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Sample records for nuclear facilities decommissioning

  1. Decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Harmon, K.M.; Jenkins, C.E.; Waite, D.A.; Brooksbank, R.E.; Lunis, B.C.; Nemec, J.F.

    1976-01-01

    This paper describes the currently accepted alternatives for decommissioning retired light water reactor fuel cycle facilities and the current state of decommissioning technology. Three alternatives are recognized: Protective Storage; Entombment; and Dismantling. Application of these alternatives to the following types of facilities is briefly described: light water reactors; fuel reprocessing plants, and mixed oxide fuel fabrication plants. Brief descriptions are given of decommissioning operations and results at a number of sites, and recent studies of the future decommissioning of prototype fuel cycle facilities are reviewed. An overview is provided of the types of operations performed and tools used in common decontamination and decommissioning techniques and needs for improved technology are suggested. Planning for decommissioning a nuclear facility is dependent upon the maximum permitted levels of residual radioactive contamination. Proposed guides and recently developed methodology for development of site release criteria are reviewed. 21 fig, 32 references

  2. Decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Buck, S.

    1996-01-01

    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)

  3. Decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Lunning, W.H.

    1977-01-01

    Collaborative studies are in progress in the U.K. between the U.K.A.E.A., the Generating Boards and other outside bodies, to identify the development issues and practical aspects of decommissioning redundant nuclear facilities. The various types of U.K.A.E.A. experimental reactors (D.F.R., W.A.G.R , S.G.H.W.R.) in support of the nuclear power development programme, together with the currently operating commercial 26 Magnox reactors in 11 stations, totalling some 5 GW will be retired before the end of the century and attention is focussed on these. The actual timing of withdrawal from service will be dictated by development programme requirements in the case of experimental reactors and by commercial and technical considerations in the case of electricity production reactors. Decommissioning studies have so far been confined to technical appraisals including the sequence logic of achieving specific objectives and are based on the generally accepted three stage progression. Stage 1, which is essentially a defuelling and coolant removal operation, is an interim phase. Stage 2 is a storage situation, the duration of which will be influenced by environmental pressures or economic factors including the re-use of existing sites. Stage 3, which implies removal of all active and non-active waste material and returning the site to general use, must be the ultimate objective. The engineering features and the radioactive inventory of the system must be assessed in detail to avoid personnel or environmental hazards during Stage 2. These factors will also influence decisions on the degree of Stage 2 decommissioning and its duration, bearing in mind that for Stage 3 activation may govern the waste disposal route and the associated radiation man-rem exposure during dismantling. Ideally, planning for decommissioning should be considered at the design stage of the facility. An objective of present studies is to identify features which would assist decommissioning of future systems

  4. The decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Niel, J.Ch.; Rieu, J.; Lareynie, O.; Delrive, L.; Vallet, J.; Girard, A.; Duthe, M.; Lecomte, C.; Rozain, J.P.; Nokhamzon, J.G.; Davoust, M.; Eyraud, J.L.; Bernet, Ph.; Velon, M.; Gay, A.; Charles, Th.; Leschaeva, M.; Dutzer, M.; Maocec, Ch.; Gillet, G.; Brut, F.; Dieulot, M.; Thuillier, D.; Tournebize, F.; Fontaine, V.; Goursaud, V.; Birot, M.; Le Bourdonnec, Th.; Batandjieva, B.; Theis, St.; Walker, St.; Rosett, M.; Cameron, C.; Boyd, A.; Aguilar, M.; Brownell, H.; Manson, P.; Walthery, R.; Wan Laer, W.; Lewandowski, P.; Dorms, B.; Reusen, N.; Bardelay, J.; Damette, G.; Francois, P.; Eimer, M.; Tadjeddine, A.; Sene, M.; Sene, R.

    2008-01-01

    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

  5. Decommissioning of nuclear power facilities

    International Nuclear Information System (INIS)

    Nosovskij, A.V.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Yashchenko, Ya.V.

    2005-01-01

    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

  6. Decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1975-01-01

    Present concepts on stages of, designing for and costs of decommissioning, together with criteria for site release, are described. Recent operations and studies and assessments in progress are summarized. Wastes from decommissioning are characterized

  7. Decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Schneider, K.J.

    1979-01-01

    The Symposium was jointly sponsored by OECD/NEA and IAEA and was attended by more than 225 participants from 26 countries. Forty one papers were presented in eight sessions which covered the following topics: national and international policies and planning; engineering considerations relevant to decommissioning; radiological release considerations and waste classifications; decommissioning experience; and decontamination and remote operations. In addition, a panel of decommissioning experts discussed questions from the participants

  8. Waste management considerations in nuclear facility decommissioning

    International Nuclear Information System (INIS)

    Elder, H.K.; Murphy, E.S.

    1981-01-01

    Decommissioning of nuclear facilities involves the management of significant quantities of radioactive waste. This paper summarizes information on volumes of waste requiring disposal and waste management costs developed in a series of decommissioning studies performed for the U.S. Nuclear Regulatory Commission by the Pacific Northwest Laboratory. These studies indicate that waste management is an important cost factor in the decommissioning of nuclear facilities. Alternatives for managing decommissioning wastes are defined and recommendations are made for improvements in waste management practices

  9. Evaluation of Nuclear Facility Decommissioning Projects program

    International Nuclear Information System (INIS)

    Baumann, B.L.

    1983-01-01

    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

  10. Decommissioning Work Modeling System for Nuclear Facility Decommissioning Design

    International Nuclear Information System (INIS)

    Park, S. K.; Cho, W. H.; Choi, Y. D.; Moon, J. K.

    2012-01-01

    During the decommissioning activities of the KRR-1 and 2 (Korea Research Reactor 1 and 2) and UCP (Uranium Conversion Plant), all information and data, which generated from the decommissioning project, were record, input and managed at the DECOMMIS (DECOMMissioning Information management System). This system was developed for the inputting and management of the data and information of the man-power consumption, operation time of the dismantling equipment, the activities of the radiation control, dismantled waste management and Q/A activities. When a decommissioning is planed for a nuclear facility, an investigation into the characterization of the nuclear facility is first required. The results of such an investigation are used for calculating the quantities of dismantled waste volume and estimating the cost of the decommissioning project. That is why, the DEFACS (DEcommissioning FAcility Characterization DB System) was established for the management of the facility characterization data. The DEWOCS (DEcommissioning WOrk-unit productivity Calculation System) was developed for the calculation of the workability on the decommissioning activities. The work-unit productivities are calculated through this system using the data from the two systems, DECOMMIS and DEFACS. This result, the factors of the decommissioning work-unit productivities, will be useful for the other nuclear facility decommissioning planning and engineering. For this, to set up the items and plan for the decommissioning of the new objective facility, the DEMOS (DEcommissioning work Modeling System) was developed. This system is for the evaluation the cost, man-power consumption of workers and project staffs and technology application time. The factor of the work-unit productivities from the DEWOCS and governmental labor cost DB and equipment rental fee DB were used for the calculation the result of the DEMOS. And also, for the total system, DES (Decommissioning Engineering System), which is now

  11. Policy on the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-08-01

    This Regulatory Policy Statement describes the policy of the Atomic Energy Control Board (AECB) on the decommissioning of those facilities defined as nuclear facilities in the Atomic Energy Control (AEC) Regulations. It is intended as a formal statement, primarily for the information of licensees, or potential licensees, of the regulatory process and requirements generally applicable to the decommissioning of nuclear facilities licensed and regulated by the AECB pursuant to the authority of the AEC Act and Regulations

  12. Methodology and technology of decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1986-01-01

    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

  13. Quality management in nuclear facilities decommissioning

    International Nuclear Information System (INIS)

    Garonis, Omar H.

    2002-01-01

    Internationally, the decommissioning organizations of nuclear facilities carry out the decommissioning according to the safety requirements established for the regulatory bodies. Some of them perform their activities in compliance with a quality assurance system. This work establishes standardization through a Specifications Requirement Document, for the management system of the nuclear facilities decommissioning organizations. It integrates with aspects of the quality, environmental, occupational safety and health management systems, and also makes these aspects compatible with all the requirements of the nuclear industry recommended for the International Atomic Energy Agency (IAEA). (author)

  14. Financing the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    2016-01-01

    Decommissioning of both commercial and R and D nuclear facilities is expected to increase significantly in the coming years, and the largest of such industrial decommissioning projects could command considerable budgets. It is important to understand the costs of decommissioning projects in order to develop realistic cost estimates as early as possible based on preliminary decommissioning plans, but also to develop funding mechanisms to ensure that future decommissioning expenses can be adequately covered. Sound financial provisions need to be accumulated early on to reduce the potential risk for residual, unfunded liabilities and the burden on future generations, while ensuring environmental protection. Decommissioning planning can be subject to considerable uncertainties, particularly in relation to potential changes in financial markets, in energy policies or in the conditions and requirements for decommissioning individual nuclear installations, and such uncertainties need to be reflected in regularly updated cost estimates. This booklet offers a useful overview of the relevant aspects of financing the decommissioning of nuclear facilities. It provides information on cost estimation for decommissioning, as well as details about funding mechanisms and the management of funds based on current practice in NEA member countries. (authors)

  15. Decommissioning engineering systems for nuclear facilities and knowledge inheritance for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Tachibana, Mitsuo

    2016-01-01

    Information on construction, operation and maintenance of a nuclear facility is essential in order to plan and implement the decommissioning of the nuclear facility. A decommissioning engineering system collects these information efficiently, retrieves necessary information rapidly, and support to plan the reasonable decommissioning as well as the systematic implementation of dismantling activities. Then, knowledge of workers involved facility operation and dismantling activities is important because decommissioning of nuclear facility will be carried out for a long period. Knowledge inheritance for decommissioning has been carried out in various organizations. This report describes an outline of and experiences in applying decommissioning engineering systems in JAEA and activities related to knowledge inheritance for decommissioning in some organizations. (author)

  16. Stakeholder involvement in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    2007-01-01

    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

  17. AECL's strategy for decommissioning Canadian nuclear facilities

    International Nuclear Information System (INIS)

    Joubert, W.M.; Pare, F.E.; Pratapagiri, G.

    1992-01-01

    The Canadian policy on decommissioning of nuclear facilities as defined in the Atomic Energy Control Act and Regulations is administered by the Atomic Energy Control Board (AECB), a Federal Government agency. It requires that these facilities be decommissioned according to approved plans which are to be developed by the owner of the nuclear facility during its early stages of design and to be refined during its operating life. In this regulatory environment, Atomic Energy of Canada (AECL) has developed a decommissioning strategy for power stations which consists of three distinctive phases. After presenting AECL's decommissioning philosophy, its foundations are explained and it is described how it has and soon will be applied to various facilities. A brief summary is provided of the experience gained up to date on the implementation of this strategy. (author) 3 figs.; 1 tab

  18. Decommissioning of nuclear facilities using current criteria

    International Nuclear Information System (INIS)

    Shum, E.Y.; Swift, J.J.; Malaro, J.C.

    1991-01-01

    When a licensed nuclear facility ceases operation, the US Nuclear Regulatory Commission (NRC) is responsible for ensuring that the facility and its site are decontaminated to an acceptable level so that it is safe to release that facility and site for unrestricted public use. Currently, the NRC is developing decommissioning criteria based on reducing public doses from residual contamination in soils and structures at sites released for unrestricted use to as low as is reasonably achievable (ALARA). Plans are to quantify ALARA in terms of an annual total effective dose equivalent (TEDE) to an average member of the most highly exposed population group. The NRC is working on a regulatory guidance document to provide a technical basis for translating residual contamination levels to annual dose levels. Another regulatory guide is being developed to provide guidance to the licensee on how to conduct radiological surveys to demonstration compliance with the NRC decommissioning criteria. The methods and approaches used in these regulatory guides on the decommissioning of a nuclear facility are discussed in the paper

  19. Investigations on the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Goertz, R.; Bastek, H.; Doerge, W.; Kruschel, K.P.

    1985-01-01

    The study discusses and evaluates safety and licensing related aspects associated with the decommissioning of nuclear power plants. Important decommissioning projects and experiences with relevance to decommissioning are analyzed. Recent developments in the field of decommissioning techniques with the potential of reducing the occupational dose to decommissioning workers are described and their range of application is discussed. The radiological consequences of the recycling of scrap metal arising during decommissioning are assessed. The results may be used to evaluate present licensing practices and may be useful for future licensing procedures. Finally the environmental impact of radionuclide release via air and water pathways associated with decommissioning activities is estimated. (orig.) [de

  20. Decommissioning of excess nuclear facilities

    International Nuclear Information System (INIS)

    Dickson, H.W.; Jacobs, D.J.; Auxier, J.A.

    1978-01-01

    The Department of Energy (DOE) is reviewing the radiological status of over 100 sites previously utilized by the Manhattan Engineering District (MED) and/or the Atomic Energy Commission (AEC) for handling uranium and thorium ores. Many of these sites have been returned to the control of private industry or to public use. Recent radiological surveys indicate that radiation levels at some of the sites exceed certain existing radiological health guidelines, some requiring remedial action. To assess the need for remedial action and to arrive at radiation levels acceptable for unrestricted use of these sites in the future, provisional radiological criteria for decontamination and decommissioning of property contaminated with radium have been developed. These criteria give due consideration to the level of risk, to consistency with existing guidelines, to achievability, enforceability, variability of natural background, flexibility in their application, and the achievement of levels as low as reasonably achievable. Based upon analyses of exposure pathways, numerical criteria have been derived for external gamma radiation, radon daughters levels in structures, radium concentrations in soil and surface contamination levels. In addition, a monitoring program has been designed to evaluate compliance with these decommissioning criteria. (author)

  1. Hematite nuclear fuel cycle facility decommissioning

    International Nuclear Information System (INIS)

    Hayes, K.

    2004-01-01

    Westinghouse Electric Company LLC ('Westinghouse') acquired a nuclear fuel processing plant at Hematite, Missouri ('Hematite', the 'Facility', or the 'Plant') in April 2000. The plant has subsequently been closed, and its operations have been relocated to a newer, larger facility. Westinghouse has announced plans to complete its clean-up, decommissioning, and license retirement in a safe, socially responsible, and environmentally sound manner as required by internal policies, as well as those of its parent company, British Nuclear Fuels plc. ('BNFL'). Preliminary investigations have revealed the presence of environmental contamination in various areas of the facility and grounds, including both radioactive contamination and various other substances related to the nuclear fuel processing operations. The disparity in regulatory requirements for radiological and nonradiological contaminants, the variety of historic and recent operations, and the number of previous owners working under various contractual arrangements for both governmental and private concerns has resulted in a complex project. This paper discusses Westinghouse's efforts to develop and implement a comprehensive decontamination and decommissioning (D and D) strategy for the facility and grounds. (author)

  2. European Nuclear Decommissioning Training Facility II

    International Nuclear Information System (INIS)

    Demeulemeester, Y.

    2005-01-01

    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

  3. Decommissioning of the LURE Nuclear Facility

    International Nuclear Information System (INIS)

    Pauwels, N.; Horodynski, J.M.; Robert, P.; Tadjeddine, A.

    2013-01-01

    With the goal of obtaining the decommissioning of the LURE nuclear facility, three of its accelerators were dismantled and another was modified to be below the thresh- old of 'Installation Nucleaire de Base' status. Operations were carried out with the strategy of mechanical dismantling with no cutting process. As the civil engineering radioactivity level was low, a great majority of it has been left in place with no process- ing, but compensatory measures have been taken for public and environmental protection. The overall result of these operations is a gain in both cost and operating time. They also contribute to a significant decrease in the risks, including radiological ones. The radiological impact after decommissioning remains acceptable. (authors)

  4. Governments' role in decommissioning nuclear power facilities

    International Nuclear Information System (INIS)

    Guindon, S.; Wendling, R.D.; Gordelier, S.; Soederberg, O.; Averous, J.; Orlando, D.

