of the sector, the law 241/2000 and by the regulation regarding the Environmental Impact Assessment. This regulatory frame is a recent one and, for some aspects, is still not completed and has, for the same reasons, sometimes caused some delay in activities. Other factors providing delays involved the excessive sensitivity of some local situation which, even though guaranteed by regulation that envisage the direct participation in decision making, see the decommissioning as a risk factor that they can't control directly. In order to proceed in completing this unpostponable operations in the most correct and effective manner, it is important that the different institutional bodies involved in the licensing procedure co-operate in the success of the program. The issue of the decree envisaged by law 230/95 constitutes a test table to this end. Working along these lines, the government has already began by signed the institutional agreement for the coordination of the licensing procedure related to the mention law 230/95 and the Environmental Impact Assessment. (author)

  10. The decommissioning and redevelopment of NECSA site

    International Nuclear Information System (INIS)

    Full text: The South African nuclear programme started in 1948 and was focussed on research and development in the nuclear field. In the early 70s a uranium conversion plant and a uranium enrichment plant were constructed on the NECSA site. The enriched uranium was used for military purposes, as fuel for the research reactor SAFARI-1 at Necsa. A semi-commercial uranium enrichment plant and a fuel manufacturing plant were commissioned in the 80's to supply fuel for the nuclear power plant at Koeberg near Cape Town. Currently the research reactor is utilized for the generation of radioactive isotopes for industrial and medical applications. Various other research projects were initiated and buildings constructed on the Necsa site to accommodate the different projects. The uranium conversion and enrichment projects were terminated in the early 90's, and many buildings on the Necsa site became redundant. An initial decommissioning strategy was to return the Necsa site to green fields. This endpoint of decommissioning has changed dramatically with the nuclear renaissance to include redevelopment and reuse options. In the case of a multi-facility nuclear site, such as the Necsa site, it is vital to develop a total site redevelopment plan rather than to decommission and allocate individual facilities for isolated reuse demands. A holistic approach should be assured by considering current and projected future redevelopment demands in the development of a redevelopment and reuse plan. It is important not to allow the redevelopment and reuse of a single facility on a multi-facility site based on short- term financial gain. With the recent increase in demand for nuclear facilities the redevelopment and reuse of nuclear facilities for non-nuclear applications should generally not be considered due to the inherent advantages associated with an existing licensed site. The initial decommissioning plan did not consider the Necsa site as a whole. Decommissioning costs, and the reuse of equipment were not optimised and the uncoordinated redevelopment and reuse lead to decommissioning to lower levels than required. A holistic approach towards redevelopment and reuse could have resulted in minimising decommissioning waste. In the past decommissioning was aimed at the final disposal of waste and the remediation of a site. This concept is currently challenged and decommissioning should not be viewed as an endpoint of a facility or site but should rather be the starting phase of a redevelopment and reuse opportunity for a facility or site. A decommissioning strategy based on the final closure of a facility or site should be a last resort and the focus should move to redevelopment and reuse options. The decommissioning of a nuclear site is usually associated with remaining liabilities, which require resources to ensure management of stored radiological waste etc. If the nuclear site is redeveloped and reused, these control measures and infrastructure could be included as part of the reuse scenario which is beneficial to the redevelopment and to liability management. (author)

  11. Needs for European decommissioning academy (EDA)

    International Nuclear Information System (INIS)

    According to analyses presented at EC meeting focused on decommissioning organized at 11.9.2012 in Brussels, it was stated that at least 500 new international experts for decommissioning will be needed in Europe up to 2025, which means about 35 per year. Having in mind the actual EHRO-N report from 2013 focused on operation of nuclear facilities and an assumption that the ratio between nuclear experts, nuclearized and nuclear aware people is comparable also for decommissioning, as well as the fact that the special study branch for decommissioning in the European countries almost does not exist, this European Decommissioning Academy (EDA) could be helpful in the over-bridging this gap. The main goal is - from about 74% of nuclearized experts (graduated at different technical Universities and increased their nuclear knowledge and skills mostly via on-job training and often in the area of NPP operation) to create nuclear experts for decommissioning via our post-gradual coursed organized in two semester study at our Academy, which will include the lessons, practical exercises in our laboratories, on-site training at NPP V-1 in Jaslovske Bohunice, Slovakia as well as 3 days technical tour to JAVYS (Slovakia), UJV Rez (Czech Rep.) and PURAM (Hungary), respectively. Beside the exams in selected topics (courses), the final thesis written under supervision of recognized experts will be the precondition for graduation and certification of the participants. For the first run of the EDA scheduled on 2014 we would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future in Europe. The growing decommissioning market creates a potential for new activities, with highly skilled jobs in an innovative field, involving high-level technologies. A clear global positioning of the EU will stimulate the export of know-how to other countries, especially those having a large nuclear programme, and promote the highest safety levels. The EU 'Community acquits' includes key legislation such as the recent Council Directive 2011/70/EURATOM establishing the Community framework for the responsible and safe management of spent fuel and radioactive waste, which sets the legal obligations for adequate funding, financial security and transparency applicable to the national waste management systems. The need to maintain and increase competent and qualified staff is a recurrent concern in the nuclear sector. In particular, in view of the growing decommissioning market, it can be expected that industry will involve new actors, including, in some cases, small and middle enterprises. The organisation of ad hoc training programs is also essential with a strong link to research and educational organisations. For Central and Eastern European countries, where several units were shut-down before the end of their operating lifetime, decommission is one of most important tasks. According to the conclusions of the conference 'Eastern and Central European Decommissioning', held in June 2013, in Trnava, Slovakia it was stated that: 1. According to common experiences from VVER decommissioning - the creation of a master approach and procedures that could be recommended for all VVER countries. NPP V-1 in Bohunice, Slovakia can be perhaps the proper place for the verification of these procedures. 2. Education, training and proper knowledge management have specific relevance for decommissioning. Based on the training courses that we run at the Slovak University of Technology we would like to create a European Academy for Decommissioning for VVER countries in collaboration with EC and IAEA. Knowledge and decommissioning skills could be shared on an international level. Input from several organisations present here at the conference would be beneficial. We recommend that specific lessons, practical exercises and on-site training shall be organised at NPP V-1 in Jaslovske Bohunice by the best European experts in this area

  12. Validation of Decommissioning Engineering System Application against KRR-2

    Energy Technology Data Exchange (ETDEWEB)

    Jin, Hyung Gon; Park, Seungkook; Park, Heeseong; Song, Chanho; Ha, Jaehyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    KAERI is the only expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR (Korea Research Reactor)-1 and 2 and UCP (Uranium Conversion Plant) decommission. This paper contains validation results of the KAERI DES by using KRR-2 decommissioning data. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DES application program. One of decommissioning experience data, KRR-2 was used for KAERI DES validation and it successfully is reflected in KAERI DES.

  13. Topical question of the Chernobyl nuclear power plant units decommissioning

    International Nuclear Information System (INIS)

    The main statements of the decommissioning conception and the results of the complex engineering and radiation inspection of the Chernobyl Nuclear Power Plant units are given. The features of the ChNPP units decommissioning are analyzed. The critical analysis of the current state of works, taken technical measures, decommissioning costs, and the present problems in view of unavailability of the necessary infrastructure for the safety units decommissioning is done. It is shown that during a long period of time the main decommissioning works has not started yet due to absence of the project of works and unavailability of the infrastructure

  14. Validation of Decommissioning Engineering System Application against KRR-2

    International Nuclear Information System (INIS)

    KAERI is the only expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR (Korea Research Reactor)-1 and 2 and UCP (Uranium Conversion Plant) decommission. This paper contains validation results of the KAERI DES by using KRR-2 decommissioning data. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DES application program. One of decommissioning experience data, KRR-2 was used for KAERI DES validation and it successfully is reflected in KAERI DES

  15. Decommissioning of the nuclear merchant ship OTTO HAHN

    International Nuclear Information System (INIS)

    With NS OTTO HAHN for the first time in the world a nuclear merchant ship and for the first time in FRG a nuclear power plant was decommissioned. Starting from the existing technical and radiological state of the plant the decommissioning concept is shown. Licensind and release procedures including the applied measuring techniques are described and the single phases of the decommissioning work are dealt with. The total masses and activities are balanced and the results of the decommissioning are discussed. With the suspension of the control area and the release of the ship the decommissioning work was finished in June 1982. (orig.)

  16. Características da carcaça de bovinos Canchim e Aberdeen Angus e de seus cruzamentos recíprocos terminados em confinamento Carcass traits of Canchim, Aberdeen Angus and reciprocal crosses finished in confinement

    OpenAIRE

    Daniel Perotto; José Luiz Moletta; Antonio Carlos Cubas

    1999-01-01

    Foram analisadas quatorze características quantitativas das carcaças de 137 machos bovinos inteiros pertencentes aos grupos Canchim (Ca), Aberdeen Angus (Ab), 3/4Ca+1/4Ab, 3/4Ab+1/4Ca, 5/8Ca+3/8Ab e 5/8Ab+3/8Ca, nascidos na Estação Experimental Fazenda Modelo, em Ponta Grossa-PR, no período de 1988 a 1993. As médias para a idade e para o peso ao início do confinamento, duração do confinamento, idade e peso ao abate foram, respectivamente, 737 dias, 356kg, 97 dias, 834 dias e 468kg. Durante o ...

  17. Decommissioning of nuclear facilities. Feasibility, needs and costs

    International Nuclear Information System (INIS)

    Reactor decommissioning activities generally are considered to begin after operations have ceased and the fuel has been removed from the reactor, although in some countries the activities may be started while the fuel is still at the reactor site. The three principal alternatives for decommissioning are described. The factors to be considered in selecting the decommissioning strategy, i.e. a stage or a combination of stages that comprise the total decommissioning programme, are reviewed. One presents a discussion of the feasibility of decommissioning techniques available for use on the larger reactors and fuel cycle facilities. The numbers and types of facilities to be decommissioned and the resultant waste volumes generated for disposal will then be projected. Finally, the costs of decommissioning these facilities, the effect of these costs on electricity generating costs, and alternative methods of financing decommissioning are discussed. The discussion of decommissioning draws on various countries' studies and experience in this area. Specific details about current activities and policies in NEA Member Countries are given in the short country specific Annexes. The nuclear facilities that are addressed in this study include reactors, fuel fabrication facilities, reprocessing facilities, associated radioactive waste storage facilities, enrichment facilities and other directly related fuel cycle support facilities. The present study focuses on the technical feasibility, needs, and costs of decommissioning the larger commercial facilities in the OECD member countries that are coming into service up to the year 2000. It is intended to inform the public and to assist in planning for the decommissioning of these facilities

  18. Current status of Tokai-1 decommissioning project

    International Nuclear Information System (INIS)

    JAPC launched Tokai-1 decommissioning in December 2001 after the submission of the notification of decommissioning plan to the government (METI). This is the first instance of the decommissioning of a commercial nuclear power plant in Japan. As the whole project is planned to take a long term of 17 years, the project program is divided into three phases. In the First Phase of 5 years, from 2001 to 2005, the underwater equipment in Cartridge Cooling Pond(CCP), Turbine Generator, Reactor Auxiliary equipment and Fuel Charge Machines are removed. In the Second Phase of 5 years, from 2006 to 2010, Steam Raising Units will be removed. The Third Phase of 7 years, from 2011 to 2017, all reactor structures, Reactor Building and miscellaneous buildings will be dismantled. The project will be completed adjusting the land to ground level. Total amount of arising wastes is 177 thousand ton. 18 thousand ton of the waste are classified as the Low Level radioactive Waste (LLW). The total cost of the Tokai-1 decommissioning project is estimated at 89 billion yen (740M$) as of year 2001, in which about 35 billion-yen (290M$) is for dismantling cost and 54 billion yen (450M$) is for radioactive waste treatment and disposal cost. (author)

  19. Decommissioning progress at Fort St. Vrain

    International Nuclear Information System (INIS)

    Decommissioning of commercial nuclear power plants in the US has initiated with the current dismantling of the Fort St. Vrain Nuclear Generation Station in Colorado. Owned and operated by Public Service Company of Colorado (PSC), the unit was permanently shutdown in 1989. After a thorough evaluation by the utility of the DECON versus SAFSTOR options, the decision was made to proceed with decommissioning the power station for unrestricted release. In 1990 a team comprised of Westinghouse Electric Corporation and Morrison Knudsen Corporation was selected by PSC to perform the decommissioning on a fixed price, turnkey basis. The Westinghouse Team (WT) concept was based on an innovative approach for dismantling the Prestressed Concrete Reactor Vessel (PCRV) by flooding it and performing most operations using underwater tooling. This approach provided the maximum shielding and contamination control along with an optimum balance of schedule, cost and ALARA with minimum risks. An overview of the decommissioning progress to date plus overall perspectives of the factors facing utilities in this area will be reviewed

  20. Offshore decommissioning issues: Deductibility and transferability

    International Nuclear Information System (INIS)

    Dealing with the decommissioning of petroleum installations is a relatively new challenge to most producer countries. It is natural to expect that industry's experience in building platforms is much greater than the one of dismantling them. Even if manifold and varied efforts are underway towards establishing international 'best practices' standards in this sector, countries still enjoy rather extensive discretionary power as they practice a particular national style in the regulation of decommissioning activities in their state's jurisdiction. The present paper offers a broad panorama of this discussion, concentrating mainly on two controversial aspects. The first one analyses the ex-ante deductibility of decommissioning costs as they constitute an ex-post expense. The second discussion refers to the assignment of decommissioning responsibility in the case of transfer of exploration and production rights to new lessees during the project's life. Finally the paper applies concepts commonly used in project financing as well as structures generally used in organising pension funds to develop insights into these discussions

  1. Spent fuel disposal impact on plant decommissioning

    International Nuclear Information System (INIS)

    Regardless of the decommissioning option selected (DECON, SAFSTOR, or ENTOMB), a 10 CFR 50 license cannot be terminated until the spent fuel is either removed from the site or stored in a separately 10 CFR 72 licensed Independent Spent Fuel Storage Installation (ISFSI). Humboldt Bay is an example of a plant which has selected the SAFSTOR option. Its spent fuel is currently in wet storage in the plant's spent fuel pool. When it completes its dormant period and proceeds with dismantlement, it will have to dispose of its fuel or license an ISFSI. Shoreham is an example of a plant which has selected the DECON option. Fuel disposal is currently critical path for license termination. In the event an ISFSI is proposed to resolve the spent fuel removal issue, whether wet or dry, utilities need to properly determine the installation, maintenance, and decommissioning costs for such a facility. In considering alternatives for spent fuel removal, it is important for a utility to properly account for ISFSI decommissioning costs. A brief discussion is presented on one method for estimating ISFSI decommissioning costs

  2. Virtual reality technology and nuclear decommissioning

    International Nuclear Information System (INIS)

    During past years, an important activity at the Halden VR Centre (HVRC), Institute for Energy Technology (IFE) in Halden has been the development of virtual reality (VR) software for use in the decommissioning of nuclear facilities. It is hoped that use of VR technology in the planning process may prove beneficial both with regard to minimizing workers' radiation exposure, as well as in helping to achieve the efficient use of human resources. VR can also be a valuable tool in the dismantling phase. In addition to this, VR provides the decommissioning project team with an effective medium in presentations to the public, as well as for communicating with relevant engineers and licensing authorities. The most extensive IFE VR decommissioning project is at present the VRdose project, conducted in co-operation with the Japan Nuclear Cycle Development Institute (JNC). VRdose will be used in the decommissioning of one of JNC's reactors, the Fugen Nuclear Power Station.The paper describes the present and planned versions of the VRdose system, but also briefly describes other related activities at HVRC. (author)

  3. The decommissioning of the water boiler reactor

    International Nuclear Information System (INIS)

    Following completion of service, the Water Boiler Reactor (WBR) has been decommissioned by the Institute of Nuclear Energy Research (INER) under the Atomic Energy Council's (AEC) regulation. The WBR is a light water moderated and graphite reflected research reactor with peak thermal power of 100 kW. The unique feature of the WBR is that it is fueled with uranyl sulfate (UO2SO4) which is in liquid form. Since there is another research reactor owned by I7NER of megawatt scale in the planning stages for decommissioning, the WBR project was conducted with great care to accumulate experience. Extensive planning by INER and step-by-step regulative activities by AEC were followed regardless of the structural simplicity of the WBR. Valuable information was gathered in the task and will be useful for preparing future decommissioning needs. The major work in the WBR decommissioning project was finished within six months and the accumulated dose received during the work was 1 9.63mSv. (author)

  4. Modelling of nuclear power plant decommissioning financing

    Czech Academy of Sciences Publication Activity Database

    Bemš, J.; Knápek, J.; Králík, T.; Hejhal, M.; Kubančák, Ján; Vašíček, J.

    Vol. 2015. Oxford : Oxford Journals, 2015, s. 1-4. ISSN 1742-3406. [8th International Conference on High Levels of Natural Radiation and Radon Areas (ICHLNRRA 2014). Prague (CZ), 01.09.2014-05.09.2014] Institutional support: RVO:61389005 Keywords : nuclear power plant * methodology * future decommissioning costs Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders

  5. MODELLING OF NUCLEAR POWER PLANT DECOMMISSIONING FINANCING

    Czech Academy of Sciences Publication Activity Database

    Bemš, J.; Knápek, J.; Králík, T.; Hejhal, M.; Kubančák, Ján; Vašíček, J.

    2015-01-01

    Roč. 164, č. 4 (2015), s. 519-522. ISSN 0144-8420 Institutional support: RVO:61389005 Keywords : nuclear power plant * methodology * future decommissioning costs Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.913, year: 2014

  6. Y-12 Plant Decontamination and Decommissioning Program

    International Nuclear Information System (INIS)

    The Decontamination and Decommissioning (D and D) Program at the Oak Ridge Y-12 Plant is part of the Environmental Restoration (ER) and Waste Management (WM) Programs (ERWM). The objective of the ER Program is to provide Y-12 the capability to meet applicable environmental regulations through facility development activities and site remedial actions. The WM Program supports the ER program. The D and D Program provides collective management of sites within the Plant which are in need of decontamination and decommissioning efforts, prioritizes those areas in terms of health, safety, and environmental concerns, and implements the appropriate level of remedial action. The D and D Program provides support to identifiable facilities which formerly served one or more of the many Plant functions. Program activities include (1) surveillance and maintenance of facilities awaiting decommissioning; (2) planning safe and orderly facility decommissioning; and (3) implementing a program to accomplish facility disposition in a safe, cost effective, and timely manner. In order to achieve the first objective, a formal plan which documents the surveillance and maintenance needs for each facility has been prepared. This report provides this documentation for the Y-12 facilities currently included in the D and D Program, as well as those planned for future inclusion in the Program, and includes projected resource requirements for the planning period of FY 1993 through FY 2000

  7. Sodium Reactor Experiment decommissioning. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Carroll, J.W.; Conners, C.C.; Harris, J.M.; Marzec, J.M.; Ureda, B.F.

    1983-08-15

    The Sodium Reactor Experiment (SRE) located at the Rockwell International Field Laboratories northwest of Los Angeles was developed to demonstrate a sodium-cooled, graphite-moderated reactor for civilian use. The reactor reached full power in May 1958 and provided 37 GWh to the Southern California Edison Company grid before it was shut down in 1967. Decommissioning of the SRE began in 1974 with the objective of removing all significant radioactivity from the site and releasing the facility for unrestricted use. Planning documentation was prepared to describe in detail the equipment and techniques development and the decommissioning work scope. A plasma-arc manipulator was developed for remotely dissecting the highly radioactive reactor vessels. Other important developments included techniques for using explosives to cut reactor vessel internal piping, clamps, and brackets; decontaminating porous concrete surfaces; and disposing of massive equipment and structures. The documentation defined the decommissioning in an SRE dismantling plan, in activity requirements for elements of the decommissioning work scope, and in detailed procedures for each major task.

  8. UK nuclear decommissioning policy: time for decision

    International Nuclear Information System (INIS)

    This report presents the results of an investigation into the current United Kingdom policy on the decommissioning of nuclear reactors. The most controversial feature of the policy is the plan to postpone the most difficult stage of decommissioning, the dismantling of the core, for over 100 years. While this policy has clear advantages to the present generation there are strong ethical arguments against such a long delay which also poses technical and economic questions. The work will be left to future generations, who will have to bear both the opportunity costs of labour and capital and some risk of radioactive contamination. Uncertainties exist over the availability of finance to complete the decommissioning so far into the future and assumptions have to be made that the relevant nuclear technology will still be available. It is suggested that a more active policy is needed to demonstrate that decommissioning can be carried out safely within expected costs and that higher priority needs to be given to the construction of safe waste repositories. (UK)

  9. 78 FR 663 - Decommissioning Planning During Operations

    Science.gov (United States)

    2013-01-04

    ... complying with the NRC's Decommissioning Planning Rule (DPR) (76 FR 35512; June 17, 2011). The DPR went into... use by holders of licenses in complying with the DPR. On December 13, 2011 (76 FR 77431), the NRC... was extended from February 10, 2012 to March 30, 2012 (77 FR 8751; February 15, 2012) to allow...

  10. Importance of funding in decommissioning cost estimates

    International Nuclear Information System (INIS)

    Decommissioning cost estimates have been made by several study groups for the decommissioning of pressurized-water and boiling-water nuclear power stations. The results of these studies are comparable when corrected for inflation and the differences in contingency factors applied by the study groups. The estimated dismantling costs differ far less than a factor of 2 in all cases, despite the design differences found in the plants that were studied. An analysis of the different methods available for funding the dismantling of these facilities shows the much stronger effect that the choice of funding methods has on the net cost of decommissioning. The total cost of dismantling may vary more than a factor of 4 from one funding method to another, assuming current or recent historical inflation rates. The funding methods evaluated include sinking funds, deposits, negative-salvage value depreciation, and insurance. These funding methods are taken from the NRC's Notice of Proposed Rulemaking description of acceptable funding methods. The funding analysis for this study was performed using the DECOST-86 computer code. The evaluation of funding options for a nuclear facility, and the appropriate choice of the funding method best for that facility, are found to be more important than detailed engineering studies in determining the net cost of decommissioning during the early portions of the plant's operating lifetime

  11. Decontamination and decommissioning focus area. Technology summary

    International Nuclear Information System (INIS)

    This report presents details of the facility deactivation, decommissioning, and material disposition research for development of new technologies sponsored by the Department of Energy. Topics discussed include; occupational safety, radiation protection, decontamination, remote operated equipment, mixed waste processing, recycling contaminated metals, and business opportunities

  12. Radiological characterization of nuclear plants under decommissioning

    International Nuclear Information System (INIS)

    In the present work a description of major problems encountered in qualitative and quantitative radiological characterization of nuclear plants for decommissioning and decontamination purpose is presented. Referring to several nuclear plant classes activation and contamination processes, direct and indirect radiological analysis and some italian significant experience are descripted

  13. Decommissioning of the Northrop TRIGA reactor

    International Nuclear Information System (INIS)

    An overview of the administrative and operational aspects of decommissioning and dismantling the Northrop Mark F TRIGA Reactor, including: planning and preparation, personnel requirements, government interfacing, costs, contractor negotiations, fuel shipments, demolition, disposal of low level waste, final survey and disposition of the concrete biological shielding. (author)

  14. Decontamination and decommissioning of Shippingport commercial reactor

    Energy Technology Data Exchange (ETDEWEB)

    Schreiber, J. [Dept. of Energy, Pittsburgh, PA (United States)

    1989-11-01

    To a certain degree, the decontamination and decommissioning (D and D) of the Shippingport reactor was a joint venture with Duquesne Light Company. The structures that were to be decommissioned were to be removed to at least three feet below grade. Since the land had been leased from Duquesne Light, there was an agreement with them to return the land to them in a radiologically safe condition. The total enclosure volume for the steam and nuclear containment systems was about 1.3 million cubic feet, more than 80% of which was below ground. Engineering plans for the project were started in July of 1980 and the final environmental impact statement (EIS) was published in May of 1982. The plant itself was shut down in October of 1982 for end-of-life testing and defueling. The engineering services portion of the decommissioning plans was completed in September of 1983. DOE moved onto the site and took over from the Navy in September of 1984. Actual physical decommissioning began after about a year of preparation and was completed about 44 months later in July of 1989. This paper describes the main parts of D and D.

  15. Decommissioning technology development for research reactors

    International Nuclear Information System (INIS)

    Although it is expected that the decommissioning of a nuclear power plant will happen since 2020, the need of partial decommissioning and decontamination for periodic inspection and life extension has been on an increasing trend and domestic market has gradually been extended. Therefore, in this project the decommissioning DB system on the KRR-1 and 2 was developed as establishing the information classification system of the research reactor dismantling and the structural design and optimization of the decommissioning DB system. Also in order to secure the reliability and safety about the dismantling process, the main dismantling simulation technology that can verify the dismantling process before their real dismantling work was developed. And also the underwater cutting equipment was developed to remove these stainless steel parts highly activated from the RSR. First, the its key technologies were developed and then the design, making, and capability analysis were performed. Finally the actual proof was achieved for applying the dismantling site. an automatic surface contamination measuring equipment was developed in order to get the sample automatically and measure the radiation/radioactivity

  16. Estimation of decommissioning costs: History and status

    International Nuclear Information System (INIS)

    In the mid-1970s. the subject of the cost of decommissioning nuclear power stations became a topic of considerable interest to the industry. A number of early demonstration plants in the US had been retired and most had been entombed. Only one plant, the Elk River Reactor (a small boiling water facility) had been totally dismantled and removed from the site (Welsh 1974). Thus, there was a very limited data base from which to develop estimates for decommissioning the much larger stations then under construction and coming into service. The nuclear industry sponsored another study for estimating decommissioning costs using an approach known as the Unit Cost Factor (UCF) method. This methodology is documented in AIF/NESP-0036 (LaGuardia 1986). and forms the basis for many of the estimates prepared by (or for) utilities for usein making submissions to their utility rate commissions to recover future decommissioning costs through current rates. This and other estimating approaches mentioned above are discussed in more detail in this paper

  17. Vandellos 1 NPP decommissioning feedback experience

    International Nuclear Information System (INIS)

    The Vandellos 1 Nuclear Power Plant (CNV1) is located on the Mediterranean coast in the province of Tarragona (Spain). The Plant is of the European Natural Uranium Graphite-Gas type. The thermal power of the plant amounts to 1,670 MWt, its electrical output being 500 Mwe. The Plant started-up commercial service in May 1972; its final shutdown, due to a fire in the turbines, occurred in October 1989, after 17 years of operation with an accumulated energy production of 55,647 GWh. The option of decommissioning accepted by the Ministry of Industry, consists of first removing the spent fuel and conditioning the operating radioactive wastes, and then undertaking dismantling of almost all the structures and components located outside the reactor vessel, except those ensuring confinement of the vessel itself and the safety and surveillance of the facility and site. No action will be taken with respect to the vessel, in which the reactor will remain confined without nuclear fuel and with its internal components intact until completion of the waiting (dormancy) period. The site itself will be kept under surveillance during dormancy phase, following partial clearance, the remaining installations being left within the new site perimeter in a situation of monitored confinement. Following the dormancy period, which will last some 30 years, total dismantling of the remaining installations will be undertaken, this implying subsequent complete clearance of the site. The project was started in November of 1992, and the works on site began in 1998. The safe enclosure consists only in the reactor pressure vessel, which will be left on site. The activity content of the vessel is about 100 000 Ci, mostly Co 60. Part of the Stage 2 concept is the total static isolation of this vessel. The vessel has 1 700 penetrations, the pipes of which were cut, seal-welded and inspected. After five years of works in Vandellos 1 NPP decommissioning, ENRESA has an experience and knowledge, that is necessary to support in order to reuse and apply the model to others projects. This knowledge and experience are mostly in three areas: -Data Bases, -Basic Document and - Lessons Learned which are described. Lessons Learned are summarized in eleven conclusions: a) The dilemma about the difference between an installation in operation and a decommissioning works. A NPP in operation is an installation; a NPP in decommissioning process is an activity, this impact is fundamental from the documentary and controls points of view; b) The flexibility of the time schedule of the project. In opposition with a construction, the time schedule of a decommissioning project it possible to maintain with small delays due to the versatility of parallel tasks; c) The authorization procedure is one of the key points, before and during the process. As a new activity, decommissioning was born without specifics regulation; day by day all the actors realize that is necessary to reflect back together in order to define and establish new standards to regulate the decommissioning processes; d) The prevention of the risks on site is a topic not only related to the Protection Radiation, the conventional risks have more importance in the decommissioning tasks. The issue of the new regulation about it, impact directly in the executions of the works. The training and the information to the workers are the best corrective tool again the risks; e) Some performances or characteristics of the auxiliary systems must be taken in account in the procurement process for decommissioning, namely, the modularity, versatility of the auxiliary systems and the reuse as a way of reducing wastes and save row materials. The radiation protection is the subject concern during all the operations; Important issues of radioprotection as operational radiological history, the characterization of the materials and the environment to prevent the risk, and special care with the internal contamination of the body; g) The very big amount of material generated during the decommissioning works, the different types, the different origins, the different vector nuclides make the problem of the materials control, a serious problem, which must be managed as a logistics with a fine control and software systems support; h) The characterisation of the materials is a very detailed work in order to define the ways for dispatching. Any radwaste procedure must be supported by a characterization data. The characterization of the materials takes more importance in the clearance process; everybody knows the relevance of the radiological decisions for release the materials outside; i) The new designs can be improve with the experience of the decommissioning. When you arrive at the last step of any industrial activity, you realize that could be designed better; Some times, technicians speak about the improve the alloy of the metals, it's true, but 'there are more things relatively important, as a expansion joints, waterproof surfaces, an other aspects, that can be improve to facilitate decommissioning activities; j) The records are the bases of the projects. To have a good documentation (as-built) from the operation time is needed in order to perform the project; During the decommissioning projects recorded files of the executed works are needed for the future, mostly in deferred dismantlement. Reflections about physical support and management system of records must be done; k) The human resources in the works are essential. It's necessary to integrate the experience of operation phase into these decommissioning teams. The multidisciplinary must be a characteristic of the teams; some changes must be done in the organization chart when the installations pass from the operational phase to the decommissioning phase. The organization from the operation is not directly applicable to decommissioning