    2005-01-01

    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

  5. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

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

    1990-09-01

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

  6. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

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

    1990-09-01

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

  7. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

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

    1989-09-01

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

  8. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-09-01

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

  9. Decommissioning of nuclear facilities: a growing activity in the world

    International Nuclear Information System (INIS)

    Anasco, Raul

    2001-01-01

    Nuclear power plants and nuclear facilities are no different from normal buildings and factories. Eventually, they become worn-out or old fashioned, too expensive to maintain or remodel. Decommissioning a nuclear facility is different from retiring other types because of the radioactivity involved. The most important consideration in nuclear decommissioning is to protect workers and the public from exposure to harmful levels of radiation. General criteria and strategies for the decommissioning of nuclear facilities are described as well as the present decommissioning activities of the Argentine CNEA (author)

  10. Prospective needs for decommissioning commercial nuclear facilities

    International Nuclear Information System (INIS)

    Stevens, G.H.; Yasui, M.; Laraia, M.

    1992-01-01

    The answers to the questions: How many reactors will face the end of their operating lifetime over the next few decades? To what extent are the issues of decommissioning urgent? The answers will lead us to those issues that should be tackled now in order to complete smoothly the decommissioning of commercial nuclear power plants. The prospective needs for decommissioning of nuclear power plants are illustrated from the viewpoint of reactor age, and some of the issues to be tackled, in particular by governments, in this century are discussed, to prepare for the future decommissioning activities. (author) 18 refs.; 2 figs.; 2 tabs

  11. Decommissioning of nuclear facilities in Korea

    International Nuclear Information System (INIS)

    Hahn, Pil Soo

    2003-01-01

    In 1996, it was concluded that the first Korea research reactor (KRR-1) and the second Korea research reactor (KRR-2) would be shut down and decommissioned. The main reason for the decommissioning was that the facilities became old and has become surrounded by the urbanised community. And many difficulties, including the higher cost, were faced according to the enhanced regulations. Another reason was the introduction of a new research reactor 'HANARO' in 1995. A project to decommission the reactors was launched on January of 1997 with a goal of release of the site and buildings for unrestricted use by 2008. All the radioactive wastes generated are to be transported to the national repository, planned by the Korea Hydro and Nuclear Power Company (KHNP), and the final evaluation of the residual radioactivity will be made before the clearance of the site. As a first step of the project, a decommissioning plan, including the assessment of the environmental impact and the quality assurance program, was prepared and submitted to the government in 1998. It was approved, after its safety evaluation, by the Korea Institute of Nuclear Safety (KINS) in November of 2000. After some preparative works such as documentation of procedures, the decontamination and dismantling works for the laboratories and hot cells of KRR-2 were started in September, 2001 and finished in December, 2002. The spent fuels that had been generated from the reactors were transferred to the United States in 1998 and no spent fuel remained at the site. All the liquid waste, both operational and decommissioning, was very low in its radioactivity and was treated in a natural evaporation facility of 200 m3/year capacity, developed by KAERI. Especially the laundry waste was treated in a membrane filtering unit for the removal of surfactants before being introduced to the natural evaporator. The solid wastes were segregated and packed in the container of 4 m3, designed according to the ISO-1496, and also in

  12. Waste management practices in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Dickson, H.W.

    1979-01-01

    Several thousand sites exist in the United States where nuclear activities have been conducted over the past 30 to 40 years. Questions regarding potential public health hazards due to residual radioactivity and radiation fields at abandoned and inactive sites have prompted careful ongoing review of these sites by federal agencies including the Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC). In some instances, these reviews are serving to point out poor low-level waste management practices of the past. Many of the sites in question lack adequate documentation on the radiological conditions at the time of release for unrestricted use or were released without appropriate restrictions. Recent investigations have identified residual contamination and radiation levels on some sites which exceed present-day standards and guidelines. The NRC, DOE, and Environmental Protection Agency are all involved in developing decontamination and decommissioning (D and D) procedures and guidelines which will assure that nuclear facilities are decommissioned in a manner that will be acceptable to the nuclear industry, various regulatory agencies, other stakeholders, and the general public

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

    International Nuclear Information System (INIS)

    1986-01-01

    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

  14. The cost of decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1993-01-01

    This report sets out the results of a National Audit Office investigation to determine the extent of the potential Government liability for nuclear decommissioning, how this is to be financed and the possible implications for the taxpayer. Further effort are needed to improve the nuclear industry's estimates, improve efficiency and face up to the costs of decommissioning. This should also ensure that the full cost of nuclear energy is identified. (author)

  15. Decommissioning and deactivation of nuclear facilities

    International Nuclear Information System (INIS)

    Anasco, Roberto; Harriague, Santiago; Hey, Alfredo M.; Fabbri, Silvio; Garonis, Omar H.

    2003-01-01

    The National Atomic Energy Commission (CNEA) is responsible for the decommissioning and deactivation of all relevant nuclear facilities in Argentina. A D and D Subprogram was created in 2000, within Technology Branch of the CNEA, in order to fulfill this responsibility. The D and D Subprogram has organized its activities in four fields: Planning; Technology development; Human resources development and training; International cooperation. The paper describes the work already done in those 4 areas, as well as the nuclear facilities existing in the country. Planning is being developed for the decommissioning of research reactors, beginning with RA-1, as well as for the Atucha I nuclear power station. An integral Management System has been developed, compatibilizing requirements from ISO 9001, ISO 14001, the national norm for Safety and Occupational Health (equivalent to BS 8800), and IAEA 50-SG Q series. Technology development is for the time being concentrated on mechanical decontamination and concrete demolition. A review has been made of technologies already developed both by CNEA and Nucleoelectrica Argentina S.A. (the nuclear power utility) in areas of chemical and electrochemical decontamination, cutting techniques and robotics. Human resources development has been based on training abroad in the areas of decontamination, cutting techniques, quality assurance and planning, as well as on specific courses, seminars and workshops. An IAEA regional training course on D and D has been given on April 2002 at CNEA's Constituyentes Atomic Center, with the assistance of 22 university graduates from 13 countries in the Latin American and Caribbean Region, and 11 from Argentina. CNEA has also given fellowships for PhD and Master thesis on the subject. International cooperation has been intense, and based on: - IAEA Technical Cooperation Project and experts missions; - Cooperation agreement with the US Department of Energy; - Cooperation agreement with Germany

  16. Decommissioning Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kang, Y. A.; Kim, G. H.

    2007-06-01

    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

  17. Decommissioning Technology Development for Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. W.; Kang, Y. A.; Kim, G. H. (and others)

    2007-06-15

    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.

  18. Decommissioning of nuclear facilities: Feasibility, needs and costs

    International Nuclear Information System (INIS)

    DeLaney, E.G.; Mickelson, J.R.

    1985-01-01

    The Nuclear Energy Agency's Working Group on Decommissioning is preparing a study entitled ''Decommissioning of Nuclear Facilities: Feasibility, Needs and Costs.'' The study addresses the economics, technical feasibility and waste management aspects of decommissioning larger commercial reactors and nuclear support facilities. Experience on decommissioning small reactors and fuel cycle facilities shows that current technology is generally adequate. Several major projects that are either underway or planned will demonstrate decommissioning of the larger and more complex facilities. This experience will provide a framework for planning and engineering the decommissioning of the larger commercial reactors and fuel cycle facilities. Several areas of technology development are desired for worker productivity improvement, occupational exposure reduction, and waste volume reduction. In order to assess and plan for the decommissioning of large commercial nuclear facilities, projections have been made of the capacity of these facilities that may be decommissioned in the future and the radioactive waste that would be produced from the decommissioning of these facilities. These projections through the year 2025 are based on current data and the OECD reactor capacity forecast through the year 2000. A 25-year operating lifetime for electrical power generation was assumed. The possibilities of plant lifetime extension and the deferral of plant dismantlement make this projection very conservative

  19. Study on archive management for nuclear facility decommissioning projects

    International Nuclear Information System (INIS)

    Huang Ling; Gong Jing; Luo Ning; Liao Bing; Zhou Hao

    2011-01-01

    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)

  20. Decommissioning of nuclear facilities: Decontamination, disassembly and waste management

    International Nuclear Information System (INIS)

    1983-01-01

    The term 'decommissioning', as used within the nuclear industry, means the actions taken at the end of a facility's useful life to retire the facility from service in a manner that provides adequate protection for the health and safety of the decommissioning workers, the general public, and for the environment. These actions can range from merely closing down the facility and a minimal removal of radioactive material coupled with continuing maintenance and surveillance, to a complete removal of residual radioactivity in excess of levels acceptable for unrestricted use of the facility and its site. This latter condition, unrestricted use, is the ultimate goal of all decommissioning actions at retired nuclear facilities. The purpose of this report is to provide an information base on the considerations important to decommissioning, the methods available for decontamination and disassembly of a nuclear facility, the management of the resulting radioactive wastes, and the areas of decommissioning methodology where improvements might be made. Specific sections are devoted to each of these topics, and conclusions are presented concerning the present status of each topic. A summary of past decommissioning experience in Member States is presented in the Appendix. The report, with its discussions of necessary considerations, available operational methods, and waste management practices, together with supporting references, provides an appreciation of the activities that comprise decommissioning of nuclear facilities. It is anticipated that the information presented in the report should prove useful to persons concerned with the development of plans for the decommissioning of retired nuclear facilities

  1. Decommissioning of nuclear fuel cycle facilities. Safety guide

    International Nuclear Information System (INIS)

    2001-01-01

    The objective of this Safety Guide is to provide guidance to regulatory bodies and operating organizations on planning and provision for the safe management of the decommissioning of non-reactor nuclear fuel cycle facilities. While the basic safety considerations for the decommissioning of nuclear fuel cycle facilities are similar to those for nuclear power plants, there are important differences, notably in the design and operating parameters for the facilities, the type of radioactive material and the support systems available. It is the objective of this Safety Guide to provide guidance for the shutdown and eventual decommissioning of such facilities, their individual characteristics being taken into account

  2. Feedback experience from the decommissioning of Spanish nuclear facilities

    International Nuclear Information System (INIS)

    Santiago, J.L.

    2008-01-01

    The Spain has accumulated significant experience in the field of decommissioning of nuclear and radioactive facilities. Relevant projects include the remediation of uranium mills and mines, the decommissioning of research reactors and nuclear research facilities and the decommissioning of gas-graphite nuclear power plants. The decommissioning of nuclear facilities in Spain is undertaken by ENRESA, who is also responsible for the management of radioactive wastes. The two most notable projects are the decommissioning of the Vandellos I nuclear power plant and the decommissioning of the CIEMAT nuclear research centre. The Vandellos I power plant was decommissioned in about five years to what is known as level 2. During this period, the reactor vessel was confined, most plant systems and components were dismantled, the facility was prepared for a period of latency and a large part of the site was restored for subsequent release. In 2005 the facility entered into the phase of dormancy, with minimum operating requirements. Only surveillance and maintenance activities are performed, among which special mention should be made to the five-year check of the leak tightness of the reactor vessel. After the dormancy period (25 - 30 years), level 3 of decommissioning will be initiated including the total dismantling of the remaining parts of the plant and the release of the whole site for subsequent uses. The decommissioning of the CIEMAT Research Centre includes the dismantling of obsolete facilities such as the research reactor JEN-1, a pilot reprocessing plant, a fuel fabrication facility, a conditioning plant for liquid and a liquid waste storage facility which were shutdown in the early eighties. Dismantling works have started in 2006 and will be completed by 2009. On the basis of the experience gained in the above mentioned sites, this paper describes the approaches adopted by ENRESA for large decommissioning projects. (author)

  3. Decommissioning of Nuclear Facilities: Training and Human Resource Considerations

    International Nuclear Information System (INIS)

    2008-01-01

    One of the cornerstones of the success of nuclear facility decommissioning is the adequate competence of personnel involved in decommissioning activities. The purpose of this publication is to provide methodological guidance for, and specific examples of good practices in training as an integral part of human resource management for the personnel performing decommissioning activities. The use of the systematic methodology and techniques described in this publication may be tailored and applied to the development of training for all types of nuclear facilities undergoing decommissioning. Examples of good practices in other aspects of human resources, such as knowledge preservation, management of the workforce and improvement of human performance, are also covered. The information contained in this publication, and the examples provided in the appendices and enclosed CD-ROM, are representative of the experience of decommissioning of a wide variety of nuclear facilities.

  4. Managing LLRW from decommissioning of nuclear facilities - a Canadian perspective

    Energy Technology Data Exchange (ETDEWEB)

    Donders, R E [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.; Hardy, D G [Frontenac Consulting Services, Deep River, ON (Canada); De, P L [Low-Level Radioactive Waste Management Office, Gloucester, ON (Canada)

    1994-03-01

    In Canada, considerable experience has been gained recently in decommissioning nuclear facilities and managing the resulting waste. This experience has raised important issues from both the decommissioning and waste management perspectives. This paper focuses on the waste management aspects of decommissioning. Past experience is reviewed, preliminary estimates of waste volumes and characteristics are provided, and the major technical and regulatory issues are discussed. (author). 5 refs., 1 tab., 2 figs.

  5. Training practices to support decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Bourassa, J.; Clark, C.R.; Kazennov, A.; Laraia, M.; Rodriguez, M.; Scott, A.; Yoder, J.

    2006-01-01

    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

  6. Decontamination and decommissioning of nuclear facilities: a literature search

    International Nuclear Information System (INIS)

    Sande, W.E.; Freeman, H.D.; Hanson, M.S.; McKeever, R.

    1975-05-01

    is bibliography includes 429 unclassified references to the decontamination and decommissioning of nuclear facilities. The references are arranged in chronological order and cover the period from 1944 through 1974. Subject and author indexes are e provided. (U.S.)

  7. Economical problems in connection with the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Dangelmaier, P.

    1977-01-01

    Discussed are: Basic questions of financing, to bring in the decommissioning costs with reference to the various types of enterprises, questions of taxes, use of the accumulated liquid means, the economy of nuclear facilities taking into account the decommissioning expenses. (HP) [de

  8. Validity evaluation of internal exposure in nuclear facility decommission

    International Nuclear Information System (INIS)

    Wang Xiaoli; Chen Dahua; You Zeyun

    2012-01-01

    During nuclear facility decommission under construction, it is very important for workers to wear respirator to avoid harm of Am aerosols. So the protection effect of respirator is very important. The protection effect of respirator was calculated and evaluated according to the data achieved from engineering practice. The result shows that the protection effect is better than target management value and the respirator is effective to protect workers from harm of Am aerosols. The respirator is applied to other nuclear facility decommission. (authors)

  9. Project and feedback experience on nuclear facility decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Santiago, J.L. [ENRESA (Spain); Benest, T.G. [United Kingdom Atomic Energy Authority, Windscale, Cumbria (United Kingdom); Tardy, F.; Lefevre, Ph. [Electricite de France (EDF/CIDEN), 69 - Villeurbanne (France); Willis, A. [VT Nuclear Services (United Kingdom); Gilis, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R. [Belgoprocess (Belgium); Jeanjacques, M. [CEA Saclay, 91 - Gif sur Yvette (France); Bohar, M.P.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.; Binet, C. [CEA Fontenay aux Roses, 92 (France); Fontana, Ph.; Fraize, G. [CEA Marcoule 30 (France); Seurat, Ph. [AREVA NC, 75 - Paris (France); Chesnokov, A.V.; Fadin, S.Y.; Ivanov, O.P.; Kolyadin, V.I.; Lemus, A.V.; Pavlenko, V.I.; Semenov, S.G.; Shisha, A.D.; Volkov, V.G.; Zverkov, Y.A. [Russian Research Centre Kurchatov Inst., Moscow (Russian Federation)

    2008-11-15

    This series of 6 short articles presents the feedback experience that has been drawn from various nuclear facility dismantling and presents 3 decommissioning projects: first, the WAGR project that is the UK demonstration project for power reactor decommissioning (a review of the tools used to dismantle the reactor core); secondly, the dismantling project of the Bugey-1 UNGG reactor for which the dismantling works of the reactor internals is planned to be done underwater; and thirdly, the decommissioning project of the MR reactor in the Kurchatov Institute. The feedback experience described concerns nuclear facilities in Spain (Vandellos-1 and the CIEMAT research center), in Belgium (the Eurochemic reprocessing plant), and in France (the decommissioning of nuclear premises inside the Fontenay-aux-roses Cea center and the decommissioning of the UP1 spent fuel reprocessing plant at the Marcoule site). (A.C.)