  18. Study on decommissioning (Annual safety research report, JFY 2010)

    International Nuclear Information System (INIS)

    This project consists of researches for 1. review plan for decommissioning plan, 2. specific method to confirm completion of decommissioning and 3. dismantling waste management method. Dismantling experiences and knowledge of domestic and international trends of decommissioning were examined and the confirmation items for authorization of decommissioning plan were extracted. The estimation of site contamination during dismantling period was performed by use of radioactive material release data of the Tokai NPP. Domestic and some foreign countries knowledge of experience of decommissioning completion confirmation was examined. This knowledge was reflected in NISA's Committee Report 'Basic concept to confirm completion of decommissioning (Interim report) - Main issues and direction of future investigation-'. Three concrete cores were sampled in biological shield of the Tokai NPP to establish method of waste package verification based on radiation level evaluation in decommissioning and dismantling waste management method. (author)

  19. Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Chinese Edition)

    International Nuclear Information System (INIS)

    Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning

  20. Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Russian Edition)

    International Nuclear Information System (INIS)

    Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning

  1. Decommissioning of Facilities. General Safety Requirements. Pt. 6

    International Nuclear Information System (INIS)

    Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning

  2. Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Arabic Edition)

    International Nuclear Information System (INIS)

    Decommissioning is the last step in the lifetime management of a facility. It must also be considered during the design, construction, commissioning and operation of facilities. This publication establishes requirements for the safe decommissioning of a broad range of facilities: nuclear power plants, research reactors, nuclear fuel cycle facilities, facilities for processing naturally occurring radioactive material, former military sites, and relevant medical, industrial and research facilities. It addresses all the aspects of decommissioning that are required to ensure safety, aspects such as roles and responsibilities, strategy and planning for decommissioning, conduct of decommissioning actions and termination of the authorization for decommissioning. It is intended for use by those involved in policy development, regulatory control and implementation of decommissioning

  3. Development of the Decommissioning Project Management System, DECOMMIS

    Energy Technology Data Exchange (ETDEWEB)

    Chung, U. S.; Park, J. H.; Lee, K. W.; Hwang, D. S.; Park, S. K.; Hwang, S. T.; Paik, S. T.; Choi, Y. D.; Chung, K. H.; Lee, K. I.; Hong, S. B

    2007-03-15

    At the Korea Atomic Energy Research Institute(KAERI), two projects for decommissioning of the research reactors and uranium conversion plant are carried out. The management of the projects can be defined as 'the decision of the changes of the decommissioning methodologies for the more efficient achievement of the project at an adequate time and to an improved method'. The correct decision comes from the experiences on the decommissioning project and the systematic experiences can be obtained from the good management of the decommissioning information. For this, a project management tool, DECOMMIS, was developed in the D and D Technology Division, which has the charge of the decommissioning projects at the KAERI, and its purpose was extended to following fields; generation of reports on the dismantling waste for WACID, record keeping for the next decommissioning projects of nuclear facilities, provision of fundamental data for the R and D of the decommissioning technologies.

  4. Decommissioning of NPP A1 - HWGCR type

    International Nuclear Information System (INIS)

    Prototype nuclear power plant A-1 located at Jaslovske Bohunice, was a HWGCR with channel type reactor KS 150 (refuelling during operation) and capacity of 143 MWe. Single unit has been constructed with reactor hall building containing reactor vessel, heavy water system and equipment for spent fuel handling. Another compartment of main building contents coolant system piping, six steam generators and six turbo compressors, the turbine hall was equipped by three turbines. Unit also shares liquid radwaste treatment and storage buildings and ventilation systems including chimney. It started operation in 1972 and was shutdown in 1977 after primary coolant system integrity accident. In 1979 a final decision was made to decommission this plant. The absence of waste treatment technologies and repository and not sufficient storage capacity affected the planning and realization of decommissioning for NPP A-1. The decommissioning policy for the first stage is for lack of regulations based on 'case by case' strategy. For these reasons and for not existence of Decommissioning Found until 1995 the preferred decommissioning option is based on differed decommissioning with safe enclosure of confinement. Transfer of undamaged spent fuel cooled in organic coolant to Russia was finished in 1990. It was necessary to develop new technology for the damaged fuel preparation for transport. The barriers check-up and dismantling of secondary circuit and cooling towers was performed during 1989/90. The complex plan for the first phase of A-1 decommissioning - the status with treated operational radwaste, removed contamination and restored treated waste and spent fuel (in case of interruption of transfer to Russia) was developed in 1993-1994. Under this project bituminization of all liquid operational radwaste (concentrates) was performed during 1995/96, vitrification of inorganic spent fuel coolant started at 1996, decontamination of spent fuel pool coolant occurs (under AEA Technology support) in 1997 as well as preparation for bituminization of organic spent fuel coolant. The new equipment for spent fuel handling including new storage (semi dry) for spent fuel was projected and should be built up in 1997. The decontamination and dismantling of auxiliary equipment (radwaste tanks, evaporation plant and original solid storage) should start after the commissioning of conditioning centre and bituminization plant with new evaporation plant in 1998 and finish at 2000. The decontamination and dismantling of original spent fuel storage should finish at 2007/8. Supporting activities to these works started at 1994/95. (author)

  5. Decommissioning of TRIGA Mark II type reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Dooseong; Jeong, Gyeonghwan; Moon, Jeikwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-10-15

    The first research reactor in Korea, KRR 1, is a TRIGA Mark II type with open pool and fixed core. Its power was 100 kWth at its construction and it was upgraded to 250 kWth. Its construction was started in 1957. The first criticality was reached in 1962 and it had been operated for 36,000 hours. The second reactor, KRR 2, is a TRIGA Mark III type with open pool and movable core. These reactors were shut down in 1995, and the decision was made to decommission both reactors. The aim of the decommissioning activities is to decommission the KRR 2 reactor and decontaminate the residual building structures and site, and to release them as unrestricted areas. The KRR 1 reactor was decided to be preserve as a historical monument. A project was launched for the decommissioning of these reactors in 1997, and approved by the regulatory body in 2000. A total budget for the project was 20.0 million US dollars. It was anticipated that this project would be completed and the site turned over to KEPCO by 2010. However, it was discovered that the pool water of the KRR 1 reactor was leaked into the environment in 2009. As a result, preservation of the KRR 1 reactor as a monument had to be reviewed, and it was decided to fully decommission the KRR 1 reactor. Dismantling of the KRR 1 reactor takes place from 2011 to 2014 with a budget of 3.25 million US dollars. The scope of the work includes licensing of the decommissioning plan change, removal of pool internals including the reactor core, removal of the thermal and thermalizing columns, removal of beam port tubes and the aluminum liner in the reactor tank, removal of the radioactive concrete (the entire concrete structure will not be demolished), sorting the radioactive waste (concrete and soil) and conditioning the radioactive waste for final disposal, and final statuses of the survey and free release of the site and building, and turning over the site to KEPCO. In this paper, the current status of the TRIGA Mark-II type reactor decommissioning projects was introduced.

  6. Decommissioning of TRIGA Mark II type reactor

    International Nuclear Information System (INIS)

    The first research reactor in Korea, KRR 1, is a TRIGA Mark II type with open pool and fixed core. Its power was 100 kWth at its construction and it was upgraded to 250 kWth. Its construction was started in 1957. The first criticality was reached in 1962 and it had been operated for 36,000 hours. The second reactor, KRR 2, is a TRIGA Mark III type with open pool and movable core. These reactors were shut down in 1995, and the decision was made to decommission both reactors. The aim of the decommissioning activities is to decommission the KRR 2 reactor and decontaminate the residual building structures and site, and to release them as unrestricted areas. The KRR 1 reactor was decided to be preserve as a historical monument. A project was launched for the decommissioning of these reactors in 1997, and approved by the regulatory body in 2000. A total budget for the project was 20.0 million US dollars. It was anticipated that this project would be completed and the site turned over to KEPCO by 2010. However, it was discovered that the pool water of the KRR 1 reactor was leaked into the environment in 2009. As a result, preservation of the KRR 1 reactor as a monument had to be reviewed, and it was decided to fully decommission the KRR 1 reactor. Dismantling of the KRR 1 reactor takes place from 2011 to 2014 with a budget of 3.25 million US dollars. The scope of the work includes licensing of the decommissioning plan change, removal of pool internals including the reactor core, removal of the thermal and thermalizing columns, removal of beam port tubes and the aluminum liner in the reactor tank, removal of the radioactive concrete (the entire concrete structure will not be demolished), sorting the radioactive waste (concrete and soil) and conditioning the radioactive waste for final disposal, and final statuses of the survey and free release of the site and building, and turning over the site to KEPCO. In this paper, the current status of the TRIGA Mark-II type reactor decommissioning projects was introduced

  7. International Decommissioning Network as a Forum to Support Decommissioning Activities In Countries with Limited Resources and Experience: the Serbian Case

    International Nuclear Information System (INIS)

    Vinca Institute Nuclear Decommissioning Program (VIND Program) is aimed to improve nuclear and radiation safety in the Vinca Institute of Nuclear Sciences, Serbia, by repatriation of the leaking spent nuclear fuel, expanding the capabilities for radioactive waste treatment and storage, and the decommissioning of several nuclear legacy sites. In this paper the case of heavy water research reactor decommissioning is considered, some specific needs for the support through IAEA International Decommissioning Network are elaborated, and proposals for events and activities which could help the preparation and implementation of key decommissioning tasks are made. (authors)

  8. The BR-3 decommissioning project, Belgium

    International Nuclear Information System (INIS)

    BR-3 was a small 10 MW(e) PWR which was shut down in 1987 after 25 years of operation. It was selected as an EU pilot project for the research and development programme on decommissioning of nuclear installations. The decommissioning project started in 1989. The optimization of the management of waste material generated by decommissioning activities has always been an intensive task and the minimization of the radioactive waste a priority. Over the past 16 years, the factors influencing the management of waste have been constantly evolving in Belgium, steered mainly by the following changes in technologies, regulations and economic conditions: - The publication of the Royal Decree of 20 July 2001, establishing a legal frame on decommissioning and including a set of clearance levels; - The improvement of the instrumentation used for characterization; - The increase in the performance of decontamination techniques; - The cost increase of the waste disposal paths; - The implementation of international recommendations in areas such as environmental impact, waste categorization, human aspects, ethics, etc.; -The strengthening of the legislation related to industrial safety and environmental release; - The diminution of the background radiation level at the decommissioning site itself. The first part of this annex gives a description of relevant influencing factors in order to define the context in which the dismantling activities took place. The second part puts in perspective the strategy chosen for the management of the waste, recognizing the influencing factors. As mentioned in the scope of this report, the focus is LLW. High and intermediate level wastes for which disposal in dedicated repositories is assumed are outside the scope of this report. They are therefore not examined in detail here

  9. European Nuclear Decommissioning Training Facility II

    International Nuclear Information System (INIS)

    SCK-CEN co-ordinates a project called European Nuclear Decommissioning Training Facility II (EUNDETRAF II) in the Sixth Framework Programme on Community activities in the field of research, technological development and demonstration for the period 2002 to 2006. This was a continuation of the FP5 project EUNDETRAF. EUNDETRAF II is a consortium of main European decommissioners, such as SCK-CEN, EWN (Energie Werke Nord, Greifswald Germany), Belgatom (Belgium), SOGIN Societa Gestione Impiantio Nucleari, Italy), Universitaet Hannover (Germany), RWE NUKEM (United Kingdom), DECOM Slovakia Slovakia), CEA Centre d'Energie Atomique, France), UKAEA (United Kingdom's Atomic Energy Agency, United Kingdom) and NRG (Nuclear Research and consultancy Group, Netherlands). The primary objective of this project is to bring together this vast skill base and experience; to consolidate it for easy assimilation and to transfer to future generations by organising a comprehensive training programme.Each training course has a one-week theoretical and a one-week practical component. The theoretical part is for a broader audience and consists of lectures covering all the main aspects of a decommissioning. The practical part of the course includes site visits and desk top solutions of anticipated decommissioning problems. Due to operational constraints and safety considerations, the number of participants to this part of the course is strictly limited. The partners intend to organise altogether two two-week EUNDETRAF II training courses over a period of three years. Another goal is to disseminate the existing theory as well as the practical know-how to personnel of the third countries. Finally it is important to bring together the principal decommissioning organisations undertaking various decommissioning activities. The project creates a forum for regular contacts to exchange information and experiences for mutual benefit of these organisations as well as to enhance skill base in Europe to strengthen the European position in the world

  10. AVR decommissioning, achievements and future programme

    International Nuclear Information System (INIS)

    Safestore decommissioning of the AVR 15 MWe experimental nuclear power plant with pebble bed high-temperature gas-cooled reactor (HTGR) began in March 1994 with defueling (phase 1). Beginning of Aug. 1997, defueling as to 81% completed. Other achievements: The dismantling in the turbine hall and outside the buildings is nearly terminated, the cooling towers are demolished, and the helium bottle-battery storage and helium compressors were removed from the ring buildings in Dec. 1996. The latter was the first dismantling inside the reactor building and belonged to projects that had been advanced from the 2nd into the 1st phase of Safestore decommissioning because of the delay in defueling. Furthermore, the licence for a first supplement to Safestore decommissioning was granted in March 1997. Inside the containment, the removal of shielding material and of insulation material from the secondary circuit components is either already or will shortly be terminated. This will give access for cutting and sealing the 120 steam generator pipe penetrations above the outer reactor vessel. The scope of Safestore decommissioning, as licensed in March 1994, will be extended by three supplements, comprising mainly the dismantling of (1) the fuel handling system, coolant circulators, and interspace convection pipe, (2) the coolant purification system, and condensation coolers, and (3) the shutdown rod system. The goal is to clear the containment from all auxiliary systems and to seal the outer reactor vessel until the end of 2001. The final goal of Continued dismantling is the restoration of the green field until 2011. The term indicated the direct transition from the present Safestore decommissioning and a stepwise procedure that can be interrupted after each step and be transferred into a Safestore mode. The decision for Continued dismantling is expected in 1998; a contract for the design and licence planning will be awarded soon. (author)

  11. SOGIN Decommissioning strategy and funding (Italy)

    International Nuclear Information System (INIS)