  10. Project and feedback experience on nuclear facility decommissioning

    International Nuclear Information System (INIS)

    Santiago, J.L.; Benest, T.G.; Tardy, F.; Lefevre, Ph.; Willis, A.; Gilis, R.; Lewandowski, P.; Ooms, B.; Reusen, N.; Van Laer, W.; Walthery, R.; Jeanjacques, M.; Bohar, M.P.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.; Binet, C.; Fontana, Ph.; Fraize, G.; Seurat, Ph.; Chesnokov, A.V.; Fadin, S.Y.; Ivanov, O.P.; Kolyadin, V.I.; Lemus, A.V.; Pavlenko, V.I.; Semenov, S.G.; Shisha, A.D.; Volkov, V.G.; Zverkov, Y.A.

    2008-01-01

    This series of 6 short articles presents the feedback experience that has been drawn from various nuclear facility dismantling and presents 3 decommissioning projects: first, the WAGR project that is the UK demonstration project for power reactor decommissioning (a review of the tools used to dismantle the reactor core); secondly, the dismantling project of the Bugey-1 UNGG reactor for which the dismantling works of the reactor internals is planned to be done underwater; and thirdly, the decommissioning project of the MR reactor in the Kurchatov Institute. The feedback experience described concerns nuclear facilities in Spain (Vandellos-1 and the CIEMAT research center), in Belgium (the Eurochemic reprocessing plant), and in France (the decommissioning of nuclear premises inside the Fontenay-aux-roses Cea center and the decommissioning of the UP1 spent fuel reprocessing plant at the Marcoule site). (A.C.)

  11. Decontamination and decommissioning project for the nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Paik, S. T.; Park, S. W. (and others)

    2007-02-15

    The final goal of this project is to complete the decommissioning of the Korean Research Reactor no.1 and no. 2(KRR-1 and 2) and uranium conversion plant safely and successfully. The goal of this project in 2006 is to complete the decontamination of the inside reactor hall of the KRR-2 which will be operating as a temporary storage for the radioactive waste until the construction and operation of the national repository site. Also the decommissioning work of the KRR-1 and auxiliary facilities is being progress. As the compaction of decommissioning project is near at hand, a computer information system was developed for a systematically control and preserve a technical experience and decommissioning data for the future reuse. The nuclear facility decommissioning, which is the first challenge in Korea, is being closed to the final stages. We completed the decommissioning of all the bio-shielding concrete for KRR-2 in 2005 and carried out the decontamination and waste material grouping of the roof, wall and bottom of the reactor hall of the KRR-2. The decommissioning for nuclear facility were demanded the high technology, remote control equipment and radioactivity analysis. So developed equipment and experience will be applied at the decommissioning for new nuclear facility in the future.

  12. The regulatory process for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1990-01-01

    The objective of this publication is to provide general guidance to Member States for regulating the decommissioning of nuclear facilities within the established nuclear regulatory framework. The Guide should also be useful to those responsible for, or interested in, the decommissioning of nuclear facilities. The Guide describes in general terms the process to be used in regulating decommissioning and the considerations to be applied in the development of decommissioning regulations and guides. It also delineates the responsibilities of the regulatory body and the licensee in decommissioning. The provisions of this Guide are intended to apply to all facilities within the nuclear fuel cycle and larger industrial installations using long lived radionuclides. For smaller installations, however, less extensive planning and less complex regulatory control systems should be acceptable. The Guide deals primarily with decommissioning after planned shutdown. Most provisions, however, are also applicable to decommissioning after an abnormal event, once cleanup operations have been terminated. The decommissioning planning in this case must take account of the abnormal event. 28 refs, 1 fig

  13. Structure and function design for nuclear facilities decommissioning information database

    International Nuclear Information System (INIS)

    Liu Yongkuo; Song Yi; Wu Xiaotian; Liu Zhen

    2014-01-01

    The decommissioning of nuclear facilities is a radioactive and high-risk project which has to consider the effect of radiation and nuclear waste disposal, so the information system of nuclear facilities decommissioning project must be established to ensure the safety of the project. In this study, by collecting the decommissioning activity data, the decommissioning database was established, and based on the database, the decommissioning information database (DID) was developed. The DID can perform some basic operations, such as input, delete, modification and query of the decommissioning information data, and in accordance with processing characteristics of various types of information data, it can also perform information management with different function models. On this basis, analysis of the different information data will be done. The system is helpful for enhancing the management capability of the decommissioning process and optimizing the arrangements of the project, it also can reduce radiation dose of the workers, so the system is quite necessary for safe decommissioning of nuclear facilities. (authors)

  14. Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2009-01-01

    1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

  15. Relative evaluation on decommissioning accident scenarios of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, Kwan-Seong; Choi, Byung-Seon; Moon, Jei-Kwon; Hyun, Dong-Jun; Kim, Geun-Ho; Kim, Tae-Hyoung; Jo, Kyung-Hwa; Seo, Jae-Seok; Jeong, Seong-Young; Lee, Jung-Jun

    2012-01-01

    Highlights: ► This paper suggests relative importance on accident scenarios during decommissioning of nuclear facilities. ► The importance of scenarios can be performed by using AHP and Sugeno fuzzy method. ► The AHP and Sugeno fuzzy method guarantee reliability of the importance evaluation. -- Abstract: This paper suggests the evaluation method of relative importance on accident scenarios during decommissioning of nuclear facilities. The evaluation method consists of AHP method and Sugeno fuzzy integral method. This method will guarantee the reliability of relative importance evaluation for decommissioning accident scenarios.

  16. Decommissioning of nuclear facilities involving operations with uranium and thorium

    International Nuclear Information System (INIS)

    Shum, E.Y.; Neuder, S.M.

    1990-01-01

    When a licensed nuclear facility ceases operation, the U.S. Nuclear Regulatory Commission (NRC) ensures that the facility and its site are decontaminated to acceptable levels so they may safely be released for unrestricted public use. Because specific environmental standards or broad federal guidelines governing release of residual radioactive contamination have not been issued, NRC has developed ad hoc cleanup criteria for decommissioning nuclear facilities that involved uranium and thorium. Cleanup criteria include decontamination of buildings, equipment, and land. We will address cleanup criteria and their rationale; procedures for decommissioning uranium/thorium facilities; radiological survey designs and procedures; radiological monitoring and measurement; and cost-effectiveness to demonstrate compliance

  17. Decommissioning of nuclear facilities: 'it can and has been done'

    International Nuclear Information System (INIS)

    2009-01-01

    Considerable international experience gained over the last 20 years demonstrates that nuclear facilities can be safely dismantled and decommissioned once a decision is made to cease operations and permanently shut them down. The term decommissioning is used to describe all the management and technical actions associated with ceasing operation of a nuclear installation and its subsequent dismantling to facilitate its removal from regulatory control (de-licensing). These actions involve decontamination of structures and components, dismantling of components and demolition of buildings, remediation of any contaminated ground and removal of the resulting waste. Worldwide, of the more than 560 commercial nuclear power plants that are or have been in operation, about 120 plants have been permanently shut down and are at some stage of decommissioning. About 10% of all shutdown plants have been fully decommissioned, including eight reactors of more than 100 MWe. A larger number of various types of fuel cycle and research facilities have also been shut down and decommissioned, including: facilities for the extraction and enrichment of uranium, facilities for fuel fabrication and reprocessing, laboratories, isotope production facilities and particle accelerators. This brochure looks at decommissioning across a spectrum of nuclear facilities and shows worldwide examples of successful projects. Further information can be found in NEA publications and on a number of web-sites

  18. Evaluation of nuclear facility decommissioning projects. Status report. Humboldt Bay Power Plant Unit 3, SAFSTOR decommissioning

    International Nuclear Information System (INIS)

    Baumann, B.L.; Haffner, D.R.; Miller, R.L.; Scotti, K.S.

    1986-06-01

    This document explains the purpose of the US Nuclear Regulatory Commission's (NRC) Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program and summarizes information concerning the decommissioning of the Humboldt Bay Power Plant (HBPP) Unit 3 facility. Preparations to put this facility into a custodial safe storage (SAFSTOR) mode are currently scheduled for completion by June 30, 1986. This report gives the status of activities as of June 1985. A final summary report will be issued after completion of this SAFSTOR decommissioning activity. Information included in this status report has been collected from the facility decommissioning plan, environmental report, and other sources made available by the licensee. This data has been placed in a computerized data base system which permits data manipulation and summarization. A description of the computer reports that can be generated by the decommissioning data system (DDS) for Humboldt Bay and samples of those reports are included in this document

  19. Beneficial Re-use of Decommissioned Former Nuclear Facilities

    International Nuclear Information System (INIS)

    Boing, L.E.

    1997-01-01

    With the decision to decommission a nuclear facility, it is necessary to evaluate whether to fully demolish a facility or to re-use the facility in some capacity. This evaluation is often primarily driven by both the past mission of the site and the facility and the site's perceived future mission. In the case where the facility to be decommissioned is located within a large research or industrial complex and represents a significant resource to the site's future mission, it may be a perfect candidate to be re-used in some fashion. However, if the site is a rather remote older facility with little chance of being modified to today's standards for its re-use, the chances for its re-use will be substantially reduced. In this presentation, some specific cases of former nuclear facilities being decommissioned and re-used will be reviewed and some factors required to be considered in making this decision will be reviewed

  20. Regulations and financing for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Kumakura, Osamu

    1981-01-01

    The purpose of this report is to survey the French legislation concerning the decommissioning of nuclear facilities and the method of financing for it. There is no clause in French regulations, which states any specific criterion or licensing procedure for the proper decommissioning. The legal problems in this domain are treated within the general regulation system on atomic energy. The decommissioning of nuclear facilities is carried out in accordance with the licensing procedure for constructing nuclear facilities or the permission procedure for operating them, according to the ''Decree on nuclear installations, 1963''. The works for the final shut-down and decommissioning are regarded as the modification to the safety report or the general operation instructions, and new permit is required. In the case that the radioactivity of substances after decommissioning is above the criteria of the Decree, 1963, the new license is required. In the case of below the criteria, the facilities are governed by the ''Act on installations classified for environmental protection, 1976''. The ''Decree on general radiation protection, 1966'', the ''Decree on radiation protection of workers in nuclear installations, 1975'', the ''Ministerial order on transport of dangerous materials, 1945'', and two ministerial orders on radioactive effluent discharge, 1974, are applied to the decommissioning works. (Kako, I.)

  1. The preliminary planning for decommissioning nuclear facilities in Taiwan

    International Nuclear Information System (INIS)

    Li, K.K.

    1993-01-01

    During the congressional hearing in 1992 for a $7 billion project for approval of the fourth nuclear power plant, the public was concerned about the decommissioning of the operating plants. In order to facilitate the public acceptance of nuclear energy and to secure the local capability for appropriate nuclear backend management, both technologically and financially, it is important to have preliminary planning for decommissioning the nuclear facilities. This paper attempted to investigate the possible scope of decommissioning activities and addressed the important regulatory, financial, and technological aspects. More research and development works regarding the issue of decommissioning are needed to carry out the government's will of decent management of nuclear energy from the cradle to the grave

  2. Radiological planning and implementation for nuclear-facility decommissioning

    International Nuclear Information System (INIS)

    Valentine, A.M.

    1982-01-01

    The need and scope of radiological planning required to support nuclear facility decommissioning are issues addressed in this paper. The role of radiation protection engineering and monitoring professionals during project implementation and closeout is also addressed. Most of the discussion focuses on worker protection considerations; however, project support, environmental protection and site release certification considerations are also covered. One objective is to identify radiological safety issues that must be addressed. The importance of the issues will vary depending on the type of facility being decommissioned; however, by giving appropriate attention to these issues difficult decommissioning projects can be accomplished in a safer manner with workers and the public receiving minimal radiation exposures

  3. Addressing Uncertainties in Cost Estimates for Decommissioning Nuclear Facilities

    International Nuclear Information System (INIS)

    Benjamin, Serge; Descures, Sylvain; Du Pasquier, Louis; Francois, Patrice; Buonarotti, Stefano; Mariotti, Giovanni; Tarakonov, Jurij; Daniska, Vladimir; Bergh, Niklas; Carroll, Simon; AaSTRoeM, Annika; Cato, Anna; De La Gardie, Fredrik; Haenggi, Hannes; Rodriguez, Jose; Laird, Alastair; Ridpath, Andy; La Guardia, Thomas; O'Sullivan, Patrick; ); Weber, Inge; )

    2017-01-01

    The cost estimation process of decommissioning nuclear facilities has continued to evolve in recent years, with a general trend towards demonstrating greater levels of detail in the estimate and more explicit consideration of uncertainties, the latter of which may have an impact on decommissioning project costs. The 2012 report on the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations, a joint recommendation by the Nuclear Energy Agency (NEA), the International Atomic Energy Agency (IAEA) and the European Commission, proposes a standardised structure of cost items for decommissioning projects that can be used either directly for the production of cost estimates or for mapping of cost items for benchmarking purposes. The ISDC, however, provides only limited guidance on the treatment of uncertainty when preparing cost estimates. Addressing Uncertainties in Cost Estimates for Decommissioning Nuclear Facilities, prepared jointly by the NEA and IAEA, is intended to complement the ISDC, assisting cost estimators and reviewers in systematically addressing uncertainties in decommissioning cost estimates. Based on experiences gained in participating countries and projects, the report describes how uncertainty and risks can be analysed and incorporated in decommissioning cost estimates, while presenting the outcomes in a transparent manner

  4. Organization and management for decommissioning of large nuclear facilities

    International Nuclear Information System (INIS)

    2000-01-01

    For nuclear facilities, decommissioning is the final phase in the life-cycle after siting, design, construction, commissioning and operation. It is a complex process involving operations such as detailed surveys, decontamination and dismantling of plant equipment and facilities, demolition of buildings and structures, and management of resulting waste and other materials, whilst taking into account aspects of health and safety of the operating personnel and the general public, and protection of the environment. Careful planning and management is essential to ensure that decommissioning is accomplished in a safe and cost effective manner. Guidance on organizational aspects may lead to better decision making, reductions in time and resources, lower doses to the workers and reduced impact on public health and the environment. The objective of this report is to provide information and guidance on the organization and management aspects for the decommissioning of large nuclear facilities which will be useful for licensees responsible for discharging these responsibilities. The information contained in the report may also be useful to policy makers, regulatory bodies and other organizations interested in the planning and management of decommissioning. In this report, the term 'decommissioning' refers to those actions that are taken at the end of the useful life of a nuclear facility in withdrawing it from service with adequate regard for the health and safety of workers and members of the public and for the protection of the environment. The term 'large nuclear facilities' involves nuclear power plants, large nuclear research reactors and other fuel cycle facilities such as reprocessing plants, fuel conversion, fabrication and enrichment plants, as well as spent fuel storage and waste management plants. Information on the planning and management for decommissioning of smaller research reactors or other small nuclear facilities can be found elsewhere. The report covers

  5. Criteria, standards and policies regarding decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Detilleux, E.; Lennemann, W.L.

    1977-01-01

    At the end of this century, there will probably be around 2500 operating nuclear power reactors, along with all the other nuclear fuel cycle facilities supporting their operation. Eventually these facilities, one by one, will be shut down and it will be necessary to dispose of them as with any redundant industrial facility or plant. Some parts of a nuclear fuel cycle facility can be dismantled by conventional methods, but those parts which have become contaminated with radioactive nuclear products or induced radioactivity must be subject to rigid controls and restrictions and handled by special dismantling and disposal procedures. In many cases, the resulting quantity of radioactive waste is likely to be relatively large and dismantling quite costly. Decommissioning nuclear facilities is a multifaceted problem involving planners, design engineers, operators, waste managers and regulatory authorities. Preparation for decommissioning should begin as early as site selection and plant design. The corner stone for the preparation of a decommissioning programme is the definition of its extent, meeting the requirements for public and environmental protection during the period that the radioactive material is of concern. The paper discusses the decontamination and decommissioning experience at the Eurochemic fuel reprocessing plant, the implications and the knowledge gained from this experience. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who should jointly make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities

  6. Incorporating design for decommissioning into the layout of nuclear facilities

    International Nuclear Information System (INIS)

    Collum, B.; Druart, A.

    2008-01-01

    Design for Decommissioning (DfD) is the design of nuclear facilities in a manner that facilitates ultimate decommissioning in as safe, technically efficient and cost effective way as possible. Strictly speaking, (DfD) should need minimal introduction and this paper should ideally be aimed at discussing the finer points of some improvement to a practice that is already widely embedded throughout the nuclear industry. The reality though is quite different. As an industry, we all know what DfD is and indeed we do incorporate it into our designs. However, application is at best patchy and there is little evidence of applying it to the level that will be advocated here. When applied at its highest level, DfD is all about truly designing nuclear facilities with their whole life cycle in mind, such that the decommissioning phase is an integral part of the design of a facility from the very first day. In this way, when a facility comes to the end of its operational life, it can move smoothly to Post Operational Clean Out (POCO) and then through the various phases of decommissioning. Demonstrating from the start that the nuclear industry addresses the challenges posed by decommissioning will help it to gain support from the regulators and the general public for proposals to build new nuclear generating capacity. (author)

  7. Status of ANSI standards on decommissioning of nuclear reprocessing facilities

    International Nuclear Information System (INIS)

    Graham, H.B.

    1975-01-01

    A definition of decommissioning is given, and the preparation of ANSI Standard, ''General Design Criteria for Nuclear Reprocessing Facilities'' (N101.3) is discussed. A Eurochemic report, entitled ''The Shutdown of Reprocessing Facilities--Results of Preliminary Studies on the Installations Belonging to Eurochemic,'' was used in the preparation of this standard. (U.S.)

  8. Final generic environmental impact statement on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-08-01

    This final generic environmental impact statement was prepared as part of the requirement for considering changes in regulations on decommissioning of commercial nuclear facilities. Consideration is given to the decommissioning of pressurized water reactors, boiling water reactors, research and test reactors, fuel reprocessing plants (FRPs) (currently, use of FRPs in the commercial sector is not being considered), small mixed oxide fuel fabrication plants, uranium hexafluoride conversion plants, uranium fuel fabrication plants, independent spent fuel storage installations, and non-fuel-cycle facilities for handling byproduct, source and special nuclear materials. Decommissioning has many positive environmental impacts such as the return of possibly valuable land to the public domain and the elimination of potential problems associated with increased numbers of radioactively contaminated facilities with a minimal use of resources. Major adverse impacts are shown to be routine occupational radiation doses and the commitment of nominally small amounts of land to radioactive waste disposal. Other impacts, including public radiation doses, are minor. Mitigation of potential health, safety, and environmental impacts requires more specific and detailed regulatory guidance than is currently available. Recommendations are made as to regulatory decommissioning particulars including such aspects as decommissioning alternatives, appropriate preliminary planning requirements at the time of commissioning, final planning requirements prior to termination of facility operations, assurance of funding for decommissioning, environmental review requirements. 26 refs., 7 figs., 68 tabs

  9. Criteria, standards and policies regarding decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Detilleux, E.; Lennemann, W.

    1977-01-01

    The paper discusses the decontamination and decommissioning experiences encountered at the Eurochemic fuel reprocessing plant, their implications and the knowledge gained from these experiences. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The conlusions which are presented should weigh heavily in the considerations of the national authorities involved in regulating nuclear power programmes. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who jointly should make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities [fr

  10. Decommissioning and environmental restoration of nuclear facilities in China

    International Nuclear Information System (INIS)

    Pan Ziqiang

    2000-01-01

    In the beginning of the 1980s, the Scientific and Technological Commission (STC) began the study on the environmental impact of the nuclear industry in China. At the end of the 1980s, the STC initiated the study on the decommissioning of nuclear facilities and environmental restoration. In 1989 the STC completed the project entitled ''Radiological and Environmental Quality Assessment of the Nuclear Industry in China Over the Past Thirty Years''. The status of the environmental pollution of various nuclear facility sites was subsequently analysed. In 1994, the decommissioning and environmental restoration of the first research and manufacture complex for nuclear weapons was completed. The complex is now accessible to the public without restriction and the site has become a town. Some nuclear related facilities, such as uranium mines, are currently being decommissioned. Although uranium mining and milling has a more serious impact on the environment, the technology for decommissioning and environmental restoration in mining and milling installations is not much more complicated than that used for reactor and reprocessing facilities: much has been achieved in the area of mining and milling. (author)

  11. Development of decommissioning, decontamination and reuse technology for nuclear facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Moon, J. K.; Choi, B. S.

    2012-03-01

    In this project, the foundation of decommissioning technology through the development of core technologies applied to maintenance and decommissioning of nuclear facility was established. First of all, we developed the key technology such as safety assessment technology for decommissioning work needed at the preparatory stage of decommissioning of the highly contaminated facilities and simultaneous measurement technology of the high-level alpha/beta contamination applicable to the operation and decommissioning of the nuclear facilities. Second, we developed a remotely controlled laser ablation decontamination system which is useful for a removal of fixed contaminants and developed a chemical gel decontamination technology for a removal of non-fixed contaminants during the maintenance and decommissioning works of high radiation hot cells which have been used for a recycling or treatment of spent fuels. Third, we developed a volume reduction and self-disposal technology for dismantled concrete wastes. Also, the technology for volume reduction and stabilization of the peculiar wastes(HEPA filter and organic mixed wastes), which have been known to be very difficult to treat and manage, generated from the high radioactive facilities in operation, improvement and repair and under decommissioning was developed. Finally, this research project was developed a system for the reduction of radiotoxicity of several uranium mixtures generated in the front- and back-end nuclear fuel cycles with characteristics of highly enhanced proliferation-resistance and more environmental friendliness, which can make the uranium to be recovered or separated from the mixtures with a high purity level enough for the uranium to be reused and to be classified as C-class level for burial near the surface, and then which result in the much reduction in volume of the uranium mixture wastes

  12. Decontamination and Decommissioning Project for the Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Park, J. H.; Paik, S. T.; Park, S. W. and others

    2006-02-15

    The final goal of this project is to complete safely and successfully the decommissioning of the Korean Research Reactor no.1 (KRR-1) and the Korean Research Reactor no.2 (KRR-2), and uranium conversion plant (UCP). The dismantling of the reactor hall of the KRR-2 was planned to complete till the end of 2004, but it was delayed because of a few unexpected factors such as the development of a remotely operated equipment for dismantling of the highly radioactive parts of the beam port tubes. In 2005, the dismantling of the bio-shielding concrete structure of the KRR-2 was finished and the hall can be used as a temporary storage space for the radioactive waste generated during the decommissioning of the KRR-1 and KRR-2. The cutting experience of the shielding concrete by diamond wire saw and the drilling experience by a core boring machine will be applied to another nuclear facility dismantling. An effective management tool of the decommissioning projects, named DECOMIS, was developed and the data from the decommissioning projects were gathered. This system provided many information on the daily D and D works, waste generation, radiation dose, etc., so an effective management of the decommissioning projects is expected from next year. The operation experience of the uranium conversion plant as a nuclear fuel cycle facility was much contributed to the localization of nuclear fuels for both HWR and PWR. It was shut down in 1993 and a program for its decontamination and dismantling was launched in 2001 to remove all the contaminated equipment and to achieve the environment restoration. The decommissioning project is expected to contribute to the development of the D and D technologies for the other domestic fuel cycle facilities and the settlement of the new criteria for decommissioning of the fuel cycle related facilities.

  13. Development of simplified decommissioning cost estimation code for nuclear facilities

    International Nuclear Information System (INIS)

    Tachibana, Mitsuo; Shiraishi, Kunio; Ishigami, Tsutomu

    2010-01-01

    The simplified decommissioning cost estimation code for nuclear facilities (DECOST code) was developed in consideration of features and structures of nuclear facilities and similarity of dismantling methods. The DECOST code could calculate 8 evaluation items of decommissioning cost. Actual dismantling in the Japan Atomic Energy Agency (JAEA) was evaluated; unit conversion factors used to calculate the manpower of dismantling activities were evaluated. Consequently, unit conversion factors of general components could be classified into three kinds. Weights of components and structures of the facility were necessary for calculation of manpower. Methods for evaluating weights of components and structures of the facility were studied. Consequently, the weight of components in the facility was proportional to the weight of structures of the facility. The weight of structures of the facility was proportional to the total area of floors in the facility. Decommissioning costs of 7 nuclear facilities in the JAEA were calculated by using the DECOST code. To verify the calculated results, the calculated manpower was compared with the manpower gained from actual dismantling. Consequently, the calculated manpower and actual manpower were almost equal. The outline of the DECOST code, evaluation results of unit conversion factors, the evaluation method of the weights of components and structures of the facility are described in this report. (author)

  14. Strategy selection for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    2004-01-01

    As modern nuclear power programmes mature and large, commercial nuclear power plants and fuel cycle facilities approach the end of their useful life by reason of age, economics or change of policy on the use of nuclear power, new challenges associated with decommissioning and dismantling come to the fore. Politicians and the public may expect there to be a 'right answer' to the choice of strategy for a particular type of facility, or even all facilities. Both this seminar and wider experience show that this is not the case. Local factors and national political positions have a significant input and often result in widely differing strategy approaches to broadly similar decommissioning projects. All facility owners represented at the seminar were able to demonstrate a rational process for strategy selection and compelling arguments for the choices made. In addition to the papers that were presented, these proceedings include a summary of the discussions that took place. (author)

  15. Development of the Decommissioning Technology for Nuclear Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kim, G. N.; Kim, S. G.

    2010-04-01

    The evaluation technology of decommissioning process must be developed and will be used for the ALARA planning tool of decommissioning process and demonstrated for tools of decommissioning equipment. Also, this technology can be used for tools workplaces with high work difficulty such as large-scale chemical plant, under water and space. The monitoring system for high alpha radioactive contamination measurement will be use in the high radioactivity decommissioning sites such as hot-cell or glove box. Also, it will be use in the general nuclear facilities as the radiation monitoring unit. The preparation technology of the radiation sensor for high radioactive contamination measurement will be transferred to the company for the industrialization. The remote monitoring system can prevent the workers exposure using the optical fiber to separate the sensor and electronics

  16. Selecting strategies for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    2006-01-01

    This status report on Selecting Strategies for the Decommissioning of Nuclear Facilities is based on the viewpoints and materials presented at the Tarragona seminar as well as the experience of the WPDD. It identifies, reviews and analyses factors influencing decommissioning strategies and addresses the challenges associated with balancing these factors in the process of strategy selection. It gives recognition to the fact that, in addition to technical characteristics, there are many other factors that influence the selection of a decommissioning strategy and that cannot be quantified, such as policy, regulatory and socio-economic factors and aspects that reach far into the future. Uncertainties associated with such factors are a challenge to those who have to take decisions on a decommissioning strategy. (author)

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

    International Nuclear Information System (INIS)

    Serrato, Michael G.; Musall, John C.; Bergren, Christopher L.

    2013-01-01

    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 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

  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

  19. An international contribution to decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Lazo, T.

    1995-01-01

    Nuclear power plants and fuel cycle facilities must be retired from service when they have completed their design objective, become obsolete or when they no longer fulfill current safety, technical or economic requirements. Decommissioning is defined as the set of technical and administrative operations that provides adequate protection of workers and public against radiation risks, minimizes impact on the environment and involves manageable costs. A traditional definition of the stages of decommissioning has been proposed by the IAEA and is largely used worldwide. A number of factors have to be considered when selecting the optimum strategy, which include the national nuclear policy, characteristics of the facility, health and safety, environmental protection, radioactive waste management, future use of the site, improvements of the technology that may be achieved in the future, costs and availability of funds and various social considerations. The paper describes the current situation of nuclear facilities and the associated forthcoming requirements and problems of decommissioning. This task requires a complete radionuclide inventory, decontamination methods, disassembly techniques and remote operations. Radiation safety presents three aspects: nuclear safety, protection of workers and protection of the public. An appropriate delay to initiate decommissioning after shutdown of a facility may considerably reduce workers exposures and costs. Decommissioning also generates significant quantities of neutron-activated and surface contaminated materials which require a specific management. A vigorous international cooperation and coordinated research programs have been encouraged by the NEA for a minimization of costs and efforts and to provide a basis for consensus of opinions on policies, strategies and criteria. (J.S.). 19 refs., 5 figs., 3 tabs

  20. A state-of-the art on decommissioning of nuclear facilities in Japan

    International Nuclear Information System (INIS)

    Park, Seung Kook; Kim, Hee Reyoung; Chung, Un Soo; Jung, Ki Jung

    2002-05-01

    While proceeding the KRR-1 and 2 decommissioning project, we are carried out study for the state of the art on decommissioning of nuclear facilities in Japan. Also, we are studied for the research reactors and commercial power plant that has the object of decommissioning, and for the government and the organization related on decommissioning operation. We are investigated for decommissioning activities of nuclear facilities achieved by JAERI, and collected the information and data for decommissioning techniques and computational system through the JPDR(Japan Power Demonstration Reactor) decommissioning activities. Such techniques are applying for Tokai Power Station began the decommissioning project from last year, and for Fugen Nuclear Power Station to be planned the decommissioning from 2003. Recent techniques for decommissioning was acquired by direct contact. The status of the treatment for decommissioning waste and the disposal facility for the very low-level radioactive concrete wastes was grasped

  1. Decontamination and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1989-06-01

    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

  2. Decontamination and Decommissioning at Small Nuclear Facilities: Facilitating the Submission of Decommissioning Funding Plans

    International Nuclear Information System (INIS)

    Minor, D.A.; Grumbles, A.

    2009-01-01

    This paper describes the efforts of the Washington State Department of Health to ensure that small nuclear facilities have the tools each needs to submit Decommissioning Funding Plans. These Plans are required by both the U.S. Nuclear Regulatory Commission (NRC) and in some states - in the case of Washington state, the Washington State Department of Health is the regulator of radioactive materials. Unfortunately, the guidance documents provided by the U.S. NRC pertain to large nuclear facilities, such as nuclear fuel fabrication plants, not the small nuclear laboratory nor small nuclear laundry that may also be required to submit such Plans. These small facilities are required to submit Decommissioning Funding Plans by dint of their nuclear materials inventory, but have only a small staff, such as a Radiation Safety Officer and few authorized users. The Washington State Department of Health and Attenuation Environmental Company have been working on certain tools, such as templates and spreadsheets, that are intended to assist these small nuclear facilities prepare compliant Decommissioning Funding Plans with a minimum of experience and effort. (authors)

  3. Decommissioning of Australian nuclear facilities - a regulatory perspective

    International Nuclear Information System (INIS)

    Diamond, T.V.; Mabbott, P.E.; Lawrence, B.R.