    Statement: In Italy, as it is well known, there are no more operational NPPs. The four existing nuclear plants are definitely shutdown and ready for decommissioning. Considerations on decommissioning funding system have to take into account this particular situation. Strategy for decommissioning: New inputs given to SOGIN by the Italian Government are: conditioning all radioactive waste existing on the NPPs within the year 2010, release all nuclear sites - free of radiological constraints - by 2020. The last task is conditioned by availability of the national waste repository by the year 2009. Strategy for decommissioning: Key issue is prompt dismantling considering No more nuclear activities in Italy and Progressive loss of competencies. Previously Existing funds: Before plant shutdown, ENEL has cumulated provisions for decommissioning, even in absence of a clear regulatory framework. These provisions were not sufficient for decommissioning, considering the early closure of the plants. An additional fund was granted to ENEL by the government, in the form of a 'credit' to be paid by the 'electric system' (CCSE). This fund (provisions + credit) was considered sufficient by ENEL for a decommissioning with Safe Store strategy (fund = discounted foreseen costs). The total fund (provisions + credit) was assigned to Sogin at the incorporation date. The amount, money 1999, was about 800 M euros. Considering the new context: new strategy (Prompt Dismantling with site release by 2020), Sogin constitution (societal costs), new economic conditions. The fund was not considered sufficient for all Sogin tasks. This conclusion was agreed upon also by the independent 'Authority for electric energy and gas'. A new regulatory framework was therefore defined. Regulatory aspects: The Legislative Decree 79/99 has stated that costs for the decommissioning of NPP, fuel cycle back end and related activities should be considered as stranded costs for the general electric system. The same Decree stated that a specific company should have been established for the management of these activities. Consequently, Sogin has been incorporated, all nuclear assets and liabilities of Enel being assigned to the Company. Sogin is responsible for decommissioning and fuel back end, under the policy indicated by the Government. The Ministerial Decree 26.01.2000 precisely defined which costs can be considered as stranded costs. As a matter of fact, the decree confirms that all costs incurred in by Sogin for decommissioning, fuel cycle back end, wastes disposal are to be considered. The same Decree defines modalities for funding Sogin for the above mentioned activities. The same Decrees define that in the 'related activities' the dismantling of research plants for the nuclear fuel cycle should be considered. These plants are now property of Enea and FN. The Decree defines modalities for funding Sogin for the above mentioned activities. Sogin is entitled to receive also the funds for the decommissioning of Enea plants, providing a Consortium with Enea. Funding mechanism - Main Criteria: Costs are financed with a levy on the price of kWh for final consumers. The amount of the levy, for different categories of consumers, is defined by the 'Authority for electric energy and gas'. Regulatory procedure: Sogin presents to the Authority, each year, a complete program with scheduled activities and cost estimates for the overall project. Present estimates consider a global cost of about 2600 M euros for power plants and 630 M euros for Research plants. The Authority, every three years, determines the total amount of the expenses on the basis of Sogin documentation, taking into account efficiency criteria. Annual re-considerations are possible if major events occur. On this basis, the Authority defines the amount of the levy. In early 2002, the Authority issued the first resolution for the determination of decommissioning costs Specific reference was made to costs foreseen for 2002-2004, in the general context of the pluri-annual program. The Authority endorsed the cost estimates of Sogin. A global levy of about 0,06 euro-cents/kWh is now established; the annual income for Sogin (and Enea) is about 150 M euros. In summary, Sogin has today a decommissioning fund that is built by two parts: the provision (cash) assigned from Enel (about 400 M euros), a credit towards the 'electric system', corresponding to the expenses foreseen in next three years period (about 350 M euros). This credit shall be re-determined every three year It is expected that in the medium term decommissioning costs shall be covered by re-determined credits for successive three year periods. The cash part of the fund shall be used in the long term. The 'cash' part of the fund is managed by Sogin according to guidelines issued by the Ministry of Economy. At the moment only low risk investment are allowed

  12. 30 CFR 250.1751 - How do I decommission a pipeline in place?

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 2 2010-07-01 2010-07-01 false How do I decommission a pipeline in place? 250... Pipeline Decommissioning 250.1751 How do I decommission a pipeline in place? You must do the following to decommission a pipeline in place: (a) Submit a pipeline decommissioning application in triplicate to...

  13. NMSS handbook for decommissioning fuel cycle and materials licensees

    Energy Technology Data Exchange (ETDEWEB)

    Orlando, D.A.; Hogg, R.C.; Ramsey, K.M. [and others

    1997-03-01

    The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ``Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.`` The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC`s SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook.

  14. NMSS handbook for decommissioning fuel cycle and materials licensees

    International Nuclear Information System (INIS)

    The US Nuclear Regulatory Commission amended its regulations to set forth the technical and financial criteria for decommissioning licensed nuclear facilities. These regulations were further amended to establish additional recordkeeping requirements for decommissioning; to establish timeframes and schedules for the decommissioning; and to clarify that financial assurance requirements must be in place during operations and updated when licensed operations cease. Reviews of the Site Decommissioning Management Plan (SDMP) program found that, while the NRC staff was overseeing the decommissioning program at nuclear facilities in a manner that was protective of public health and safety, progress in decommissioning many sites was slow. As a result NRC determined that formal written procedures should be developed to facilitate the timely decommissioning of licensed nuclear facilities. This handbook was developed to aid NRC staff in achieving this goal. It is intended to be used as a reference document to, and in conjunction with, NRC Inspection Manual Chapter (IMC) 2605, ''Decommissioning Inspection Program for Fuel Cycle and Materials Licensees.'' The policies and procedures discussed in this handbook should be used by NRC staff overseeing the decommissioning program at licensed fuel cycle and materials sites; formerly licensed sites for which the licenses were terminated; sites involving source, special nuclear, or byproduct material subject to NRC regulation for which a license was never issued; and sites in the NRC's SDMP program. NRC staff overseeing the decommissioning program at nuclear reactor facilities subject to regulation under 10 CFR Part 50 are not required to use the procedures discussed in this handbook

  15. Nuclear submarine decommissioning. Radiation risk assessments

    International Nuclear Information System (INIS)

    Decommissioning of the ships and vessels with nuclear power installations is a problem of primary and worldwide importance. It is essential for both the naval fleet and the military industrial complex as a whole. Nuclear submarines decommissioning is accompanied by a number of questions concerning the development and performance of the safe technologies for managing radioactive equipment and nuclear waste from the vessels with the nuclear power facilities. Decommissioning of nuclear submarines including unloading of the spent fuel should take place at the operating ship yards and repairing plants that are usually situated close to the densely populated areas and living blocks. Decommissioning includes a series of the potentially dangerous operations with radioactive materials, e.g. fuel unloading, disposal of coolant, dismantling of the contaminated equipment, cutting out the reactor compartment, etc. As a result a great amount of highly radioactive liquid and solid wastes are formed including the cut-out reactor compartment and spent fuel that produce additional radioactive load on the local environment and population. Estimation of the radiation risk for the environment and population due to decommissioning becomes an actual and necessary question. Apart from this the process of decommissioning may cause accidents followed by complicated radiation situation with high dose rates and contamination of the environment. Analysis of the most probable scenarios of the accident development and estimation of the expected radiation consequences should help to assess the risk rate for radiation impact on the environment and population as well as to develop an adequate environmental monitoring and to undertake measures for the accident localisation and liquidation of its consequences. A separate problem is management of the reactor compartment containing radioactive equipment of the steam producing installation and biological protection. Since there are no specialised facilities with an adequate equipment for decomposition of reactor compartments incorporating highly active equipment they need to be stored in special containers for a long period until radiation level decreases to the level safe for decomposing operations without special remote and protection equipment. Various storage techniques are discussed, e.g. in floating regime, burial in shallow waters, open ground, etc. (author)

  16. On Decommissioning Costs of the Ranstad Site

    International Nuclear Information System (INIS)

    The main objective of this study has been to extend the review of the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. The feedback of experience and actual costs from a decommissioning project in the United Kingdom (A26 in Springfields) has been used to help in the assessment of the reasonableness of the estimated costs for decommissioning of the old uranium mine in Ranstad. A quantitative (albeit subjective) statement about the accuracy of the Ranstad cost estimate has been developed. Also, the factors relevant to the allocation of costs between the Swedish state and the current owners of the old uranium mine site have been evaluated and presented. The study has developed the following main conclusions: - The importance of thorough characterization/radiological mapping to the selection of the optimum decommissioning approach (technique) has been reinforced very strongly. - Thorough characterization has the related consequence of being able to better define the costs of decommissioning, in terms of equipment needed, labour hours required and, importantly, the volumes of different categories of waste requiring different routes (and associated different unit costs) for ultimate disposition. - Uncertainties in the Ranstad decommissioning cost estimate nevertheless remain, in particular relating to the viability of the proposed approach to dismantling and decontaminating the acid proof bricks that line the pools in the Large Leaching Hall; a method that is acknowledged to be not proven. The outcome could have an impact on actual dismantling and decontamination costs, as well as on the costs of ultimate waste disposition. The KB2010 cost estimate report does not offer an alternative in the event that the base plan proves to be unfeasible. - On balance it would appear that the continued presence of RMA at the Ranstad site ultimately will provide a net cost benefit to the program. The extra costs that RMA operations may cause are assessed to be more than offset by the benefits of having a functioning RMA Leach Hall facility, as well as the historical benefits of general site management

  17. Nuclear submarine decommissioning. Radiation risk assessments

    Energy Technology Data Exchange (ETDEWEB)

    Blekher, A. Ja.; Dovgusha, V.V. [Research Inst. of Industrial and Marine Medicine, St.-Petersburg (Russian Federation); Kuchin, N.L. [Krylov Inst., St.-Petersburg (Russian Federation)

    2000-05-01

    Decommissioning of the ships and vessels with nuclear power installations is a problem of primary and worldwide importance. It is essential for both the naval fleet and the military industrial complex as a whole. Nuclear submarines decommissioning is accompanied by a number of questions concerning the development and performance of the safe technologies for managing radioactive equipment and nuclear waste from the vessels with the nuclear power facilities. Decommissioning of nuclear submarines including unloading of the spent fuel should take place at the operating ship yards and repairing plants that are usually situated close to the densely populated areas and living blocks. Decommissioning includes a series of the potentially dangerous operations with radioactive materials, e.g. fuel unloading, disposal of coolant, dismantling of the contaminated equipment, cutting out the reactor compartment, etc. As a result a great amount of highly radioactive liquid and solid wastes are formed including the cut-out reactor compartment and spent fuel that produce additional radioactive load on the local environment and population. Estimation of the radiation risk for the environment and population due to decommissioning becomes an actual and necessary question. Apart from this the process of decommissioning may cause accidents followed by complicated radiation situation with high dose rates and contamination of the environment. Analysis of the most probable scenarios of the accident development and estimation of the expected radiation consequences should help to assess the risk rate for radiation impact on the environment and population as well as to develop an adequate environmental monitoring and to undertake measures for the accident localisation and liquidation of its consequences. A separate problem is management of the reactor compartment containing radioactive equipment of the steam producing installation and biological protection. Since there are no specialised facilities with an adequate equipment for decomposition of reactor compartments incorporating highly active equipment they need to be stored in special containers for a long period until radiation level decreases to the level safe for decomposing operations without special remote and protection equipment. Various storage techniques are discussed, e.g. in floating regime, burial in shallow waters, open ground, etc. (author)

  18. In Situ Decommissioning (ISD) Concepts and Approaches for Excess Nuclear Facilities Decommissioning End State - 13367

    Energy Technology Data Exchange (ETDEWEB)

    Serrato, Michael G. [Savannah River National Laboratory, Savannah River Nuclear Solutions, Aiken, SC 29808 (United States); Musall, John C.; Bergren, Christopher L. [Savannah River Nuclear Solutions, Aiken, SC 29808 (United States)

    2013-07-01

    The United States Department of Energy (DOE) currently has numerous radiologically contaminated excess nuclear facilities waiting decommissioning throughout the Complex. The traditional decommissioning end state is complete removal. This commonly involves demolishing the facility, often segregating various components and building materials and disposing of the highly contaminated, massive structures containing tons of highly contaminated equipment and piping in a (controlled and approved) landfill, at times hundreds of miles from the facility location. Traditional demolition is costly, and results in significant risks to workers, as well as risks and costs associated with transporting the materials to a disposal site. In situ decommissioning (ISD or entombment) is a viable alternative to demolition, offering comparable and potentially more protective protection of human health and the environment, but at a significantly reduced cost and worker risk. The Savannah River Site (SRS) has completed the initial ISD deployment for radiologically contaminated facilities. Two reactor (P and R Reactors) facilities were decommissioned in 2011 using the ISD approach through the American Recovery and Reinvestment Act. The SRS ISD approach resolved programmatic, regulatory and technical/engineering issues associated with avoiding the potential hazards and cost associated with generating and disposing of an estimated 124,300 metric tons (153,000 m{sup 3}) of contaminated debris per reactor. The DOE Environmental Management Office of Deactivation and Decommissioning and Facility Engineering, through the Savannah River National Laboratory, is currently investigating potential monitoring techniques and strategies to assess ISD effectiveness. As part of SRS's strategic planning, the site is seeking to leverage in situ decommissioning concepts, approaches and facilities to conduct research, design end states, and assist in regulatory interactions in broad national and international government and private industry decommissioning applications. SRS offers critical services based upon the SRS experience in decommissioning and reactor entombment technology (e.g., grout formulations for varying conditions, structural and material sciences). The SRS ISD approach follows a systems engineering framework to achieve a regulatory acceptable end state based on established protocols, attains the final end state with minimal long stewardship requirements, protects industrial workers, and protects groundwater and the environment. The ISD systems engineering framework addresses key areas of the remedial process planning, technology development and deployment, and assessment to attain the ultimate goal of natural resource stewardship and protecting the public. The development and deployment of the SRS ISD approach has established a path for ISD of other large nuclear facilities in the United States and around the globe as an acceptable remedial alternative for decommissioning nuclear facilities. (authors)

  19. In Situ Decommissioning (ISD) Concepts and Approaches for Excess Nuclear Facilities Decommissioning End State - 13367

    International Nuclear Information System (INIS)

    The United States Department of Energy (DOE) currently has numerous radiologically contaminated excess nuclear facilities waiting decommissioning throughout the Complex. The traditional decommissioning end state is complete removal. This commonly involves demolishing the facility, often segregating various components and building materials and disposing of the highly contaminated, massive structures containing tons of highly contaminated equipment and piping in a (controlled and approved) landfill, at times hundreds of miles from the facility location. Traditional demolition is costly, and results in significant risks to workers, as well as risks and costs associated with transporting the materials to a disposal site. In situ decommissioning (ISD or entombment) is a viable alternative to demolition, offering comparable and potentially more protective protection of human health and the environment, but at a significantly reduced cost and worker risk. The Savannah River Site (SRS) has completed the initial ISD deployment for radiologically contaminated facilities. Two reactor (P and R Reactors) facilities were decommissioned in 2011 using the ISD approach through the American Recovery and Reinvestment Act. The SRS ISD approach resolved programmatic, regulatory and technical/engineering issues associated with avoiding the potential hazards and cost associated with generating and disposing of an estimated 124,300 metric tons (153,000 m3) of contaminated debris per reactor. The DOE Environmental Management Office of Deactivation and Decommissioning and Facility Engineering, through the Savannah River National Laboratory, is currently investigating potential monitoring techniques and strategies to assess ISD effectiveness. As part of SRS's strategic planning, the site is seeking to leverage in situ decommissioning concepts, approaches and facilities to conduct research, design end states, and assist in regulatory interactions in broad national and international government and private industry decommissioning applications. SRS offers critical services based upon the SRS experience in decommissioning and reactor entombment technology (e.g., grout formulations for varying conditions, structural and material sciences). The SRS ISD approach follows a systems engineering framework to achieve a regulatory acceptable end state based on established protocols, attains the final end state with minimal long stewardship requirements, protects industrial workers, and protects groundwater and the environment. The ISD systems engineering framework addresses key areas of the remedial process planning, technology development and deployment, and assessment to attain the ultimate goal of natural resource stewardship and protecting the public. The development and deployment of the SRS ISD approach has established a path for ISD of other large nuclear facilities in the United States and around the globe as an acceptable remedial alternative for decommissioning nuclear facilities. (authors)

  20. Technology, safety and costs of decommissioning a reference pressurized water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule

    International Nuclear Information System (INIS)

    Preparation of the final Decommissioning Rule by the Nuclear Regulatory Commission (NRC) staff has been assisted by Pacific Northwest Laboratory (PNL) staff familiar with decommissioning matters. These efforts have included updating previous cost estimates developed during the series of studies on conceptually decommissioning reference licensed nuclear facilities for inclusion in the Final Generic Environmental Impact Statement (FGEIS) on decommissioning; documenting the cost updates; evaluating the cost and dose impacts of post-TMI-2 backfits on decommissioning; developing a revised scaling formula for estimating decommissioning costs for reactor plants different in size from the reference pressurized water reactor (PWR) described in the earlier study; defining a formula for adjusting current cost estimates to reflect future escalation in labor, materials, and waste disposal costs; and completing a study of recent PWR steam generator replacements to determine realistic estimates for time, costs and doses associated with steam generator removal during decommissioning. This report presents the results of recent PNL studies to provide supporting information in four areas concerning decommissioning of the reference PWR: updating the previous cost estimates to January 1986 dollars; assessing the cost and dose impacts of post-TMI-2 backfits; assessing the cost and dose impacts of recent steam generator replacements; and developing a scaling formula for plants different in size than the reference plant and an escalation formula for adjusting current cost estimates for future escalation

  1. Decommissioning of the Tokamak Fusion Test Reactor

    Energy Technology Data Exchange (ETDEWEB)

    E. Perry; J. Chrzanowski; C. Gentile; R. Parsells; K. Rule; R. Strykowsky; M. Viola

    2003-10-28

    The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory was operated from 1982 until 1997. The last several years included operations with mixtures of deuterium and tritium. In September 2002, the three year Decontamination and Decommissioning (D&D) Project for TFTR was successfully completed. The need to deal with tritium contamination as well as activated materials led to the adaptation of many techniques from the maintenance work during TFTR operations to the D&D effort. In addition, techniques from the decommissioning of fission reactors were adapted to the D&D of TFTR and several new technologies, most notably the development of a diamond wire cutting process for complex metal structures, were developed. These techniques, along with a project management system that closely linked the field crews to the engineering staff who developed the techniques and procedures via a Work Control Center, resulted in a project that was completed safely, on time, and well below budget.

  2. Decommissioning of an uranium hexafluoride pilot plant

    International Nuclear Information System (INIS)

    The Institute of Nuclear and Energetic Researches has completed fifty years of operation, belongs to the National Commission for Nuclear Energy, it is situated inside the city of Sao Paulo. The IPEN-CNEN/SP is a Brazilian reference in the nuclear fuel cycle, researches in this field began in 1970, having dominance in the cycle steps from Yellow Cake to Uranium Hexafluoride technology. The plant of Uranium Hexafluoride produced 35 metric tonnes of this gas by year, had been closed in 1992, due to domain and total transference of know-how for industrial scale, demand of new facilities for the improvement of recent researches projects. The Institute initiates decommissioning in 2002. Then, the Uranium Hexafluoride pilot plant, no doubt the most important unit of the fuel cycle installed at IPEN-CNEN/SP, beginning decommissioning and dismantlement (D and D) in 2005. Such D and D strategies, planning, assessment and execution are described, presented and evaluated in this paper. (author)

  3. Shoreham decommissioning technology: Simple and effective

    International Nuclear Information System (INIS)

    This article reports that at Shoreham decommissioning a large nuclear power plant proves to be a straightforward exercise, accomplished with existing tools and procedures. Plans to dismantle Shoreham nuclear power embraced a simple concept: applying proven technology in new or innovative ways to get the job done. Although Shoreham's operating history was brief, the project is significant because the plant was a large commercial unit and the technologies and methods applied to dismantle it will eventually apply to the present operating fleet of nuclear plants when their service lives come to an end. So, in several respects, Shoreham became the proving ground for planning, techniques and technologies that are likely to figure prominently in the evolution of decommissioning practices over the next two decades

  4. Decommissioning plan for Andujar uranium mill facilities

    International Nuclear Information System (INIS)

    The milling of radioactive ores results in contaminated buildings and facilities which must be decommissioned, and large quantities of tailings which must be managed safely so that residual environmental and health risks do not exceed acceptable levels. In the south of Spain on the outskirts of the town of Andujar an inactive uranium mill facility is under decommissioning. Mill equipment, buildings and process facilities have been dismantled and demolished and the resulting metal wastes and debris have been placed in the pile. The tailing mass is being reshaped by flattening the sideslopes and a cover system will be placed over the pile. This paper describes the safety aspects and technical approaches which are being used for the remediation and closure of the Andujar mill site. (author). 7 figs

  5. Decommissioning? Why not use a robot

    International Nuclear Information System (INIS)

    Tasks which may be accomplished by robots alone or in conjunction with human workers in decommissioning nuclear facilities include: routine surveillance in contaminated areas; radiation surveys and sampling; preparation of work area; decontamination of walls and floors; disassembly of contaminated equipment and piping; internal decontamination of piping and waste storage/processing tanks; sorting materials; removal of large activated/contaminated structures; asbestos removal and packaging; transport of waste from disassembly areas; tending waste processing equipment; waste packaging for storage. The status of the technology is briefly reviewed and examples of the use of robots in decommissioning work in the USA are described. Although the use of robots in this field is not extensive so far, that use is increasing and information on its costs and benefits are becoming available. (UK)

  6. Decommissioning plan for the TRIGA mark-3

    International Nuclear Information System (INIS)

    TRIGA Mark-III (KRR-2) is the second research reactor in Korea. Construction of KRR-2 was started in 1969 and first criticality was achieved in 1972. After 24 years operation, KRR-2 has stopped its operation at the end of 1995 due to normal operation of HANARO. KRR-2 was then decided to decommission in 1996 by government. Decontamination and decommissioning (D and D) will be conducted in accordance with domestic laws and international regulations. Selected method of D and D will be devoted to protect workers and environment and to minimize radioactive wastes produced. The major D and D work will be conducted safely by using conventional industrial equipment because of relatively low radioactivity and contamination in the facility. When removing activated concrete from reactor pool, it will be installed a temporary containment and ventilation system. In this paper, structure of KRR-2 and method of D and D in each step are presented and discussed

  7. Perspective of decommissioning in East European countries

    International Nuclear Information System (INIS)

    A regional co-operation was organized in 1986 between East European countries on problems connected with the last stage of the NPP unit life cycle. Closure of a nuclear power plant (NPP) unit is considered as a problem with influence upon the safety of the nuclear energetics. Bulgaria, the USSR and Czechoslovakia have united their efforts establishing the Joint Venture for Decommissioning NPP 'Decom' thus giving a possibility for a safe and effective NPP unit decommissioning. At present a preparatory work is being conducted at the Joint Venture on all aspects of the problem - ecological, social, technical and economic. A certain practical experience has been accumulated. Research performed previously has delivered certain scientific and technical results. (author) 1 tab

  8. Design of user interface on decommissioning DB

    International Nuclear Information System (INIS)

    It has been designed GUI(Graphic user interface) to consult the convenience of a input data and the flexibility that can be retrieved dismantling information relation to decommissioning DB of KRR1 and 2. The GUI can proceed an input materials and a search and output of a saved data in server based on a facility code and also have a function of explorer which can find the lower dismantling objects in each facilities. It has added the structure of the multimedia that could be showed a series of dismantling activities with a Mpeg and pictures into the GUI. In the future work, decommissioning DB and user interface are intend to contribute a functions that could be evaluate and analyze for a dismantling activities with a engineering theory

  9. Decommissioning of the Tokamak Fusion Test Reactor

    International Nuclear Information System (INIS)

    The Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory was operated from 1982 until 1997. The last several years included operations with mixtures of deuterium and tritium. In September 2002, the three year Decontamination and Decommissioning (D and D) Project for TFTR was successfully completed. The need to deal with tritium contamination as well as activated materials led to the adaptation of many techniques from the maintenance work during TFTR operations to the D and D effort. In addition, techniques from the decommissioning of fission reactors were adapted to the D and D of TFTR and several new technologies, most notably the development of a diamond wire cutting process for complex metal structures, were developed. These techniques, along with a project management system that closely linked the field crews to the engineering staff who developed the techniques and procedures via a Work Control Center, resulted in a project that was completed safely, on time, and well below budget

  10. Law regulations on decommissioning of reactors

    International Nuclear Information System (INIS)

    Concerning the decommissioning of reactors, the major provisions are discussed in the Electricity Enterprises Act and The Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors. Tokai Unit 1 in Tokai Power Station, Japan's first nuclear power plant, will be subject to the low regulations on reactor decommissioning about ten years hence. JPDR (Japan Power Demonstration Reactor) is being dismantled in the near future. Accoring to the Act the electricity enterprise must obtain the permission thereon from the Ministry for International Trade and Industry. According to the Low, the reactor owner must report thereon in advance to the competent Minister and the competent Minister may give orders concerning the necessary measures etc. (Mori, K.)

  11. System for remotely controlled decommissioning operations

    International Nuclear Information System (INIS)

    The aim of the study was to analyse the possibilities of reducing radiation exposure during the decommissioning of nuclear facilities by employing remotely operated systems. All types of nuclear reactors and reprocessing plants that exist in the countries of the European Communities are included. In decommissioning tasks the main fields to be considered for remote control are monitoring by visual inspection and radiation or position measurement, decontamination of assemblies or work space, dismantling of metal or concrete structures and, possibly, treatment and transport of resulting debris. As a result of this study three general purpose robotic systems are proposed in conceptual design form. Most of the technology needed already exists but some further developments in hardware and computer software are suggested for greater efficiency. (U.K.)

  12. Some studies related to decommissioning of nuclear reactors

    International Nuclear Information System (INIS)

    Decommissioning of large nuclear reactors has not yet taken place in the Nordic countries. Small nuclear installations, however, have been dismantled. This NKA-programme has dealt with some interesting and important factors which have to be analysed before a large scale decommissioning programme starts. Prior to decommissioning, knowledge is required regarding the nuclide inventory in various parts of the reactor. Measurements were performed in regions close to the reactor tank and the biological shield. These experimental data are used to verify theoretical calculations. All radioactive waste generated during decommissioning will have to be tansported to a repository. Studies show that in all the Nordic countries there are adequate transport systems with which decommissioning waste can be transported. Another requirement for orderly decommissioning planning is that sufficient information about the plant and its operation history must be available. It appears that if properly handled and sorted, all such information can be extracted from existing documentation. (authors)

  13. Reutilization potential of accelerator components: a decommissioning perspective

    International Nuclear Information System (INIS)

    At decommissioning, some accelerators leave a legacy of low-level induced radioactivity in massive components. Although guidelines for acceptable surface contamination levels for release of materials and equipment to the general public do exist, there are presently no standards for release of materials and equipment with radioactivity distributed throughout their volumes. The decommissionings of five AEC-funded accelerators were examined. One common feature of these decommissionings was that major components usually were assigned and shipped for use or storage at other accelerator laboratories. In addition to reviewing selected past decommissionings, the authors also examined various aspects of decommissioning accelerators presently operating. The estimated cost ($ 1978) of decommissioning ranges from $8.8 x 104 for an electron linac to $7.0 x 106 for the ZGS

  14. Study on archive management for nuclear facility decommissioning projects

    International Nuclear Information System (INIS)

    This paper introduces the main features and status of the archive management for nuclear facility decommissioning projects, and explores and discusses the countermeasures in its archive management. Taking the practice of the archive management system of a reactor decommissioning project as an example, the paper illustrates the establishment of archive management system for the nuclear facility decommissioning projects. The results show that the development of a systematic archive management principle and system for nuclear decommissioning projects and the construction of project archives for the whole process from the design to the decommissioning by digitalized archive management system are one effective route to improve the complete, accurate and systematic archiving of project documents, to promote the standardization and effectiveness of the archive management and to ensure the traceability of the nuclear facility decommissioning projects. (authors)

  15. The U.S. Nuclear Regulatory Commission's decommissioning process

    International Nuclear Information System (INIS)

    The term 'Decommission' is defined in the U.S.. Nuclear Regulatory Commission's (USNRC's) regulations at 10 CFR 20.1003 as to remove a facility or site safely from service and reduce residual radioactivity to a level that permits 1) release of the property for unrestricted use and termination of the license; or, 2) release of the property under restricted conditions and the termination of the license. USNRC's decommissioning program encompasses the decommissioning of all NRC licensed facilities, ranging from routine license terminations for sealed source users, to the oversight of complex sites and those on the Site Decommissioning Management Plan (SDMP), as well as power and non-power reactors. This paper describes the USNRC's decommissioning process for materials and reactor facilities and presents an overview of USNRC's decommissioning program activities. (author)

  16. Research reactor back-end options - decommissioning: a necessary consideration

    International Nuclear Information System (INIS)

    Decommissioning is a challenge, which all radioactive site licensees eventually need to face and research reactors are no exception. BNFL has completed numerous major decommissioning projects at its own operational sites and has undertaken similar works at customers' sites including the decommissioning of the Universities Research Reactor (URR), Risley and the ICI TRIGA 1-Mk I Reactor at Billingham. Based on the execution of such projects BNFL has gained an understanding of the variety of customer requirements and the effectiveness of specific decommissioning techniques for research reactors. This paper addresses factors to be considered when reviewing the way forward following shut down and how these affect the final decisions for fuel management and the extent of decommissioning. Case studies are described from BNFL's recent experience decommissioning both the URR and ICI TRIGA reactors. (author)

  17. CEA experimental feedback on sodium loop decommissioning

    International Nuclear Information System (INIS)