    2000-01-01

    Decommissioning has been a key political, economic and technical issue for the nuclear industry in recent years as older nuclear facilities have been retired. The management of decommissioning is an important part of nuclear safety as the potential exists for occupational exposures that are several times those expected during normal operation. It involves pre-planning and preparatory measures, procedures and instructions, technical and safety assessments, technology for handling large volumes of radioactive material, cost analyses, and a complex decision process. A challenge for the Commonwealth Government regulatory body, the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA), is to allow the Commonwealth entities that operate nuclear facilities ample freedom to address the above, at the same time ensuring that international best practice is invoked to ensure safety. Accordingly, ARPANSA has prepared a regulatory guideline, first drafted by the Nuclear Safety Bureau in March 1997, that documents the process and the criteria that it uses when assessing an application from an operating organisation for a decommissioning licence. Copyright (2000) Australasian Radiation Protection Society Inc

  4. Atmospheric discharges from nuclear facilities during decommissioning: German experiences

    Energy Technology Data Exchange (ETDEWEB)

    Braun, H.; Goertz, R.; Weil, L.

    1997-08-01

    In Germany, a substantial amount of experience is available with planning, licensing and realization of decommissioning projects. In total, a number of 18 nuclear power plants including prototype facilities as well as 6 research reactors and 3 fuel cycle facilities have been shut down finally and are at different stages of decommissioning. Only recently the final {open_quotes}green field{close_quotes} stage of the Niederaichbach Nuclear Power Plant total dismantlement project has been achieved. From the regulatory point of view, a survey of the decommissioning experience in Germany is presented highlighting the aspects of production and retention of airborne radioactivity. Nuclear air cleaning technology, discharge limits prescribed in licences and actual discharges are presented. As compared to operation, the composition of the discharged radioactivity is different as well as the off-gas discharge rate. In practically all cases, there is no significant amount of short-lived radionuclides. The discussion further includes lessons learned, for example inadvertent discharges of radionuclides expected not to be in the plants inventory. It is demonstrated that, as for operation of nuclear power plants, the limits prescribed in the Ordinance on Radiological Protection can be met using existing air cleaning technology, Optimization of protection results in public exposures substantially below the limits. In the frame of the regulatory investigation programme a study has been conducted to assess the airborne radioactivity created during certain decommissioning activities like decontamination, segmentation and handling of contaminated or activated parts. The essential results of this study are presented, which are supposed to support planning for decommissioning, for LWRs, Co-60 and Cs-137 are expected to be the dominant radionuclides in airborne discharges. 18 refs., 2 figs., 1 tab.

  5. Design Lessons Drawn from the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    2011-05-01

    This report provides an updated compilation incorporating the most recent lessons learned from decommissioning and remediation projects. It is intended as a 'road map' to those seeking to apply these lessons. The report presents the issues in a concise and systematic manner, along with practical, thought-provoking examples. The most important lessons learned in recent years are organized and examined to enable the intended audience to gauge the importance of this aspect of the planning for new nuclear facilities. These will be of special interest to those seeking to construct nuclear facilities for the first time. In Sections 1 and 2, the current situation in the field of decommissioning is reviewed and the relevance and importance of beneficial design features is introduced. A more detailed review of previous and current lessons learned from decommissioning is given in Section 3 where different aspects of the decommissioning process are analysed. From this analysis beneficial design features have been extracted and identified in Section 4 which includes two comprehensive tables where brief descriptions of the features are summarized and responsibilities are identified. Conclusions and key design features and key recommendations are given in Section 5. Two Annexes are included to provide lessons from past projects and past experience and to record notes and extracts taken from a comprehensive list of publications listed in the References on page 47.

  6. General framework and basis of decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Santiago, J. L.; Martin, N.; Correa, C.

    2013-01-01

    This article summarizes the legal framework defining the strategies, the main activities and the basic responsibilities and roles of the various agents involved in the decommissioning of nuclear facilities in Spain. It also describes briefly the most relevant projects and activities already developed and/or ongoing nowadays, which have positioned Spain within the small group of countries having an integrated and proved experience and know how in this particular field. (Author)

  7. The Practice of Cost Estimation for Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Davidova, Ivana; Desecures, Sylvain; Lexow, Thomas; Buonarroti, Stefano; Marini, Giuseppe; Pescatore, Claudio; Rehak, Ivan; Weber, Inge; ); Daniska, Vladimir; Linan, Jorge Borque; Caroll, Simon; Hedberg, Bjoern; De La Gardie, Fredrik; Haenggi, Hannes; Laguardia, Thomas S.; Ridpath, Andy

    2015-01-01

    Decommissioning of both commercial and R and D nuclear facilities is expected to increase significantly in the coming years, and the largest of such industrial decommissioning projects could command considerable budgets. Several approaches are currently being used for decommissioning cost estimations, with an international culture developing in the field. The present cost estimation practice guide was prepared in order to offer international actors specific guidance in preparing quality cost and schedule estimates to support detailed budgeting for the preparation of decommissioning plans, for the securing of funds and for decommissioning implementation. This guide is based on current practices and standards in a number of NEA member countries and aims to help consolidate the practice and process of decommissioning cost estimation so as to make it more widely understood. It offers a useful reference for the practitioner and for training programmes. The remainder of report is divided into the following chapters: - Chapter 2 covers the purpose and nature of decommissioning cost estimates, approaches to cost estimation and the major elements of a cost estimate. - Chapter 3 examines the development of the integrated schedule of the activity-dependent work scope and the determination of the project critical path. - Chapter 4 describes the attributes of a quality assurance programme applicable to cost estimation and the use and cautions of benchmarking the estimate from other estimates or actual costs. - Chapter 5 describes the pyramidal structure of the report, and the scope and content that should be included in the cost study report to ensure consistency and transparency in the estimate underpinnings. - Chapter 6 provides some observations, conclusions and recommendations on the use of this guide

  8. Interim Storage Facility for LLW of Decommissioning Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Amato, S.; Ugolini, D.; Basile, F. [European Commission, Joint Research Centre, Nuclear Decommissioning and Facility Management Unit, TP 800, Via E. Fermi 2749, 21027 Ispra - VA (Italy)

    2009-06-15

    JRC-Ispra has initiated a Decommissioning and Waste Management (D and WM) Programme of all its nuclear facilities. In the frame of this programme, it has been decided to build an interim storage facility to host conditioned low level waste (LLW) that had been produced during the operation of JRC-Ispra nuclear research reactors and laboratories and that will be produced from their decommissioning. This paper presents the main characteristics of the facility. The storage ISFISF has a rectangular shape with uniform height and it is about 128 m long, 41 m wide and 9 m high. The entire surface affected by the facility, including screening area and access roads, is about 27.000 m{sup 2}. It is divided in three sectors, a central one, about 16 m long, for loading/unloading operations and operational services and two lateral sectors, each about 55 m long, for the conditioned LLW storage. Each storage sector is divided by a concrete wall in two transversal compartments. The ISFISF, whose operational lifetime is 50 years, is designed to host the conditioned LLW boxed in UNI CP-5.2 packages, 2,5 m long, 1.65 m wide, and 1,25 m high. The expected nominal inventory of waste is about 2100 packages, while the maximum storage is 2540 packages, thus a considerably large reserve capacity is available. The packages will be piled in stacks of maximum number of five. The LLW is going to be conditioned with a cement matrix. The maximum weight allowed for each package has been fixed at 16.000 kg. The total radioactivity inventory of waste to be hosted in the facility is about 30 TBq (mainly {beta}/{gamma} emitters). In order to satisfy the structural, seismic, and, most of all, radiological requirements, the external walls of the ISFISF are made of pre-fabricated panels, 32 cm thick, consisting of, from inside to outside, 20 cm of reinforced concrete, 7 cm of insulating material, and again 5 cm of reinforced concrete. For the same reason the roof is made with pre-fabricated panels in

  9. Development of decommissioning technology for nuclear fuel facility

    International Nuclear Information System (INIS)

    Tanimoto, Ken-ichi

    1998-01-01

    There are many kinds of objects for decommissioning and their properties are greatly different in respects of morphology, constituent materials, contamination history, etc. Therefore, the techniques for decontamination and dismantlement are required to have a great applicability. In addition, most of contamination nuclides have long half-life and so, it is desirable to rapidly take measures to stop or close a contaminated facility. In consideration of these characteristics developments of elementary techniques for decontamination have been attempted. This report summarized the present states of decommissioning technology for nuclear fuel facility. The function and performance of each elementary technique were examined through test operation and simulation was made for the important techniques of them aiming at generalization and optimization. For remote handling technology, two operation tools; 'metal splitting saw cutting tool' and 'plasma cutting tool' were produced and utilizations of these tools in combination with a robot for conveyance are under investigation now. (M.N.)

  10. The decommissioning of nuclear facilities; Le demantelement des installations nucleaires de base

    Energy Technology Data Exchange (ETDEWEB)

    Niel, J.Ch.; Rieu, J.; Lareynie, O.; Delrive, L.; Vallet, J.; Girard, A.; Duthe, M.; Lecomte, C.; Rozain, J.P.; Nokhamzon, J.G.; Davoust, M.; Eyraud, J.L.; Bernet, Ph.; Velon, M.; Gay, A.; Charles, Th.; Leschaeva, M.; Dutzer, M.; Maocec, Ch.; Gillet, G.; Brut, F.; Dieulot, M.; Thuillier, D.; Tournebize, F.; Fontaine, V.; Goursaud, V.; Birot, M.; Le Bourdonnec, Th.; Batandjieva, B.; Theis, St.; Walker, St.; Rosett, M.; Cameron, C.; Boyd, A.; Aguilar, M.; Brownell, H.; Manson, P.; Walthery, R.; Wan Laer, W.; Lewandowski, P.; Dorms, B.; Reusen, N.; Bardelay, J.; Damette, G.; Francois, P.; Eimer, M.; Tadjeddine, A.; Sene, M.; Sene, R

    2008-11-15

    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

  11. Pt. 1: Decommissioning of nuclear facilities. Pt. 2: Methods of decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Steinkilberg, W.

    1982-01-01

    In the present paper the different steps of dismantlement of nuclear facilities are dealt with. First the planning principles for decomminconing are discussed and then the planning of the reactorblock dismantlement in the FR2 research reactor is described. (RW)

  12. General principles underlying the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-03-01

    Previous statements on the use of the term 'decommissioning' by the International Atomic Energy Agency, the Atomic Energy Control Board, and the Advisory Committee on Nuclear Safety are reviewed, culminating in a particular definition for its use in this paper. Three decommissioning phases are identified and discussed, leading to eight general principles governing decommissioning including one related to financing

  13. Financial precautions for the decommissioning and dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Lukes, R.; Salje, P.; Feldmann, F.J.

    1978-01-01

    Starting from the fact that the disposal of nuclear-technical plants requires considerable means, the article asks if the financial guarantee for decommissioning and disposal should be requested before giving the licence. He shows the possibilities to ensure financial provisions and to describe their advantages and disadvantages. Planned decommissioning is dealt with separately from unplanned, decommissioning. (UN) [de

  14. Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1978-03-01

    Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase future decommissioning needs, the NRC staff began an in-depth review and re-evaluation of NRC's regulatory approach to decommissioning in 1975. Major technical studies on decommissioning have been initiated at Battelle Pacific Northwest Laboratory in order to provide a firm information base on the engineering methodology, radiation risks, and estimated costs of decommissioning light water reactors and associated fuel cycle facilities. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. The report sets forth in detail the NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

  15. The assessment system based on virtual decommissioning environments to reduce abnormal hazards from human errors for decommissioning of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan Seong; Moon, Jei Kwon; Choi, Byung Seon; Hyun, Dong jun; Lee, Jong Hwan; Kim, Ik June; Kang, Shin Young [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    Decommissioning of nuclear facilities has to be accomplished by assuring the safety of workers. So, it is necessary that before decommissioning, the exposure dose to workers has to be analyzed and assessed under the principle of ALARA (as low as reasonably achievable). Furthermore, to improve the proficiency of decommissioning environments, method and system need to be developed. To establish the plan of exposure dose to workers during decommissioning of nuclear facilities before decommissioning activities, it is necessary that assessment system is developed. This system has been successfully developed so that exposure dose to workers could be real-time measured and assessed in virtual decommissioning environments. It can be concluded that this system could be protected from accidents and enable workers to improve his familiarization about working environments. It is expected that this system can reduce human errors because workers are able to improve the proficiency of hazardous working environments due to virtual training like real decommissioning situations.

  16. National policies and regulations for decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1993-07-01

    This report, though produced as a follow-up to Safety Series No. 105, The Regulatory Process for the Decommissioning of Nuclear Facilities, is not primarily intended as guidance. Rather, its objective is to provide an overview of national decommissioning policies and regulatory practices as part of the background knowledge which is an essential precondition for good decision making. It discusses the reasons for the similarities and differences in national approach using specific examples but without giving preference to any particular scheme; it aims rather to provide factual, general information on the choices that have been or are being made, and why. As many Member States are in a transient situation between the case-by-case approach to decommissioning and the establishment of national policies, strategies and regulations, this seems the right moment to assess existing national practices worldwide and that is the purpose for which the document is issued at this time. The information gathered in this report is based on submissions by Member States which have developed or are in the process of developing decommissioning oriented policies and regulations. 29 refs

  17. Procedure for estimating facility decommissioning costs for non-fuel-cycle nuclear facilities

    International Nuclear Information System (INIS)

    Short, S.M.

    1988-01-01

    The Nuclear Regulatory Commission (NRC) staff has been reappraising its regulatory position relative to the decommissioning of nuclear facilities over the last several years. Approximately 30 reports covering the technology, safety, and costs of decommissioning reference nuclear facilities have been published during this period in support of this effort. One of these reports, Technology, Safety, and Costs of Decommissioning Reference Non-Fuel-Cycle Nuclear Facilities (NUREG/CR-1754), was published in 1981 and was felt by the NRC staff to be outdated. The Pacific Northwest Laboratory (PNL) was asked by the NRC staff to revise the information provided in this report to reflect the latest information on decommissioning technology and costs and publish the results as an addendum to the previous report. During the course of this study, the NRC staff also asked that PNL provide a simplified procedure for estimating decommissioning costs of non-fuel-cycle nuclear facilities. The purpose being to provide NRC staff with the means to easily generate their own estimate of decommissioning costs for a given facility for comparison against a licensee's submittal. This report presents the procedure developed for use by NRC staff

  18. The unit cost factors and calculation methods for decommissioning - Cost estimation of nuclear research facilities

    International Nuclear Information System (INIS)

    Kwan-Seong Jeong; Dong-Gyu Lee; Chong-Hun Jung; Kune-Woo Lee

    2007-01-01

    Available in abstract form only. Full text of publication follows: The uncertainties of decommissioning costs increase high due to several conditions. Decommissioning cost estimation depends on the complexity of nuclear installations, its site-specific physical and radiological inventories. Therefore, the decommissioning costs of nuclear research facilities must be estimated in accordance with the detailed sub-tasks and resources by the tasks of decommissioning activities. By selecting the classified activities and resources, costs are calculated by the items and then the total costs of all decommissioning activities are reshuffled to match with its usage and objectives. And the decommissioning cost of nuclear research facilities is calculated by applying a unit cost factor method on which classification of decommissioning works fitted with the features and specifications of decommissioning objects and establishment of composition factors are based. Decommissioning costs of nuclear research facilities are composed of labor cost, equipment and materials cost. Of these three categorical costs, the calculation of labor costs are very important because decommissioning activities mainly depend on labor force. Labor costs in decommissioning activities are calculated on the basis of working time consumed in decommissioning objects and works. The working times are figured out of unit cost factors and work difficulty factors. Finally, labor costs are figured out by using these factors as parameters of calculation. The accuracy of decommissioning cost estimation results is much higher compared to the real decommissioning works. (authors)

  19. Remote machine engineering applications for nuclear facilities decommissioning

    International Nuclear Information System (INIS)

    Toto, G.; Wyle, H.R.