    The aim of this paper is to present experimental feedback on sodium loop dismantling techniques at the CEA (The French Atomic Energy Commission) and to offer recommendations for the decommissioning of Fast Reactor secondary sodium loops. This study is based on acquired CEA decommissioning experience which primarily concerns the following: the decommissioning of RAPSODIE (France's first Fast Reactor), the PHENIX reactor secondary loop replacement, the sodium loop decommissioning carried out by the Laboratory of Sodium Technologies and Treatment, and several technical documents. This paper deals with the main results of this survey. First, a comparison of 8 pipe-cutting techniques is made, taking into account speed in cutting, reliability, dissemination, fire risk due to the presence of sodium, cutting depth, and different types of waste (empty pipes, sodium-filled pipes, tanks...). This comparison has led us to recommend the use of an alternative saw or a chain saw rather than the use of the plasma torch or grinder. Different techniques are recommended depending on if they are on-site, initial cuttings or if they are to be carried out in a specially-designed facility referred to hereafter as 'the cutting building'. After the cutting stage, the sodium waste must be processed with water to become an ultimate stable waste. Four treatment processes are compared with different standards : speed, cost, low activity adaptability and 'large sodium quantity' adaptability. Recommendations are also made for reliable storage, and for the general dismantling system organization. Last, calculations are presented concerning a complete dismantling facility prototype capable of treating large amounts and volume of sodium wastes. (author)

  18. Technology development for decontamination and decommissioning

    International Nuclear Information System (INIS)

    This paper describes the program being developed by the Morgantown Energy Technology Center for the U.S. Department of Energy Office of Technology Development to implement the Decontamination and Decommissioning Focus Area Program. Background information, basic operating principles, and the goals of large-scale demonstration projects are outlined. Ongoing and planned technology development areas for deactivation, decontamination, dismantlement, and disposition and recycle are listed

  19. Decontamination and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Since 1973, when the IAEA first introduced the subject of decontamination and decommissioning into its programme, twelve Agency reports reflecting the needs of the Member States on these topics have been published. These reports summarize the work done by various Technical Committees, Advisory Groups, and International Symposia. While the basic technology to accomplish decontamination and decommissioning (D and D) is fairly well developed, the Agency feels that a more rapid exchange of information and co-ordination of work are required to foster technology, reduce duplication of effort, and provide useful results for Member States planning D and D activities. Although the Agency's limited financial resources do not make possible direct support of every research work in this field, the IAEA Co-ordinated Research Programme (CRP) creates a forum for outstanding workers from different Member States brought into closer contact with one another to provide for more effective interaction and, perhaps subsequently, closer collaboration. The first IAEA Co-ordinated Research Programme (CRP) on decontamination and decommissioning was initiated in 1984. Nineteen experts from 11 Member States and two international organizations (CEC, OECD/NEA) took part in the three Research Co-ordination Meetings (RCM) during 1984-87. The final RCM took place in Pittsburgh, USA, in conjunction with the 1987 International Decommissioning Symposium (sponsored by the US DOE and organized in co-operation with the IAEA and OECD/NEA). The present document summarizes the salient features and achievements of the co-ordinated research work performed during the 1984-87 programme period. The document consists of two parts: Part 1, Summary of the three research co-ordination meetings and Part 2, Final submissions by participants on the research work performed during 1984-1987. A separate abstract was prepared for each of the 7 reports presented. Refs, figs and tabs

  20. Workshop 3: Retrospective Dosimetry and Decommissioning Data

    Science.gov (United States)

    Serén, Tom; Fero, Arnold

    2009-08-01

    The workshop had 27 participants. There was an initial discussion of the current status and use of retrospective dosimetry techniques. There was a consensus that this had become a wide-spread and useful technique. The applications have ranged from the well known characterization of reactor vessel neutron exposure to the assessment of the age of metal specimens removed from reactor internals to concrete trepans from concrete shields in a decommissioning context...

  1. Experimental feedback on sodium loop decommissioning

    International Nuclear Information System (INIS)

    The aim of this paper is to present experimental feedback on sodium loop dismantling techniques at the CEA (The French Atomic Energy Commission) and to offer recommendations for the decommissioning of Fast Reactor secondary sodium loops. This study is based on acquired CEA decommissioning experience which primarily concerns the following: the decommissioning of RAPSODIE (France's first Fast Reactor), the Phenix reactor secondary loop replacement, the sodium loop decommissioning carried out by the Laboratory of Sodium Technologies and Treatment, and several technical documents. This paper deals with the main results of this survey. First, a comparison of 8 pipe-cutting techniques is made, taking into account speed in cutting, reliability, dissemination, fire risk due to the presence of sodium, cutting depth, and different types of waste (empty pipes, sodium-filled pipes, tanks). This comparison has led us to recommend the use of an alternative saw or a chain saw rather than the use of the plasma torch or grinder. Different techniques are recommended depending on if they are on-site, initial cuttings or if they are to be carried out in a specially-designed facility referred to hereafter as 'the cutting building'. After the cutting stage, the sodium waste must be processed with water to become an ultimate stable waste. Four treatment processes are compared with different standards: speed, cost, low activity adaptability and 'large sodium quantity' adaptability. Recommendations are also made for reliable storage, and for the general dismantling system organization. Last, calculations are presented concerning a complete dismantling facility prototype capable of treating large amounts and volume of sodium wastes. (author)

  2. Decommissioning the N.S. Otto Hahn

    International Nuclear Information System (INIS)

    After more than ten years of troublefree operation the German commercial nuclear vessel N.S. Otto Hahn was decommissioned in Februar 1979 following the burnup of its second core, because the scientific results expected from another four years of operation with a third core would no longer have justified the financial expenditure. The activated components of the reactor will now be dismantled and removed, the other systems decontaminated; in this way the ship can subsequently be used for conventional operation. (orig.)

  3. Optimization of electrodecontamination processes for decommissioning

    International Nuclear Information System (INIS)

    In the frame of the ENEL-CISE R and D activities in the decommissioning field, electrodecontamination testing in various electrolytes have been performed, in order to obtain the unrestricted release of both stainless steel and carbon steel materials. Results show that an optimum process configuration has been determined for the electrodecontamination of stainless steel in a HNO3 bath and of carbon steel in a HCOOH 8% + HF 1.5% bath. (author)

  4. Potential use of near infrared spectroscopy for the on-line prediction of fatty acid composition in Limousin and Aberdeen Angus beef samples

    OpenAIRE

    Prieto, Nuria; Ross, D. W.; Navajas, E. A.; Richardson, R. I.; Hyslop, J. J.; Simm, G; Roehe, R.

    2009-01-01

    The objective of this study was to test the on-line estimation of the concentration of individual fatty acids (FA) and groups of FA in crossbred Limousin (LIM) and Aberdeen Angus (AA) beef samples using NIR spectroscopy (NIRS), immediately after exposing the meat surface in the abattoir at 48 h post mortem. Samples from 106 LIM and 88 AA M. longissimus thoracis were scanned over the NIR spectral range from 1100-1800 nm and samples of the M. longissimus lumborum w...

  5. Lumbar Disc Screening Using Back Pain Questionnaires: Oswestry Low Back Pain Score, Aberdeen Low Back Pain Scale, and Acute Low Back Pain Screening Questionnaire

    OpenAIRE

    Kim, Do Yeon; Oh, Chang Hyun; Yoon, Seung Hwan; Park, Hyung Chun; Park, Chong Oon

    2012-01-01

    Objective To evaluate the usefulness of back pain questionnaires for lumbar disc screening among Korean young males. Methods We carried out a survey for lumbar disc screening through back pain questionnaires among the volunteers with or without back pain. Three types of back pain questionnaire (Oswestry Low Back Pain Score, Aberdeen Low Back Pain Scale, and Acute Low Back Pain Screeing Questionnaire) were randomly assigned to the examinees. The authors reviewed lumbar imaging studies (simple ...

  6. Decommissioning project of commercial nuclear power plant

    International Nuclear Information System (INIS)

    Decommissioning project of commercial nuclear power plant in Japan was outlined. It is expected that the land, after the decommissioning of commercial nuclear power plants, will serve as sites for new plants. Steps will be taken to reduce the amount of wastes generated and to recycle/reuse them. Wastes with a radioactivity concentration below the 'clearance level' need not be dealt with as radioactive material, and may be handled in the same way as conventional wastes. The Tokai-1 power station, a 166 MWe carbon dioxide cooled reactor which closed down in 1998, is being decommissioned and the first ten years as 'safe storage' to allow radioactivity to decay. Non-reactor grade components such as turbines were already removed, heat exchanger dismantling started and the reactor will be dismantled, the buildings demolished and the site left ready for reuse. All radioactive wastes will be classified as low-level wastes in three categories and will be buried under the ground. The total cost will be 88.5 billion yen -34.7 billion for dismantling and 53.8 billion for waste treatment including the graphite moderator. (T. Tanaka)

  7. The use of managing agencies in decommissioning

    International Nuclear Information System (INIS)

    On 1 April 1994 UKAEA Government Division was formed and one of its main responsibilities is the safe and cost effective management of the facilities which have already closed and the fuel reprocessing and radioactive waste management plant required to assist in the current programme of decommissioning. UKAEA Government Division, working on behalf of DTI, is intended to be a lean and efficient programme management and procurement organisation. Rather than build up its own project management capability it intends to use external resources for this function, obtained in future by competitive tendering. For each major facility undergoing decommissioning a Managing Agency has been, or will be, appointed to act on behalf of UKAEA Government Division. The responsibilities of each Managing Agency will be to assist in the definition of tasks, the commissioning of option studies and safety studies, the specification of individual contracts, management of the tendering processes and the subsequent management of the Implementation Contractors carrying out the decommissioning work, including the associated safety and training responsibilities. Teams involved in Managing Agency work require skills in project management, relevant technical issues, contract and safety management. (author)

  8. Governments' role in decommissioning nuclear power facilities

    International Nuclear Information System (INIS)

    Many nuclear power plants will reach the end of their operating lives over the next 20 years; some may be life-extended, others may not. This development will precipitate enhanced industrial and regulatory activities in the area of decommissioning. We are also witnessing in many countries a significant shift in the role of government itself: new pressures on governments, such as enhanced attention on environmental impact/mitigation and strategies to implement market-oriented approaches in a variety of sectors, including the energy sector are driving the public policy agenda. The paper will examine the range of policy issues, drawing from recent NEA studies on decommissioning policies and the recent NEA study on Government and Nuclear Energy and, strategies and costs, and other current trends and developments in the nuclear industry and in the nuclear policy fields. The paper will reflect on issues to be addressed during the conference and draw conclusions on the appropriate role of government in this area. Decommissioning policy is very specific and focused: it is not a high level policy/political issue in most instances and rarely gets the same attention as the issue surrounding the future of nuclear energy itself and public concerns regarding safety, waste and economics. One reason why decommissioning does not get the same attention as for example disposal of spent nuclear fuel might be the fact that technology is available for decommissioning, while technology for disposal of spent nuclear fuel is under development. High profile or not, it will remain an important issue for governments and industry alike particularly because of the cost and long lead times involved. In some instances, governments are the owners of the facilities to be decommissioned. In addition, decommissioning factors into issues surrounding the economics of nuclear energy and the sustainability of the nuclear option. Based on results of the Tarragona Seminar (Spain, September 2-4, 2003) and the Rome Workshop, we conclude that, with respect to power production facilities, government policy should aim at securing funding, whatever system is practically chosen, so that the actual beneficiary from the power generated - and not the future taxpayer -pays for all the production costs, including future decommissioning. There are very good ethical reasons behind a system which ensures that the generations that consume this electricity do not leave such an economic burden to their grandchildren. This is also one of the principles that are expressed in the 1999 Joint Convention. The most practical way to ensure that such economic burdens do not crop up at a later stage is probably to create some sort of funding mechanism. Such funding can be organised in different ways according to different conditions in different countries. Generally speaking, to ensure an effective funding mechanism, there has to be national legislation on how such a mechanism should be constructed. Different systems with governmental institutions more or less involved are possible. But any funding system, aiming at providing economic resources for decommissioning in a foreseeable future should meet the following requirements. Stable legal framework: the legislation regarding funding should have high profile among legislators to ensure that political pressures do not lead to decisions to change the legislation in order to allow assets to be used for other urgent purposes. Legal rules must ensure that funds collected for this purpose cannot disappear as a consequence of bankruptcy of an owner of a nuclear facility that needs to be decommissioned. Calculations of future costs have to meet high accuracy standards. This means that appropriate discount factors will have to be applied to ensure that the time frames when costs will be incurred will be factored into the costing formulae. One possible way to achieve high accuracy is to require regular and frequent reviews of all calculations. It is essential that mechanisms are in place to ensure that the real value of assets in the fund guard against periods of high inflation. Last but not least, competent administration of the funding system is of paramount importance. To conclude, the cost of decommissioning is an important criterion in deregulated markets where competition calls for a lowering of costs of producing electricity. In this regard, the NEA Study on the Role of Government concluded that one duty of government is to ensure that funds will be available to carry out decommissioning for facilities that may not close for a century or more. This may require fairly sophisticated financial management of billion dollar sums of money and ongoing attention of national governments. Enhanced dialogue at the international level will be particularly beneficial to governments, regulatory bodies and industry

  9. P2 integration into conduct of decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Boing, L.E.; Lindley, R.

    1997-08-01

    Over the last five years, the D and D Program at the ANL-East site has completed decommissioning of three facilities. Currently, decommissioning of two facilities continues at the site with completion of the JANUS Reactor scheduled for September 1997 and completion of the CP-5 Reactor scheduled for late in CY 1999. In the course of this work, certain waste minimization pollution prevention (WMin/P2) activities have been integrated into all these projects. In most cases, the P2 aspects were key components of the operations that made the best use of available project resources to complete the work safely, within the budget and on or ahead of schedule. This paper will highlight those WMin/P2 activities found most suitable for these D and D operations. Activities covered will include: re-use of lead bricks from a research reactor for shielding material at an accelerator facility, re-use of a reactor out building structure by the on-site plant services group, and several other smaller scope activities which have also helped heighten WMin/P2 awareness in decommissioning.

  10. Decommissioning of the Salaspils Research Reactor

    Directory of Open Access Journals (Sweden)

    Abramenkovs Andris

    2011-01-01

    Full Text Available In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor and to dispense with nuclear energy in the future. The reactor has been out of operation since July 1998. A conceptual study on the decommissioning of the Salaspils Research Reactor was drawn up by Noell-KRC-Energie- und Umwelttechnik GmbH in 1998-1999. On October 26th, 1999, the Latvian government decided to start the direct dismantling to “green-field” in 2001. The upgrading of the decommissioning and dismantling plan was carried out from 2003-2004, resulting in a change of the primary goal of decommissioning. Collecting and conditioning of “historical” radioactive wastes from different storages outside and inside the reactor hall became the primary goal. All radioactive materials (more than 96 tons were conditioned for disposal in concrete containers at the radioactive wastes depository “Radons” at the Baldone site. Protective and radiation measurement equipment of the personnel was upgraded significantly. All non-radioactive equipment and materials outside the reactor buildings were released for clearance and dismantled for reuse or conventional disposal. Contaminated materials from the reactor hall were collected and removed for clearance measurements on a weekly basis.