    1983-01-01

    Decontamination and decommissioning of a nuclear facility require the application of techniques that protect the worker and the enviroment from radiological contamination and radiation. Remotely operated portable robotic arms, machines, and devices can be applied. The use of advanced systems should enhance the productivity, safety, and cost facets of the efforts; remote automatic tooling and systems may be used on any job where job hazard and other factors justify application. Many problems based on costs, enviromental impact, health, waste generation, and political issues may be mitigated by use of remotely operated machines. The work that man can not do or should not do will have to be done by machines

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1982-09-01

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

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

    International Nuclear Information System (INIS)

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

    1982-09-01

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

  2. The technological study on the decommissioning of nuclear facility, etc. in the Tokai Research Establishment

    International Nuclear Information System (INIS)

    Tomii, Hiroyuki; Matsuo, Kiyoshi; Shiraishi, Kunio; Kato, Rokuro; Watabe, Kozou; Higashiyama, Yutaka; Nagane, Satoru

    2005-03-01

    Since JPDR is dismantled and is removed, in Tokai Research Establishment, Japan Atomic Energy Research Institute, the dismantling of nuclear facility which finished the mission, etc. is advanced. At present, nuclear facility as a dismantling object count the approximately 20 facilities, and decommissioning plan of these facilities becomes an important problem, when the decommissioning countermeasure is considered. However, decommissioning techniques in proportion to various nuclear facility, etc. are clearly, and it has not been determined. In this report, the technical consideration on decommissioning techniques of nuclear facility promoted on the basis of this experience in future, while until now decommissioning experience and technical knowledge are arranged, etc. was added in order to appropriately and surely carry out decommissioning techniques and legal procedures, etc. (author)

  3. Policies and Strategies for the Decommissioning of Nuclear and Radiological Facilities

    International Nuclear Information System (INIS)

    2011-01-01

    This publication presents the main elements of policies and strategies for decommissioning activities of nuclear and radiological facilities. It is intended to help in facilitating proper and systematic planning, and safe, timely and cost effective implementation of all decommissioning activities. The policy establishes the principles for decommissioning and the strategy contains the approaches for the implementation of the policy. The publication will be a useful guide for strategic planners, waste managers, operators of facilities under decommissioning, regulators and other stakeholders.

  4. Evolution of some important principles on decommissioning of nuclear and radiation facilities

    International Nuclear Information System (INIS)

    Zhao Yamin; Wu Hao

    2004-01-01

    The paper introduces the evolution of some important principles on decommissioning of nuclear and radiation facilities. Decommissioning issue should not be regarded just as an end phase of the facilities operation, but should be taken into consideration as a part of whole operation process. The decommissioning plan and management should be considered in all phases of siting, design, construction and operation. A new term 'Facilitating Decommissioning' is introduced. Three stages principle of decommissioning (storage with surveillance, restricted release and unrestricted release) is being faded. The decommissioning implementation and related regulatory body should pay attention to these principal changes

  5. Decommissioning of a nuclear facility: the Brazilian case

    International Nuclear Information System (INIS)

    Menezes, Regina M.; Deppe, Alzira L.; Nunes, Marcos E.C.; Cardoso, Eliezer M.; Nouailhetas, Y.; Mouco, Charles; Ferreira, Paulo R.; Matta, Luiz E.da

    1996-01-01

    The first decommissioning process of a nuclear facility in Brazil, has being taken place in Usina de Santo Amaro (USAM), located in Sao Paulo whose physical and chemical milling activities of the monazitic sands were interrupted in June 1992. Nowadays, materials and equipment generated from Minerals Physical Treatment and Rare Earths Separation Sectors, classified as low level radiation areas, are in final phase of dismantling, monitoring and release to the internal backyard of the facility or segregation in controlled areas. This decommissioning phase is considered as pilot for the verification of procedures, follow up of pieces and application of suitable radioprotection measures for the future dismantling of the Chemical Treatment of Monazite Sector, which will involve higher risks regarding radioprotection and safety aspects. The criteria of discharge of areas and equipment established by CNEN are conservative enough to assure that the contamination is not released to the environment. CNEN's activities conducted at the surveillance of works involving the dismantling and decontamination of materials and equipment verifying that they are in accordance with the requirements established by the Brazilian Commission of Nuclear Energy. (author)

  6. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The paper on nuclear decommissioning was presented by Dr H. Lawton to a meeting of the British Nuclear Energy Society and Institution of Nuclear Engineers, 1986. The decommissioning work currently being undertaken on the Windscale advanced gas cooled reactor (WAGR) is briefly described, along with projects in other countries, development work associated with the WAGR operation and costs. (U.K.)

  7. A study on the influence of the regulatory requirements of a nuclear facility during decommissioning activities

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hee Seong; Park, Seung Kook; Park, Kook Nam; Hong, Yun Jeong; Park, Jang Jin; Choi, Jong Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The preliminary decommissioning plan should be written with various chapters such as a radiological characterization, a decommissioning strategy and methods, a design for decommissioning usability, a safety evaluation, decontamination and dismantling activities, radioactive waste management, an environmental effect evaluation, and fire protection. The process requirements of the decommissioning project and the technical requirements and technical criteria should comply with regulatory requirements when dismantling of a nuclear facility. The requirements related to safety in the dismantling of a nuclear facility refer to the IAEA safety serious. The present paper indicates that a decommissioning design and plan, dismantling activities, and a decommissioning project will be influenced by the decommissioning regulatory requirements when dismantling of a nuclear facility. We hereby paved the way to find the effect of the regulatory requirements on the decommissioning of a whole area from the decommissioning strategy to the radioactive waste treatment when dismantling a nuclear facility. The decommissioning requirements have a unique feature in terms of a horizontal relationship as well as a vertical relationship from the regulation requirements to the decommissioning technical requirements. The decommissioning requirements management will be conducted through research that can recognize a multiple relationship in the next stage.

  8. Use of data processing tools in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Petrasch, P.; Lukacs, G.

    1995-01-01

    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) [de

  9. On Younger Stakeholders and Decommissioning of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Tyszkiewicz, Bogumila; Labor, Bea

    2009-08-15

    In modern democratic countries, information sharing and effective and open communication concerning dismantling and decommissioning of of nuclear facilities as well as the management of nuclear waste are essential for the task to build the confidence required for any further development of nuclear energy. At the same time, it is often perceived that all decision making processes about nuclear energy policies are probably increasingly influenced by public opinion. Nuclear and radiation safety Authorities have a clear role in this regard to provide unbiased information on any health and safety related issues. In order to meet this need, it is necessary for Authorities and others to understand the values and opinions of the citizens, and especially the younger ones. They hold the key to the future at the same time as their perspective on these issues is the least understood. The need of greater public participation in decision making is becoming increasingly recognised the scientific as well as the political community. Many activities are carried out in order to stimulate to higher levels of public involvement in decision making in this active research area. Younger citizens is a stakeholder group that is often excluded in decision- making processes. The existence of large gaps between the involvement of older and younger stakeholders in decision making processes needs to be addressed, since such imbalances might otherwise lead to unequal opportunities between generations and limit the future consumption level of the coming generations. Another demanding task for the present generation is to assure that appropriate financial resources are injected into the Swedish Nuclear Waste Fund. It will thereby be possible for coming generations to undertake efficient measures in the decommissioning and dismantling of older nuclear facilities. To undertake such measures in line with the environmental and health codex is essential. An appropriate balance in this regard must be

  10. On Younger Stakeholders and Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Tyszkiewicz, Bogumila; Labor, Bea

    2009-08-01

    In modern democratic countries, information sharing and effective and open communication concerning dismantling and decommissioning of of nuclear facilities as well as the management of nuclear waste are essential for the task to build the confidence required for any further development of nuclear energy. At the same time, it is often perceived that all decision making processes about nuclear energy policies are probably increasingly influenced by public opinion. Nuclear and radiation safety Authorities have a clear role in this regard to provide unbiased information on any health and safety related issues. In order to meet this need, it is necessary for Authorities and others to understand the values and opinions of the citizens, and especially the younger ones. They hold the key to the future at the same time as their perspective on these issues is the least understood. The need of greater public participation in decision making is becoming increasingly recognised the scientific as well as the political community. Many activities are carried out in order to stimulate to higher levels of public involvement in decision making in this active research area. Younger citizens is a stakeholder group that is often excluded in decision- making processes. The existence of large gaps between the involvement of older and younger stakeholders in decision making processes needs to be addressed, since such imbalances might otherwise lead to unequal opportunities between generations and limit the future consumption level of the coming generations. Another demanding task for the present generation is to assure that appropriate financial resources are injected into the Swedish Nuclear Waste Fund. It will thereby be possible for coming generations to undertake efficient measures in the decommissioning and dismantling of older nuclear facilities. To undertake such measures in line with the environmental and health codex is essential. An appropriate balance in this regard must be

  11. Research in decommissioning techniques for nuclear fuel cycle facilities in JNC. 7. JWTF decommissioning techniques

    International Nuclear Information System (INIS)

    Ogawa, Ryuichiro; Ishijima, Noboru

    1999-02-01

    Decommissioning techniques such as radiation measuring and monitoring, decontamination, dismantling and remote handling in the world were surveyed to upgrading technical know-how database for decommissioning of Joyo Waste Treatment Facility (JWTF). As the result, five literatures for measuring and monitoring techniques, 14 for decontamination and 22 for dismantling feasible for JWTF decommissioning were obtained and were summarized in tables. On the basis of the research, practical applicability of those techniques to decommissioning of JWTF was evaluated. This report contains brief surveyed summaries related to JWTF decommissioning. (H. Itami)

  12. The IAEA review of methods of reducing occupational exposures during decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Alejnikov, V.E.

    1986-01-01

    International interest in decommissioning has increased rapidly in the last few years because of the large number of older facilities which are or soon will be retired from service and because of the many hundreds of new facilities which have been built or planned and will eventually require decommissioning. A state-of-the-art review of methods of reducing occupational exposures during decommissioning of nuclear facilities has been prepared recently by the International Atomic Energy Agency. The report concludes that decommissioning can be carried out without unacceptable impact on man or his environment. However, additional development is required to reduce occupational exposures during decommissioning. (author)

  13. R and D and Innovation Needs for Decommissioning Nuclear Facilities

    International Nuclear Information System (INIS)

    Farr, Harvey; LaGuardia, Thomas S.

    2014-01-01

    Nuclear decommissioning activities can greatly benefit from research and development (R and D) projects. This report examines applicable emergent technologies, current research efforts and innovation needs to build a base of knowledge regarding the status of decommissioning technology and R and D. This base knowledge can be used to obtain consensus on future R and D that is worth funding. It can also assist in deciding how to collaborate and optimise the limited pool of financial resources available among NEA member countries for nuclear decommissioning R and D. (authors)

  14. Accidental safety analysis methodology development in decommission of the nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Park, G. H.; Hwang, J. H.; Jae, M. S.; Seong, J. H.; Shin, S. H.; Cheong, S. J.; Pae, J. H.; Ang, G. R.; Lee, J. U. [Seoul National Univ., Seoul (Korea, Republic of)

    2002-03-15

    Decontamination and Decommissioning (D and D) of a nuclear reactor cost about 20% of construction expense and production of nuclear wastes during decommissioning makes environmental issues. Decommissioning of a nuclear reactor in Korea is in a just beginning stage, lacking clear standards and regulations for decommissioning. This work accident safety analysis in decommissioning of the nuclear facility can be a solid ground for the standards and regulations. For source term analysis for Kori-1 reactor vessel, MCNP/ORIGEN calculation methodology was applied. The activity of each important nuclide in the vessel was estimated at a time after 2008, the year Kori-1 plant is supposed to be decommissioned. And a methodology for risk analysis assessment in decommissioning was developed.

  15. Decommissioning of nuclear facilities in Europe and the experience of TUV SUD

    International Nuclear Information System (INIS)

    Hummel, Lothar; Kim, Duill; Ha, Taegun; Yang, Kyunghwa

    2012-01-01

    Many commercial nuclear facilities of the first generation will be taken out of operation in the near future. As of January 2012, total 19 prototype and commercial nuclear reactors have been decommissioned or are under dismantling in Germany. Most of decommissioning projects were successfully performed and a great deal of experience has been accumulated. Selecting a decommissioning strategy is a very important step at the beginning of the decision making process. According to IAEA requirements immediate dismantling is chosen as a preferred option in many countries today. It is associated with less uncertainty, positive political and social effect, and it can make use of existing operational experience and know-how. The availability of funds and final repository is of high importance for a decommissioning strategy selection. The time frame for the dismantling of nuclear facilities depends on the type, size and complexity of the individual project. TUV SUD, which is supervising most of nuclear power plants in Germany, has accumulated lots of experience by taking parts in decommissioning projects. It direct dismantling is chosen, actual light water reactor in Germany decommissioned to green field in approx. 10 years. The activities of TUV SUD cover from establishing the decommissioning concept to the clearance of the sites. This provides an overview of decommissioning projects of nuclear facilities in Europe, including a detail illustration of the German situation. Finally, some recommendations are suggested for the first decommissioning project based on the lessons and experiences derived from many decommissioning works in Europe

  16. Cost calculations for decommissioning and dismantling of nuclear research facilities

    International Nuclear Information System (INIS)

    Andersson, I.; Backe, S.; Cato, A.; Lindskog, S.; Efraimsson, H.; Iversen, Klaus; Salmenhaara, S.; Sjoeblom, R.

    2008-07-01

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

  17. Cost calculations for decommissioning and dismantling of nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, I. (Studsvik Nuclear AB (Sweden)); Backe, S. (Institute for Energy Technology (Norway)); Cato, A.; Lindskog, S. (Swedish Nuclear Power Inspectorate (Sweden)); Efraimsson, H. (Swedish Radiation Protection Authority (Sweden)); Iversen, Klaus (Danish Decommissioning (Denmark)); Salmenhaara, S. (VTT Technical Research Centre of Finland (Finland)); Sjoeblom, R. (Tekedo AB, (Sweden))

    2008-07-15

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

  18. Development of the decommissioning techniques for nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Tanimoto, Ken-ichi; Sugaya, Toshikatsu; Hara, Mitsuo; Kikuchi, Yutaka; Tobita, Hiroo; Enokido, Yuji

    1992-01-01

    Being developed the basement techniques such as measurement, decontamination, dismantling, remote handling and data base. For the elevating and systematizing the basement techniques, thinking over the application, forward to the facility decommissionings in the future, including the technique of waste treatment in WDF and the achievement using the dismantling and recycling technique in renewaling the research facilities. (author)

  19. Recycling of rare metals from the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Charlier, Frank; Dabruck, Jan Philipp

    2014-01-01

    The German Government decided in 2011 to phase out nuclear power. Thus, 17 power reactors will be shut down within the next 11 years and to be decommissioned. An interesting question is, in which extent rare metals of strategic economic importance can be recycled within the scope of decommissioning. To be named are valuable bulk metals like copper, aluminium and lead, but also rare metals like indium, niobium, vanadium, cobalt, or tin and rare earth metals. Due to high requirements in terms of material technology, materials found in nuclear reactor components are of particular importance when it comes to recycling. These include components of the primary cooling system (RPV-internals, control rods and grid-structures) components for process control systems and components from the non-nuclear part of reactors (pumps, valves, heat exchangers or boilers). Especially the radiologically controlled melt-down of metals is used as an alternative to free release or disposal. This process has some serious disadvantages, thus it seems to be appropriate optimizing the decommissioning process regarding recycling of valuable metals. The work schedule for pre-investigation is outlined for 18 months and can be summarized as follows: - Requesting design, operational and material data, - Data from a sample facility: detailed specification of used components, substances contained and data from related activation calculations, fluence-values and contamination, - Setting up a database to assign non-ferrous metals and components with additional data like activation and decay time possibly needed, concentration, distribution, total mass, aggregate state, state of chemical bonding and recyclability, - Determining the activation distribution to evaluate if a components is recyclable at all, thus: preparation of an MCNP-model, simulation of n-fluence and application of variance-reduction methods to optimize activation calculations, - Classification of recyclability considering the following

  20. A study on the decommissioning methods of nuclear facilities of North Korea

    International Nuclear Information System (INIS)

    Chung, U. S.; Park, J. H.; Park, S. K.; Hong, S. B.; Lee, G. W.