  11. Decommissioning Cost Estimating -The ''Price'' Approach

    International Nuclear Information System (INIS)

    Over the past 9 years UKAEA has developed a formalized approach to decommissioning cost estimating. The estimating methodology and computer-based application are known collectively as the PRICE system. At the heart of the system is a database (the knowledge base) which holds resource demand data on a comprehensive range of decommissioning activities. This data is used in conjunction with project specific information (the quantities of specific components) to produce decommissioning cost estimates. PRICE is a dynamic cost-estimating tool, which can satisfy both strategic planning and project management needs. With a relatively limited analysis a basic PRICE estimate can be produced and used for the purposes of strategic planning. This same estimate can be enhanced and improved, primarily by the improvement of detail, to support sanction expenditure proposals, and also as a tender assessment and project management tool. The paper will: describe the principles of the PRICE estimating system; report on the experiences of applying the system to a wide range of projects from contaminated car parks to nuclear reactors; provide information on the performance of the system in relation to historic estimates, tender bids, and outturn costs

  12. Large transport packages for decommissioning waste

    International Nuclear Information System (INIS)

    The main tasks performed during the period related to the influence of manufacture, transport and disposal on the design of such packages. It is deduced that decommissioning wastes will be transported under the IAEA Transport Regulations under either the Type B or Low Specific Activity (LSA) categories. If the LSA packages are self-shielded, reinforced concrete is the preferred material of construction. But the high cost of disposal implies that there is a strong reason to investigate the use of returnable shields for LSA packages and in such cases they are likely to be made of ferrous metal. Economic considerations favour the use of spheroidal graphite cast iron for this purpose. Transport operating hazards have been investigated using a mixture of desk studies, routes surveys and operations data from the railway organisations. Reference routes were chosen in the Federal Republic of Germany, France and the United Kingdom. This work has led to a description of ten accident scenarios and an evaluation of the associated accident probabilities. The effect of disposal on design of packages has been assessed in terms of the radiological impact of decommissioning wastes, an in addition corrosion and gas evolution have been examined. The inventory of radionuclides in a decommissioning waste package has low environmental impact. If metal clad reinforced concrete packages are to be used, the amount of gas evolution is such that a vent would need to be included in the design. Similar unclad packages would be sufficiently permeable to gases to prevent a pressure build-up. (author)

  13. Lessons learned on stakeholder issues in decommissioning

    International Nuclear Information System (INIS)

    Issues of public concern during decommissioning and dismantling (D and D) are partly the same and partly different from those of the preceding phases (planning, construction and operation). While in the course of construction and operation the main challenges include meeting expectations of a higher quality of life, accommodating a growing population, mitigating construction nuisances, and assuring the safe operation of the facility, the main concerns in the D and D phase are decreasing employment rate, the eventual reduction of revenues for the municipality, the future use of the affected land and negative social impacts (e.g., out-migration). The decommissioning phase is characterised by heterogeneity of stakeholder interests and values, difficulties of reaching consensus or compromise, and difficulties in connection with the harmonization of energy production, environmental protection and sustainable socio-economic development considerations. Typically, there might also be tensions between local and regional decisions. As in other phases, the building of trust between stakeholder is crucial from the point of view of conflict management, and social lessons learnt from the siting and developments of nuclear facilities are widely applicable in the field of D and D as well. A review is presented of major lessons to be learnt from NEA activities in the field of decommissioning and stakeholder involvement. (author)

  14. Lessons learned on stakeholder issues in decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    O' Sullivan, P.; Pescatore, C. [OECD Nuclear Energy Agency, 92 - Issy les Moulineaux (France)

    2008-07-01

    Issues of public concern during decommissioning and dismantling (D and D) are partly the same and partly different from those of the preceding phases (planning, construction and operation). While in the course of construction and operation the main challenges include meeting expectations of a higher quality of life, accommodating a growing population, mitigating construction nuisances, and assuring the safe operation of the facility, the main concerns in the D and D phase are decreasing employment rate, the eventual reduction of revenues for the municipality, the future use of the affected land and negative social impacts (e.g., out-migration). The decommissioning phase is characterised by heterogeneity of stakeholder interests and values, difficulties of reaching consensus or compromise, and difficulties in connection with the harmonization of energy production, environmental protection and sustainable socio-economic development considerations. Typically, there might also be tensions between local and regional decisions. As in other phases, the building of trust between stakeholder is crucial from the point of view of conflict management, and social lessons learnt from the siting and developments of nuclear facilities are widely applicable in the field of D and D as well. A review is presented of major lessons to be learnt from NEA activities in the field of decommissioning and stakeholder involvement. (author)

  15. Decommissioning strategies for facilities using radioactive material

    International Nuclear Information System (INIS)

    The planning for the decommissioning of facilities that have used radioactive material is similar in many respects to other typical engineering projects. However, decommissioning differs because it involves equipment and materials that are radioactive and therefore have to be handled and controlled appropriately. The project management principles are the same. As with all engineering projects, the desired end state of the project must be known before the work begins and there are a number of strategies that can be used to reach this end state. The selection of the appropriate strategy to be used to decommission a facility can vary depending on a number of factors. No two facilities are exactly the same and their locations and conditions can result in different strategies being considered acceptable. The factors that are considered cover a wide range of topics from purely technical issues to social and economic issues. Each factor alone may not have a substantial impact on which strategy to select, but their combination could lead to the selection of the preferred or best strategy for a particular facility. This Safety Report identifies the factors that are normally considered when deciding on the most appropriate strategy to select for a particular facility. It describes the impact that each factor can have on the strategy selection and also how the factors in combination can be used to select an optimum strategy

  16. Investment management for nuclear decommissioning trusts

    International Nuclear Information System (INIS)

    According to Nuclear Regulatory Commission estimates, and assuming a 4 percent annual inflation rate, minimum decommissioning requirements for a single reactor could total almost $350 million after 30 years. Consequently, reducing customer contributions to decommissioning funds is a potentially rewarding activity. In fact, improving the after-tax return earned on an NDT fund by as little as one percentage point can reduce customer contributions to the fund by 15% over its life. Unfortunately, many electric utilities are headed in the wrong direction and are unlikely to achieve satisfactory results. The main problem is the prevalence of the conventional wisdom, most of which has been appropriated from the area of pension fund management. This is an area which is familiar to most utility managements, but which has only superficial similarity to the issue of NDT investing. The differences are pronounced: NDTs, unlike pensions, are fully taxable at corporate income tax rates. In addition, NDT managers should be concerned with protecting the inflation-adjusted or real value of fund investments at a single, future decommissioning date. Pension managers, on the other hand, may be concerned with satisfying nominal contractual obligations spread over an extended future time horizon. In view of the large stakes involved in the management of NDTs, the authors summarize five key tenets of the conventional wisdom in this area and demonstrate where they feel they are in error

  17. Decommissioning U.K. power stations

    International Nuclear Information System (INIS)

    The strategy for decommissioning U.K. commercial nuclear power stations at the end of their operating lives has hitherto been based on early partial dismantling and clearance to green-field site after about 100 years. This strategy involves a considerable financial liability particularly in the early years following shutdown of the stations. In 1990 Nuclear Electric identified the potential for significantly reducing this liability by reviewing a range of alternative strategies for decommissioning. This review has now been completed by Nuclear Electric and this paper describes the background to it, the review itself and the conclusions. As a result Nuclear Electric are now proposing to adopt a new strategy, referred to as the ''Deferred Safestore strategy'' for all its gas-cooled power stations. This does not involve any significant active dismantling until about 135 years after shutdown, allowing radioactivity levels in the plant to decay to very low levels in-situ. Following defuelling, an initial care and maintenance phase of about 30 years occurs followed by construction of containments (Safestores) around all buildings containing active plant. The purpose of these is to protect the buildings and their contents from deterioration due to weathering for a further 100 years. Complete dismantling is carried out after that time. An alternative option at that time, with further considerable cost savings, could be In-situ decommissioning. (Author)

  18. Decommissioning nuclear power plants - the wave of the future

    International Nuclear Information System (INIS)

    The paper discusses the project controls developed in the decommissioning of a nuclear power plant. Considerations are given to the contaminated piping and equipment that have to be removed and the spent and used fuel that has to be disposed of. The storage issue is of primary concern here. The cost control aspects and the dynamics of decommissioning are discussed. The effects of decommissioning laws on the construction and engineering firms are mentioned. 5 refs

  19. North Sea decommissioning : valuing the options: OIES paper: EE21

    OpenAIRE

    Roberts, Tracy; Mitchell , John

    1997-01-01

    This paper develops a model of the decision to decommission an oil platform offshore the UK, using elementary options valuation It contrasts the choice of decommissioning date under expected or certain-equivalent value with the dates that would be optimal if options values for continuing production were developed with respect to uncertain prices, decommissioning costs, fixed operating costs, and quantities. The problem of combining uncertain parameters is discussed and the effe...

  20. The Northern Ireland peace process and the impact of decommissioning

    OpenAIRE

    De Chastelain, John

    2001-01-01

    This paper examines the impact that the decommissioning of paramilitary arms has had, and continues to have, on the Northern Ireland peace process. It selects the beginning of the paramilitary group ceasefires in 1994 as the beginning of that pro-cess, and examines how decommissioning has affected progress in it up to the present date. It looks at the involvement of the Independent Body, the International Chairmen and the Independent International Commission on Decommissioning throughout the ...

  1. Initial decommissioning planning for the Budapest research reactor

    Directory of Open Access Journals (Sweden)

    Toth Gabor

    2011-01-01

    Full Text Available The Budapest Research Reactor is the first nuclear research facility in Hungary. The reactor is to remain in operation for at least another 13 years. At the same time, the development of a decommissioning plan is a mandatory requirement under national legislation. The present paper describes the current status of decommissioning planning which is aimed at a timely preparation for the forthcoming decommissioning of the reactor.

  2. Initial decommissioning planning for the Budapest research reactor

    OpenAIRE

    Toth Gabor

    2011-01-01

    The Budapest Research Reactor is the first nuclear research facility in Hungary. The reactor is to remain in operation for at least another 13 years. At the same time, the development of a decommissioning plan is a mandatory requirement under national legislation. The present paper describes the current status of decommissioning planning which is aimed at a timely preparation for the forthcoming decommissioning of the reactor.

  3. Administrative requirements of financial securities to cover decommissioning operations

    International Nuclear Information System (INIS)

    This paper points out that the lack of experience in decommissioning of nuclear power plants is reflected by the absence of specific legislation regarding the economic, fiscal and accounting aspects of the process. The author suggests that a fund be created for decommissioning costs through contributions deriving from plant operation. The paper analyses the procedures to be followed and draws attention to the need for clear legislation on decommissioning. (NEA)

  4. Unrestricted re-use of decommissioned nuclear laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Cornelissen, R.; Noynaert, L.; Harnie, S.; Marien, J.

    1996-09-18

    A decommissioning strategy was developed by the Belgian Nuclear Research Centre SCK/CEN. In this strategy decommissioning works are limited to the radioactive parts of the nuclear installation. After obtaining an attestation for unrestricted reuse of the building after removal of all radioactivity, the building can be used for new industrial purposes outside the nuclear field. The decommissioning activities according to this strategy have been applied in four buildings. The results are described.

  5. Training practices to support decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Adequate numbers of competent personnel must be available during any phase of a nuclear facility life cycle, including the decommissioning phase. While a significant amount of attention has been focused on the technical aspects of decommissioning and many publications have been developed to address technical aspects, human resource management issues, particularly the training and qualification of decommissioning personnel, are becoming more paramount with the growing number of nuclear facilities of all types that are reaching or approaching the decommissioning phase. One of the keys to success is the training of the various personnel involved in decommissioning in order to develop the necessary knowledge and skills required for specific decommissioning tasks. The operating organisations of nuclear facilities normally possess limited expertise in decommissioning and consequently rely on a number of specialized organisations and companies that provide the services related to the decommissioning activities. Because of this there is a need to address the issue of assisting the operating organisations in the development and implementation of human resource management policies and training programmes for the facility personnel and contractor personnel involved in various phases of decommissioning activities. The lessons learned in the field of ensuring personnel competence are discussed in the paper (on the basis of information and experiences accumulated from various countries and organizations, particularly, through relevant IAEA activities). Particularly, the following aspects are addressed: transition of training from operational to decommissioning phase; knowledge management; target groups, training needs analysis, and application of a systematic approach to training (SAT); content of training for decommissioning management and professional staff, and for decommissioning workers; selection and training of instructors; training facilities and tools; and training as the integral part of management of human resources. (author)

  6. Heterose sobre os pesos de bovinos Canchim e Aberdeen Angus e de seus cruzamentos recíprocos Heterosis upon weights in Canchim and Aberdeen Angus calves and in their reciprocal crosses

    Directory of Open Access Journals (Sweden)

    DANIEL PEROTTO

    2000-12-01

    Full Text Available O trabalho foi conduzido para estimar a heterose sobre os pesos ao nascimento (PNT, à desmama (P210 e ao ano (P365 e sobre os ganhos de pesos médios diários do nascimento à desmama (G210 e da desmama ao ano (G365 nas quatro primeiras gerações do sistema de cruzamentos alternados entre as raças Canchim (C e Aberdeen Angus (A. Os dados de 1.147 bezerros nascidos de 1981 a 1998 foram analisados pelo método dos mínimos quadrados, ajustando-se um modelo linear que incluiu os efeitos linear e quadrático da idade da mãe do bezerro e os efeitos fixos de sexo, grupo genético, mês e ano de nascimento do bezerro. Estimativas de heterose e de outras diferenças genéticas foram estimadas por contrastes entre médias e testadas pelo teste t. O contraste "CA" foi positivo e significativo (PThe study was conducted to estimate heterosis upon birth weight (PNT, weaning weight (P210, yearling weight (P365 and daily weight gain from birth to weaning (G210 and from weaning to one year of age (G365 in the first, second, third and fourth generations of a rotational crossbreeding system between Canchim (C and Aberdeen Angus (A. Data from 1,147 calves born from 1981 to 1998 were analyzed by least squares procedures fitting a linear model that included the linear and the quadratic effects of age of the dam of the calf plus the fixed effects of sex, genetic group, month and year of birth of calf. Estimates of heterosis and of other genetic differences were obtained by linear contrasts of appropriate means and tested by the t test. The contrast CA was positive and significant (P<0.001 for all five traits. The contrast F1CAF1AC was negative and highly significant (P<0.001 for P210 and for G210 and significant (P<0.05 for P365. The F1 generation exhibited heterosis of 4.8% for P210 and of 4.9% for G210. Maternal heterosis was 3.7%, 5.8%, 6.3% and 20.4%, respectively, for P210, G210, P365 and G365. The heterosis estimated for the mean of the third and fourth generations of the rotational crossbreeding system between C and A was 4.6% for P210, 5.3% for G210 and 3.5% for P365.