    2012-02-01

    For Korea, it is essential to participate in the decommissioning of North Korean nuclear facilities for Pu-based weapon program and to lead the project for the protection of the environments from the possible spread of nuclear contamination. Before, the studies for the verification of the North Korea nuclear facilities and for the technical preparation of the decommissioning of north Korea were conducted but the depth of the studies was not reached to the evaluation of the decommissioning project by the documentation of a decommissioning plan to the provision of the technical information to the policy decision makers. It is very helpful for understanding the characteristics of the decommissioning projects to formulate a possible dismantling scenario and to make a decommissioning plan. The cost and the periods estimated on the base of this scenario is more exact and the analysis for the selection of different policies will be possible

  1. The Study on Domestic and Foreign Cases for Decommissioning of DPRK Nuclear Facilities

    International Nuclear Information System (INIS)

    Baek, Ye Ji; Hhu, Joo Youn; Lee, Jung Hyun; Hwang, Yong Soo

    2016-01-01

    This study was able to analyze domestic and foreign cases, and collect data on the approximate amount of waste and time required time; however, data on applied technology, input manpower, required cost, and waste disposal method was insufficient. DPRK activities such as nuclear weapon development or nuclear testing not only threaten our country's security but also have an adverse effect on nuclear nonproliferation and security in the international society. Therefore, denuclearization of the DPRK is prior task that is essential to peace on the Korean Peninsula. The fundamental purpose of denuclearization of the DPRK is to safely decommission facilities related to developing nuclear weapons and to depose related radioactive waste and nuclear materials. Understanding descriptive references and physical properties of the facility and its purpose important for decommissioning nuclear facilities. Although it was impossible to collect data on DPRK nuclear facilities to perform complete decommissioning, we were able to understand the process used at DPRK nuclear facilities with open source data. This study has been conducted to establish overall measures for decommissioning DPRK nuclear facilities. DPRK nuclear facilities in this study include a IRT- 2000 type nuclear research reactor, a 5 MWe graphite moderated reactor, nuclear fuel fabrication facility, and a nuclear fuel reprocessing facility, which are considered as facilities that produce or manufacture nuclear materials needed for nuclear weapons or related to such activities.

  2. The Study on Domestic and Foreign Cases for Decommissioning of DPRK Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Baek, Ye Ji; Hhu, Joo Youn; Lee, Jung Hyun; Hwang, Yong Soo [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

    2016-05-15

    This study was able to analyze domestic and foreign cases, and collect data on the approximate amount of waste and time required time; however, data on applied technology, input manpower, required cost, and waste disposal method was insufficient. DPRK activities such as nuclear weapon development or nuclear testing not only threaten our country's security but also have an adverse effect on nuclear nonproliferation and security in the international society. Therefore, denuclearization of the DPRK is prior task that is essential to peace on the Korean Peninsula. The fundamental purpose of denuclearization of the DPRK is to safely decommission facilities related to developing nuclear weapons and to depose related radioactive waste and nuclear materials. Understanding descriptive references and physical properties of the facility and its purpose important for decommissioning nuclear facilities. Although it was impossible to collect data on DPRK nuclear facilities to perform complete decommissioning, we were able to understand the process used at DPRK nuclear facilities with open source data. This study has been conducted to establish overall measures for decommissioning DPRK nuclear facilities. DPRK nuclear facilities in this study include a IRT- 2000 type nuclear research reactor, a 5 MWe graphite moderated reactor, nuclear fuel fabrication facility, and a nuclear fuel reprocessing facility, which are considered as facilities that produce or manufacture nuclear materials needed for nuclear weapons or related to such activities.

  3. The scenario-based system of workers training to prevent accidents during decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, KwanSeong; Choi, ByungSeon; Moon, JeiKwon; Hyun, DongJun; Lee, JongHwan; Kim, IkJune; Kim, GeunHo; Seo, JaeSeok

    2014-01-01

    Highlights: • This paper is meant to develop the training system to prevent accidents during decommissioning of nuclear facilities. • Requirements of the system were suggested. • Data management modules of the system were designed. • The system was developed on virtual reality environment. - Abstract: This paper is meant to develop the training system to prevent accidents during decommissioning of nuclear facilities. Requirements of the system were suggested. Data management modules of the system were designed. The system was developed on virtual reality environment. The performance test of the system was proved to be appropriate to decommissioning of nuclear facilities

  4. Strategic aspects on waste management in decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Rannemalm, T.; Eliasson, S.; Larsson, A.; Lidar, P.; Bergh, N.; Hedin, G.

    2017-01-01

    A team composed of experts from the facility owner OKG, Westinghouse and Studsvik (today Cyclife Sweden and Studsvik Consulting) was asked to develop a basis for decision on an overall strategy for the management of the material and waste arising from the decommissioning of two BWR NPPs at the Oskarshamn site in Sweden. To be able to provide a good basis for decision the full waste management chain from generation to disposition, i.e. clearance or disposal had to be assessed, categorised, quantified and analysed with regards to costs, environmental impact and risks. A systematic approach was applied taking benefit of the decommissioning studies made previously for the two facilities, the decommissioning concepts developed by Ndcon (the partnership in decommissioning between Studsvik and Westinghouse) and the combined knowledge and experience in the project team. In total 4 different waste management concepts were compared individually and in combinations. The four concepts evaluated were based on: direct disposal in the national geological repository; treatment of the waste for volume reduction and where applicable clearance in an external waste treatment facility; decontamination and clearance in an on-site waste treatment facility; direct disposal in a near surface repository at the NPP site. It was important to be able to compare the different options in a quantifiable way. Therefore the project team set up a matrix with parameters for the different options gained from the utility, the national waste management company, external vendors and the experience of the team. In this way a quantitative analysis could be done with the four different waste management options. In addition to the quantitative analysis the team summarised decades of experience in radioactive waste management and decommissioning recommendations and risk analyses. Special attention was given to risk mitigation and redundancy in the waste management chain. The development of an overall waste

  5. Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1978-12-01

    The present decommissioning regulations contained in Sections 50.33(f) and 50.82 of 10 CFR part 50 require applicants for power reactor operating licenses to demonstrate that they can obtain the funds needed to meet both operating costs and estimated costs of shutdown and decommissioning. The development of detailed, specific decommissioning plans for nuclear power plants is not currently required until the licensee seeks to terminate his operating license. Recognizing that the current generation of large commercial reactors and supporting nuclear facilities would substantially increase the need for future decommissionings, the NRC staff began an in-depth review and reevaluation of NRC's regulatory approach to decommissioning in 1975. The Nuclear Regulatory Commission is now considering development of a more explicit overall policy for nuclear facility decommissioning and amending its regulations in 10 CFR Parts 30, 40, 50, and 70 to include more specific guidance on decommissioning criteria for production and utilization facility licensees and byproduct, source, and special nuclear material licensees. In response to comments from the public and states, and to information gained during the initial stage of execution of the plan, several modifications of the plan are now required. The revised overall report sets forth in detail the current NRC staff plan for the development of an overall NRC policy on decommissioning of nuclear facilities

  6. Status of the support researches for the regulation of nuclear facilities decommissioning in Japan

    International Nuclear Information System (INIS)

    Masuda, Yusuke; Iguchi, Yukihiro; Kawasaki, Satoru; Kato, Masami

    2011-01-01

    In Japan, 4 nuclear power stations are under decommissioning and some nuclear fuel cycle facilities are expected to be decommissioned in the future. On the other hand, the safety regulation of decommissioning of nuclear facilities was changed by amending act in 2005. An approval system after review process of decommissioning plan was adopted and applied to the power stations above. In this situation, based on the experiences of the new regulatory system, the system should be well established and moreover, it should be improved and enhanced in the future. Nuclear Industry and Safety Agency (NISA) is in charge of regulation of commercial nuclear facilities in Japan and decommissioning of them is included. Japan Nuclear Energy Safety Organization (JNES) is in charge of technical supports for NISA as a TSO (Technical Support Organization) also in this field. As for decommissioning, based on regulatory needs, JNES has been continuing research activities from October 2003, when JNES has been established. Considering the 'Prioritized Nuclear Safety Research Plan (August 2009)' of the Nuclear Safety Commission of Japan and the situation of operators facilities, 'Regulatory Support Research Plan between FY 2010-2014' was established in November 2009, which shows the present regulatory needs and a research program. This program consists of researches for 1. review process of decommissioning plan of power reactors, 2. review process of decommissioning plan of nuclear fuel cycle facilities, 3. termination of license at the end of decommissioning and 4. management of decommissioning waste. For the item 1, JNES studied safety assessment methods of dismantling, e.g. obtaining data and analysis of behavior of dust diffusion and risk assessment during decommissioning, which are useful findings for the review process. For the item 2, safety requirements for the decommissioning of nuclear fuel cycle facilities was compiled, which will be used in the future review. For the item 3

  7. Decommissioning of nuclear facilities by the United States Department of Energy Oak Ridge Field Office

    International Nuclear Information System (INIS)

    DeLozier, M.F.P.

    1992-01-01

    The Oak Ridge Field Office of the United States Department of Energy is projecting one of the largest decommissioning efforts in the nation during the next ten to twenty years. The nuclear facilities are varied with respect to the types of contaminants and types of structures and equipment involved. The facilities planned for decommissioning include 26 ORNL facilities (e.g., OGR, HRE, MSRE), 70 facilities at Oak Ridge K25 site, and the Y-12 plant at Oak Ridge. Innovative technologies are required to decommission the facilities and dispose of the waste generated. (R.P.)

  8. Nuclear decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Lawton, H.

    1987-02-01

    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 UK, good progress has been made with the WAGR 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.

  9. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1987-01-01

    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 UK, good progress has been made with the WAGR 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)

  10. Development of the Decontamination and Decommissioning Technology for Nuclear Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Moon, J. K.; Won, C. H.

    2010-04-01

    The research results could be used for a design of a remote ablation decontamination system and ultimately applicable for an decontamination of high radiation facilities such as the DUPIC and PIEF. The evaluation technology of decommissioning process must be developed and will be used for the ALARA planning tool of decommissioning process and demonstrated for tools of decommissioning equipment. Also, this technology can be used for tools workplaces with high work difficulty such as large-scale chemical plant, under water and space. It is expected that the technology for a volume reduction and self-disposal of dismantled concrete wastes can be contributed to the establishment of a management plan for radioactive dismantled concrete wastes through the minimization of final waste volume

  11. Development of decommissioning management system for nuclear fuel cycle facilities (DECMAN)

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Ryuichirou; Ishijima, Noboru; Tanimoto, Ken-ichi [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1999-04-01

    In making a plan of decommissioning of nuclear fuel facilities, it is important to optimize the plan on the standpoint of a few viewpoints, that is, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost (they are called evaluation indexes). In the midst of decommissioning, the decommissioning plan would be modified suitably to optimize the evaluation indexes adjusting to progress of the decommissioning. The decommissioning management code (DECMAN), that is support system on computer, has been developed to assist the decommissioning planning. The system calculates the evaluation indexes quantitatively. The system consists of three fundamental codes, facility information database code, technical know-how database code and index evaluation code, they are composed using Oracle' database and 'G2' expert system. The functions of the system are as follows. (1) Facility information database code. Information of decommissioning facility and its rooms, machines and pipes in the code. (2) Technical know-how database code. Technical Information of tools to use in decommissioning work, cutting, dose measure, and decontamination are there. (3) Index evaluation code. User build decommissioning program using above two database codes. The code evaluates five indexes, the amount of working days, workers, radioactive waste, exposure dose of worker, and cost, on planning decommissioning program. Results of calculation are shown in table, chart, and etc. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-09-01

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

  13. Decommissioning Facility Characterization DB System

    International Nuclear Information System (INIS)

    Park, S. K.; Ji, Y. H.; Park, J. H.; Chung, U. S.

    2010-01-01

    Basically, when a decommissioning is planed for a nuclear facility, an investigation into the characterization of the nuclear facility is first required. The results of such an investigation are used for calculating the quantities of dismantled waste and estimating the cost of the decommissioning project. In this paper, it is presented a computer system for the characterization of nuclear facilities, called DEFACS (DEcommissioning FAcility Characterization DB System). This system consists of four main parts: a management coding system for grouping items, a data input system, a data processing system and a data output system. All data is processed in a simplified and formatted manner in order to provide useful information to the decommissioning planner. For the hardware, PC grade computers running Oracle software on Microsoft Windows OS were selected. The characterization data results for the nuclear facility under decommissioning will be utilized for the work-unit productivity calculation system and decommissioning engineering system as basic sources of information

  14. Decommissioning Facility Characterization DB System

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-10-15

    Basically, when a decommissioning is planed for a nuclear facility, an investigation into the characterization of the nuclear facility is first required. The results of such an investigation are used for calculating the quantities of dismantled waste and estimating the cost of the decommissioning project. In this paper, it is presented a computer system for the characterization of nuclear facilities, called DEFACS (DEcommissioning FAcility Characterization DB System). This system consists of four main parts: a management coding system for grouping items, a data input system, a data processing system and a data output system. All data is processed in a simplified and formatted manner in order to provide useful information to the decommissioning planner. For the hardware, PC grade computers running Oracle software on Microsoft Windows OS were selected. The characterization data results for the nuclear facility under decommissioning will be utilized for the work-unit productivity calculation system and decommissioning engineering system as basic sources of information

  15. Methods for reducing occupational exposures during the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1987-01-01

    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 facilities which have been or soon will be retired from service. This report is a review of the current state of knowledge concerning methods for reducing occupational exposures during the decommissioning of nuclear facilities. This report focuses on water cooled nuclear power plants but, in addition, other major nuclear facilities are briefly discussed to determine how they differ from nuclear power plants in this regard. The information presented should be useful to those responsible for or interested in designing or constructing nuclear facilities or in the planning or implementing of the decommissioning of such installations. 59 refs, 1 tab

  16. Contaminated Land Remediation on decommissioned nuclear facilities: an optimized approach

    International Nuclear Information System (INIS)