  7. Fatores de correção para perímetro escrotal ao sobreano para tourinhos mestiços Aberdeen Angus x Nelore Adjustment factors for scrotal circumference at yearling for crossbred Aberdeen Angus x Nelore young bulls

    Directory of Open Access Journals (Sweden)

    J.S. Lopes

    2009-04-01

    Full Text Available Obtiveram-se fatores de correção (FC para o perímetro escrotal ao sobreano (PES para os efeitos de grupo genético (GG, heterozigose individual (HI, peso ao sobreano (PS e idade do animal à pesagem de sobreano (IDS, utilizando-se registros de peso corporal e medidas de perímetro escrotal obtidos de 11.662 tourinhos das raças Aberdeen Angus, Nelore e de produtos do cruzamento entre elas, criados nas regiões Sul, Sudeste e Centro-Oeste do Brasil, nascidos entre 1987 e 2001. Os coeficientes de regressão que geraram os FC foram estimados pelo método dos quadrados mínimos, adotando um modelo que incluiu os efeitos de grupo de contemporâneos ao sobreano (GC, GG, heterozigose materna (HM, HI, PS e IDS. Todos os efeitos incluídos no modelo foram significativos (PAdjustment factors (AF for scrotal circumference at yearling (SCY were figured out for effects of genetic group (GG, individual heterozygosis (IH, yearling weight (YW, and age of the animal at yearling weight (AYW using body weight and scrotal circumference records from 11,662 Aberdeen Angus, Nelore, and their crosses. The animals were born from 1987 to 2001 and were raised in the South East and Central West Regions of Brazil. The regression coefficients to obtain AF were estimated by least squares means method. The model included the fixed effects of contemporaneous group at yearling (CG, maternal heterozygosis (MH, IH, and the covariates YW (linear and quadratic effects and AYW (linear effect. All the factors included in the model showed significant effects (P<0.01 on SCY. The mean and standard deviation for SCY were 29.90±3.55cm. Quadratic effect of YW on SCY was also observed. Decreases in SCY with the increase in YW was found. High SCY was observed immediately after post-weaning. The YW effects on SCY were 0.06695804±0.00345000cm/kg (linear effect and -0.00005252±0.00000508cm/kg² (quadratic effect. The AYW linear effect on SCY was 0.02176450±0.00038568cm/day. The factors included in the model are important sources of variation to adjust SCY for the selection of young bulls in order to improve sexual precocity.

  8. Conclusions and theses relating to the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Most of the problems encountered in decommissioning are due to deficiencies on the side of the laws. Items of controversy revealed at the meeting are: -content covered by the term decommissioning; - definition of decommissioning stages and their hierarchy in schedule; - subject matter of decommissioning; -interfaces between operation and decommissioning processes; - substantive requirements to be met; - formal requirements to be met. The meaning of the term 'nuclear installation' used in paragraph 7 sub-sec. (3), 1st sentence Atomic Energy Act corresponds to the meaning of the term used in paragraph 7 sub-sec. 1 Atomic Energy Act. However, the licensee is free to proceed with the decommissioning of individual components of an installation that can be disconnected from the safety programme of decommissioning activities. Those measures in the post-shutdown phase under regulatory control under the operating licence or the surveillance programme do not require to be licensed anew. All other measures require a licence for decommissioning ('as far as'). Decommissioning cannot be 'directed' by orders under the surveillance programme. The (unlawful) nuclear power phaseout cannot be imposed on the basis of paragraph 7 sub-sec. 3 Atomic Energy Act. (orig./HSCH)

  9. Computer System Analysis for Decommissioning Management of Nuclear Reactor

    International Nuclear Information System (INIS)

    Nuclear reactor decommissioning is a complex activity that should be planed and implemented carefully. A system based on computer need to be developed to support nuclear reactor decommissioning. Some computer systems have been studied for management of nuclear power reactor. Software system COSMARD and DEXUS that have been developed in Japan and IDMT in Italy used as models for analysis and discussion. Its can be concluded that a computer system for nuclear reactor decommissioning management is quite complex that involved some computer code for radioactive inventory database calculation, calculation module on the stages of decommissioning phase, and spatial data system development for virtual reality. (author)

  10. Radiation protection in connection with the decommissioning of nuclear plants

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    This document presents the SSI preliminary views and position concerning the decommissioning of nuclear plants. To prevent the exposure of the decommissioning personnel and the general public to unacceptable levels of radiation and to protect the environment and future generations, it is SSI`s task to formulate and issue the necessary terms and regulations with which the reactor licensees must comply during the decommissioning work. The views and principles presented here are the basis of SSI`s continued work on guidelines and regulations for the decommissioning of nuclear plants.

  11. Decommissioning of fuel cycle facilities in South Africa

    International Nuclear Information System (INIS)

    Experience gained in South Africa on the decommissioning of uranium conversion, enrichment and fuel fabrication facilities is briefly summarized with emphasis on the lessons learned. The South African Nuclear Energy Corporation (Necsa) has consolidated its nuclear decommissioning and waste management activities at Pelindaba and introduced a comprehensive, all-embracing nuclear liability management approach. The paper describes the experience gained on various aspects of decommissioning and waste management including the social impacts of the decommissioning and waste related activities during the decade from 1995 to 2005. Certain technological difficulties arose during this period and the approaches adopted to resolve these difficulties are also addressed. (author)

  12. SGN's Dismantling and Decommissioning engineering, projects experience and capabilities

    International Nuclear Information System (INIS)

    Its experience in waste treatment, conditioning, storage and disposal, its cooperation with CEA and COGEMA Group in license agreements give SGN expertise in the decommissioning field. SGN's experience and background in all areas of nuclear facility decommissioning, such as chemical and mechanical cells, nuclear advanced reactors, reprocessing facilities result in fruitful references to the customers. The poster is presenting different achievements and projects with SGN's participation such as: - The decommissioning of Windscale Advanced Gas cooled Reactors (WAGR), in particular providing methodology and equipment to dismantle the Pressure and Insulation Vessel of the reactor. - The decommissioning plan of Ignalina (Lithuania) and Paldiski (Estonia), defining strategies, scenarios, necessary equipments and tools and choosing the best solutions to decommission the site under different influencing parameters such as cost, dose rate exposure, etc... - Th One Site Assistance Team (OSAT) at Chernobyl regarding the preparation works for the waste management and decommissioning of the plant. - The decommissioning of French nuclear facilities such as reprocessing (UP1) and reactor (EL4) plants. The important experience acquired during the facility management and during the first dismantling and decommissioning operations is an important factor for the smooth running of these techniques for the future. The challenge to come is to control all the operations, the choice of strategies, the waste management, the efficiency of tools and equipments, and to provide nuclear operators with a full range of proven techniques to optimise costs and minimize decommissioning personnel exposure. (Author)

  13. Decommissioning wind energy projects: An economic and political analysis

    International Nuclear Information System (INIS)

    Wind energy is the fastest-growing segment of new electrical power capacity in the United States, with the potential for significant growth in the future. To facilitate such growth, a number of concerns between developers and landowners must be resolved, including assurance of wind turbine decommissioning at the end of their useful lives. Oklahoma legislators enlisted the authors to develop an economically-sound proposal to ensure developers complete their decommissioning obligations. Economic analysis of turbine decommissioning is complicated by a lack of operational experience, as few U.S. projects have been decommissioned. This leads to a lack of data regarding decommissioning costs. Politically, the negotiation leading to the finally-enacted solution juxtaposed economic theory against political pragmatism, leading to a different but hopefully sound solution. This article will provide background for the decommissioning issue, chronicle the development of the decommissioning component of the Oklahoma Wind Energy Act, and frame issues that remain for policymakers in regulating wind power development. - Highlights: ? Wind energy is the fastest-growing component of U.S. power generation. ? Decommissioning wind projects is policy concern for wind development. ? Little public information on wind turbine decommissioning costs exists. ? Oklahomas solution attempts to account for both costs and risks. ? Additional research is needed to create a more precise policy solution.

  14. Funding nuclear-power-plant decommissioning. Final report

    International Nuclear Information System (INIS)

    The report is organized according to the steps that one might go through when analyzing funding of decommissioning costs. The first step in analyzing decommissioning costs might be to review the present regulatory framework within which decommissioning cost decisions must be made. A description is presented of the present NRC regulations that address the decommissioning of a nuclear power plant. A description is also presented of recent public utility commission activities concerning funding the costs of decommissioning. Possible future trends in NRC regulation are also discussed. The estimation of decommmissioning costs is analyzed. A description of each of the possible decommissoining options is presented. The options of decommissioning include immediate dismantlement, various types of safe storage, and entombment. A discussion is presented of cost estimations for each decommissioning option for nuclear units containing pressurized water reactors and boiling water reactors. A description is included of the various methods of collecting funds for decommissioning as well as a discussion of their possible regulatory treatment. Material is presented which will provide the reader with background information that might assist state utility commissioners or their staffs in choosing or evaluating one of the financial mechanisms for covering decommissioning costs

  15. The decommissioning program of JAERI's Reprocessing Test Facility

    International Nuclear Information System (INIS)

    Decommissioning program of JAERI's Reprocessing Test Facility (JRTF) has been carried out to establish decommissioning techniques for nuclear fuel facilities. The project consists of 2 phases ; phase 1 is preparatory stage of decommissioning project, and phase 2 is execution stage of the JRTF decommissioning. The project started in 1990 under a contract with the Science and Technology Agency, and will be finished in 2001. Up to now, treatment of some radioactive liquid waste and physical inventory estimation were carried out. In addition to the technical development for dismantling, the design for treatment of the unpurified uranium solution and high level liquid waste are in progress steadily. (author)

  16. Planning for safe decommissioning of research reactors in Egypt

    International Nuclear Information System (INIS)

    Egypt operates two Research Reactors: ETRR-1: Tank type, 2 MW power, 10% enrichment EK-10 fuel, and commissioned in 1960 and ETRR-2: Open pool type, 22 MW power, 20% enrichment plate type fuel and commissioned in 1997. A proposed decommissioning plan for each reactor will be presented. The established decommissioning plan includes facility characterization, procedures and radiological protection aspects. The safety assessment during the decommissioning identifies the actions that are necessary to ensure continuous safety during all phases of decommissioning. Protective measures should provide the necessary defense in depth. (author)

  17. Use of data processing tools in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    With the present level of electronic data processing technology, no project of the scale of nuclear reactor decommissioning could be carried out without the use of data processing systems. On the contrary, a reactor decommissioning project requires essential support not only for the technical but also the economic side through the use of proper data processing programs, and not only general applications in the area of personal computers such as MS-EXCEL or MS Project, but also special data processing systems designed for the reactor decommissioning tasks. Various data processing supports are required depending upon the progress of a reactor decommissioning project. (orig./DG)

  18. EC decommissioning information network (EC-DB-NET2)

    International Nuclear Information System (INIS)

    The EC Decommissioning Information Network is the platform to effectively share the achievements, techniques and principles that have been developed under previous and the current EC programmes and also the knowledge drawn from practical decommissioning projects. The strategic tools of the EC-DB-NET2 project are first the database on technical and cost aspects on decommissioning of nuclear installations which is a consequent enhancement of the former databases EC-DB-COST and EC-DB-TOOL and second the EC Decommissioning Web Site being an essential part of this network. (authors)

  19. Radiological characterisation and decommissioning in Denmark

    International Nuclear Information System (INIS)

    Danish Decommissioning (DD) is currently decommissioning the last Danish research reactor (DR3) and the Hot Cell facility. The DR3 project will soon finish dismantling of the external parts of the reactor (January 2012). The approval for dismantling of neutron activated and tritium contaminated heavy water pumps and tubing was granted in December 2011. DD will begin the work on the inner parts as the tendering process for equipment will start in 2012. Hereafter the dismantling of the top of the reactor will begin using the obtained remote controlled equipment. The Hot Cell facility consists of 6 contaminated cells. The first cell have been opened and cleaned. Currently the work progresses by removing parts and hot spots from the other cells with the use of robotic equipment. Challenges, lack of conventional and radiological documentation, dose rates and contamination higher than expected and the confined space in the cells have delayed the project. No final repository exists in Denmark. Therefore no official Waste Acceptance Criteria (WAC) have been formulated. However the Danish authority (SIS) does require a description of the waste in the interim storage facility (Inventory). Furthermore radiological characterisation of key nuclides is needed during decommissioning and dismantling. The information gained from the characterisation helps in the planning phase prior to the dismantling and for inventory calculations for later use. DD performs the radiological characterisation via both non-destructive and destructive analysis on samples. The samples are measured with gamma spectroscopy using mathematical and geometrical analysis. Scaling factors are used for neutron activated waste (DR3) to determine the difficult-to-measure isotopes and pure beta emitters. The primary scaling isotope is Co-60. Waste from the Hot Cell facility is alpha contaminated and scaling procedures for determination of alpha contamination are currently used in the planning process. Scaling of alpha emitters will be incorporated into the inventory calculations. Due to the variable nature of the systems being decommissioned, the sampling procedures are based on ad hoc principles. The number of samples needed is determined by the conventional characterisation of the systems. For systems where conventional knowledge is limited, more samples are generally needed earlier in the decommissioning process. Otherwise sampling can take place prior to the packing of the containers for the interim storage facility. In this case less sampling is needed as few representative samples for each material from each system in the container are sufficient. (author)

  20. HEAVY WATER COMPONENTS TEST REACTOR DECOMMISSIONING

    Energy Technology Data Exchange (ETDEWEB)

    Austin, W.; Brinkley, D.

    2011-10-13

    The Heavy Water Components Test Reactor (HWCTR) Decommissioning Project was initiated in 2009 as a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) Removal Action with funding from the American Recovery and Reinvestment Act (ARRA). This paper summarizes the history prior to 2009, the major D&D activities, and final end state of the facility at completion of decommissioning in June 2011. The HWCTR facility was built in 1961, operated from 1962 to 1964, and is located in the northwest quadrant of the Savannah River Site (SRS) approximately three miles from the site boundary. The HWCTR was a pressurized heavy water test reactor used to develop candidate fuel designs for heavy water power reactors. In December of 1964, operations were terminated and the facility was placed in a standby condition as a result of the decision by the U.S. Atomic Energy Commission to redirect research and development work on heavy water power reactors to reactors cooled with organic materials. For about one year, site personnel maintained the facility in a standby status, and then retired the reactor in place. In the early 1990s, DOE began planning to decommission HWCTR. Yet, in the face of new budget constraints, DOE deferred dismantlement and placed HWCTR in an extended surveillance and maintenance mode. The doors of the reactor facility were welded shut to protect workers and discourage intruders. In 2009 the $1.6 billion allocation from the ARRA to SRS for site footprint reduction at SRS reopened the doors to HWCTR - this time for final decommissioning. Alternative studies concluded that the most environmentally safe, cost effective option for final decommissioning was to remove the reactor vessel, both steam generators, and all equipment above grade including the dome. The transfer coffin, originally above grade, was to be placed in the cavity vacated by the reactor vessel and the remaining below grade spaces would be grouted. Once all above equipment including the dome was removed, a concrete cover was to be placed over the remaining footprint and the groundwater monitored for an indefinite period to ensure compliance with environmental regulations.