    Sauer, Emilie

    2016-01-01

    The site of the Monts d'Arree located in Brennilis in the area of Brittany in France is a former 70 MWe heavy water reactor. EDF is now in charge of its decommissioning. The effluent treatment facility (STE) is currently being dismantled. As the future use of the site will exclude any nuclear activity, EDF is taking site release into consideration. Therefore a land management strategy for the land and soil is needed. An optimized approach is being proposed for the STE, to the French Regulator. In France, there is no specific regulation related to contaminated land (either radiologically contaminated or chemically contaminated). The French Nuclear Safety Authority's doctrine for radioactively contaminated land is a reference approach which involves complete clean-up, removing any trace of artificial radioactivity in the ground. If technical difficulties are encountered or the quantity of radioactive waste produced is too voluminous, an optimised clean-up can be implemented. EDF has been engaged since 2008 in drawing up a common guideline with other French nuclear operators (CEA and AREVA). The operators' guideline proposed the first steps to define how to optimise nuclear waste and to carry out a cost-benefits analysis. This is in accordance with the IAEA's prescriptions. Historically, various incidents involving effluent drum spills caused radiological contamination in the building platform and the underlying soil. While conducting the decontamination works in 2004/2005, it was impossible to remove all contamination (that went deeper than expected). A large characterization campaign was carried out in order to map the contamination. For the site investigation, 34 boreholes were drilled from 2 to 5 m under the building platform and 98 samples were analyzed to search for gamma, beta and alpha emitters. With the results, the contamination was mapped using a geostatistical approach developed by Geovariances TM . Main results were: - Soils are

  17. Development of training system to prevent accidents during decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, Kwanseong; Moon, Jeikwon; Choi, Byungseon; Hyun, Dongjun; Lee, Jonghwan; Kim, Ikjune; Kim, Geunho; Seo, Jaeseok

    2014-01-01

    Decommissioning workers need familiarization with working environments because working environment is under high radioactivity and work difficulty during decommissioning of nuclear facilities. On-the-job training of decommissioning works could effectively train decommissioning workers but this training approach could consume much costs and poor modifications of scenarios. The efficiency of virtual training system could be much better than that of physical training system. This paper was intended to develop the training system to prevent accidents for decommissioning of nuclear facilities. The requirements for the training system were drawn. The data management modules for the training system were designed. The training system of decommissioning workers was developed on the basis of virtual reality which is flexibly modified. The visualization and measurement in the training system were real-time done according as changes of the decommissioning scenario. It can be concluded that this training system enables the subject to improve his familiarization about working environments and to prevent accidents during decommissioning of nuclear facilities

  18. Development of training system to prevent accidents during decommissioning of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwanseong; Moon, Jeikwon; Choi, Byungseon; Hyun, Dongjun; Lee, Jonghwan; Kim, Ikjune; Kim, Geunho; Seo, Jaeseok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Decommissioning workers need familiarization with working environments because working environment is under high radioactivity and work difficulty during decommissioning of nuclear facilities. On-the-job training of decommissioning works could effectively train decommissioning workers but this training approach could consume much costs and poor modifications of scenarios. The efficiency of virtual training system could be much better than that of physical training system. This paper was intended to develop the training system to prevent accidents for decommissioning of nuclear facilities. The requirements for the training system were drawn. The data management modules for the training system were designed. The training system of decommissioning workers was developed on the basis of virtual reality which is flexibly modified. The visualization and measurement in the training system were real-time done according as changes of the decommissioning scenario. It can be concluded that this training system enables the subject to improve his familiarization about working environments and to prevent accidents during decommissioning of nuclear facilities.

  19. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1987-01-01

    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)

  20. The planning of decommissioning activities within nuclear facilities - Generating a Baseline Decommissioning Plan

    International Nuclear Information System (INIS)

    Meek, N.C.; Ingram, S.; Page, J.

    2003-01-01

    BNFL Environmental Services has developed planning tools to meet the emerging need for nuclear liabilities management and decommissioning engineering both in the UK and globally. It can provide a comprehensive baseline planning service primarily aimed at nuclear power stations and nuclear plant. The paper develops the following issues: Decommissioning planning; The baseline decommissioning plan;The process; Work package; Compiling the information; Deliverables summary; Customer Benefits; - Planning tool for nuclear liability life-cycle management; - Robust and reliable plans based upon 'real' experience; - Advanced financial planning; - Ascertaining risk; - Strategy and business planning. The following Deliverables are mentioned:1. Site Work Breakdown Structure; 2. Development of site implementation strategy from the high level decommissioning strategy; 3. An end point definition for the site; 4. Buildings, operational systems and plant surveys; 5. A schedule of condition for the site; 6. Development of technical approach for decommissioning for each work package; 7. Cost estimate to WBS level 5 for each work package; 8. Estimate of decommissioning waste arisings for each work package; 9. Preparation of complete decommissioning programme in planning software to suit client; 10. Risk modelling of work package and overall project levels; 11. Roll up of costs into an overall cost model; 12. Cash flow, waste profiling and resource profiling against the decommissioning programme; 13. Preparation and issue of Final Report. Finally The BDP process is represented by a flowchart listing the following stages: [Power Station project assigned] → [Review project and conduct Characterisation review of power station] → [Identify work packages] → [Set up WBS to level 3] → [Assign work packages] → [Update WBS to level 4] →[Develop cost model] → [Develop logic network] → [Develop risk management procedure] ] → [Develop project strategy document]→ [Work package

  1. Decommissioning of the Nuclear Licensed Facilities at the Fontenay aux Roses CEA Center

    International Nuclear Information System (INIS)

    Jeanjacques, Michel; Piketty, Laurence; Mandard, Lionel; Pedron, Guy; Boissonneau, Jean Francois; Fouquereau, Alain; Pichereau, Eric; Lethuaire, Nathalie; Estivie, David; Binet, Cedric; Meden, Igor

    2008-01-01

    This is a summary of the program for the decommissioning of all the CEA's facilities in Fontenay aux Roses. The particularity of this center is that it is located in a built-up area. Taking into account the particularities of the various buildings and the levels of radioactivity in them, it was possible to devise a coherent, optimized program for the CEA-FAR licensed nuclear facility decommissioning operations

  2. Challenges in the management of decommission waste of nuclear facilities in Ghana

    International Nuclear Information System (INIS)

    Glover, E.T.; Fletcher, J.J.

    2002-01-01

    It is inevitable that every nuclear facility must one day be safely decommissioned. When considering decommissioning, large amounts of radioactive and non-radioactive waste have to be taken into account. Disposal of such materials can have large economic impact on the overall decommissioning cost. In developing countries like Ghana, the perception of environmental protection through waste management, is often not very high as compared to many other pressing needs. Therefore limited resources are allocated for environmental problems. Ghana operates a tank-in- pool type research reactor, 30kW output for research in neutron activation analysis, radioisotope preparation, education and training, a radiotherapy unit that utilizes a 185TBq Co-60 radioactive sources for the treatment of cancer and a gamma irradiation facility which utilizes 1.85PBq Co-60 radioactive source for the irradiation of various materials. All these facilities are operating without designed decommissioning in mind, an inadequate waste management infrastructure as well as a lack of a repository to handling the resulting waste. It is today's beneficials of the nuclear facility that has to deal with the legacies of the future decommissioning activities. The paper outlines some of the challenges and issues to be expected in the management of waste from future decommissioning of nuclear facilities in Ghana with the absence of a waste management infrastructure and inadequate financial resources. The paper puts forth a concept to perform meaningful and significant plans whilst the facilities are still operating. (author)

  3. Record keeping for the decommissioning of nuclear facilities: Guidelines and experience

    International Nuclear Information System (INIS)

    2002-01-01

    This report covers record keeping for the decommissioning of nuclear facilities. Nuclear facilities include large commercial facilities such as nuclear power plants or chemical nuclear facilities (e.g. for fabrication and reprocessing), but also include smaller facilities such as research reactors and medical, industrial and other research facilities. Special attention may be needed for these small facilities owing to factors such as the low priority given to decommissioning by research teams and the possibility of poorly recorded structural and operational changes. A focus on research reactors is also important because of their widespread distribution. Two IAEA TECDOCs address record keeping for radioactive waste management and disposal facilities, and therefore these areas are not covered in this report. The objective of this report is to provide information, experience and assistance on how to identify, update as needed and maintain records to assist in the decommissioning of nuclear facilities, including for the decommissioning plan. This report is intended to be useful to policy makers, regulators, owners, operators, decommissioning contractors and other interested parties. Record keeping is an integral part of overall QA or quality management programmes, and this is emphasized in this report. This report also indicates the possible consequences of not maintaining adequate records. This report describes the needs and the sources of the records for decommissioning (Section 3) and the process of identifying and selecting these records (Section 4). Section 5 considers the records from the decommissioning process itself and their retention, while Section 6 deals with QA, organization and responsibilities. The Records Management System (RMS) is dealt with in Section 7 and the management of new records in Section 8. A summary of observations is included in Section 9. The report is complemented by an appendix and annexes that describe case histories

  4. Deregulation in the field of decommissioning and dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Kurz, A.

    1994-05-01

    The report comprises two articles covering current topics of the decommissioning and dismantling of nuclear facilities. In the first article written by Kurz, the legal standards are listed together with conclusions and proposals regarding their implementation for the further development of this field of law. The article by Baumgaertel is aimed at evaluating the regulations governing nuclear technology as regards their applicability to the decommissioning and dismantling of nuclear facilities. These articles shall contribute to the discussions taking place in this field at the moment. As a result, an appropriate and project-specific application of the legal provisions and not legally binding (technical) regulations in the field of nuclear technology (deregulation) in the licensing procedures required for the decommissioning and dismantling of nuclear facilities is requested by the authors. (orig.) [de

  5. Decommissioning and decontamination of licensed reactor facilities and demonstration nuclear power plants

    International Nuclear Information System (INIS)

    Lear, G.; Erickson, P.B.

    1975-01-01

    Decommissioning of licensed reactors and demonstration nuclear power plants has been accomplished by mothballing (protective storage), entombment, and dismantling or a combination of these three. The alternative selected by a licensee seems to be primarily based on cost. A licensee must, however, show that the decommissioning process provides adequate protection of the health and safety of the public and no adverse impact on the environment. To date the NRC has approved each of the alternatives in the decommissioning of different facilities. The decommissioning of small research reactors has been accomplished primarily by dismantling. Licensed nuclear power plants, however, have been decommissioned primarily by being placed in a mothballed state in which they continue to retain a reactor license and the associated licensee responsibilities

  6. Survey of technology for decommissioning of nuclear fuel cycle facilities. 8. Remote handling and cutting techniques

    Energy Technology Data Exchange (ETDEWEB)

    Ogawa, Ryuichiro; Ishijima, Noboru [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1999-03-01

    In nuclear fuel cycle facility decommissioning and refurbishment, the remote handling techniques such as dismantling, waste handling and decontamination are needed to reduce personnel radiation exposure. The survey research for the status of R and D activities on remote handling tools suitable for nuclear facilities in the world and domestic existing commercial cutting tools applicable to decommissioning of the facilities was conducted. In addition, the drive mechanism, sensing element and control system applicable to the remote handling devices were also surveyed. This report presents brief surveyed summaries. (H. Itami)

  7. Planning, Management and Organizational Aspects of the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    2013-08-01

    Many old reactors and other nuclear facilities worldwide are being actively dismantled or are candidates for decommissioning in the near term. A significant number of these facilities are located in Member States having little experience or expertise in planning and implementing state of the art decommissioning projects. Planning, management and organization are critical for the success of such projects. The main objective of IAEA technical activities related to decommissioning is to promote the exchange of lessons learned, thereby contributing to successful planning and implementation of decommissioning projects. Imperative for success is a better understanding of the decision making process, the comparison and selection of decommissioning plans and organizational provisions, and relevant issues affecting the entire decommissioning process. Topics addressed in this publication include details on development of the decommissioning plan, structuring of key project tasks, organizing the project management team, identifying key staffing positions and determining required workforce skills, and managing the transition from an operational phase to the decommissioning phase. It is expected that this project, and in particular the papers collected in this publication, will draw Member States' attention to the practicality and achievability of timely planning and smooth management of decommissioning projects, especially for smaller projects. Concluding reports summarizing the work undertaken under the aegis of a coordinated research project (CRP) on planning, management and organizational aspects in the decommissioning of nuclear facilities, and presented at the third and final research coordination meeting (RCM) held in Da Lat, Vietnam, 5-9 September 2011, are included in this publication. Operating experience and lessons learned during full scale applications, as well as national programmes and plans, are among the most significant achievements of the CRP and have been

  8. Planning, Management and Organizational Aspects of the Decommissioning of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Many old reactors and other nuclear facilities worldwide are being actively dismantled or are candidates for decommissioning in the near term. A significant number of these facilities are located in Member States having little experience or expertise in planning and implementing state of the art decommissioning projects. Planning, management and organization are critical for the success of such projects. The main objective of IAEA technical activities related to decommissioning is to promote the exchange of lessons learned, thereby contributing to successful planning and implementation of decommissioning projects. Imperative for success is a better understanding of the decision making process, the comparison and selection of decommissioning plans and organizational provisions, and relevant issues affecting the entire decommissioning process. Topics addressed in this publication include details on development of the decommissioning plan, structuring of key project tasks, organizing the project management team, identifying key staffing positions and determining required workforce skills, and managing the transition from an operational phase to the decommissioning phase. It is expected that this project, and in particular the papers collected in this publication, will draw Member States' attention to the practicality and achievability of timely planning and smooth management of decommissioning projects, especially for smaller projects. Concluding reports summarizing the work undertaken under the aegis of a coordinated research project (CRP) on planning, management and organizational aspects in the decommissioning of nuclear facilities, and presented at the third and final research coordination meeting (RCM) held in Da Lat, Vietnam, 5-9 September 2011, are included in this publication. Operating experience and lessons learned during full scale applications, as well as national programmes and plans, are among the most significant achievements of the CRP and have been

  9. Risk assessment on hazards for decommissioning safety of a nuclear facility

    International Nuclear Information System (INIS)

    Jeong, Kwan-Seong; Lee, Kune-Woo; Lim, Hyeon-Kyo

    2010-01-01

    A decommissioning plan should be followed by a qualitative and quantitative safety assessment of it. The safety assessment of a decommissioning plan is applied to identify the potential (radiological and non-radiological) hazards and risks. Radiological and non-radiological hazards arise during decommissioning activities. The non-radiological or industrial hazards to which workers are subjected during a decommissioning and dismantling process may be greater than those experienced during an operational lifetime of a facility. Workers need to be protected by eliminating or reducing the radiological and non-radiological hazards that may arise during routine decommissioning activities and as well as during accidents. The risk assessment method was developed by using risk matrix and fuzzy inference logic, on the basis of the radiological and non-radiological hazards for a decommissioning safety of a nuclear facility. Fuzzy inference of radiological and non-radiological hazards performs a mapping from radiological and non-radiological hazards to risk matrix. Defuzzification of radiological and non-radiological hazards is the conversion of risk matrix and priorities to the maximum criterion method and the mean criterion method. In the end, a composite risk assessment methodology, to rank the risk level on radiological and non-radiological hazards of the decommissioning tasks and to prioritize on the risk level of the decommissioning tasks, by simultaneously combining radiological and non-radiological hazards, was developed.

  10. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    Energy Technology Data Exchange (ETDEWEB)

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi [Ministry of Science and Technology (MoST), Al-Jadraya, P.O. Box 0765, Baghdad (Iraq); Cochran, John R. [Sandia National Laboratories1, New Mexico, Albuquerque New Mexico 87185 (United States)

    2013-07-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the

  11. Radioactive Waste Management and Nuclear Facility Decommissioning Progress in Iraq - 13216

    International Nuclear Information System (INIS)

    Al-Musawi, Fouad; Shamsaldin, Emad S.; Jasim, Hadi; Cochran, John R.

    2013-01-01

    Management of Iraq's radioactive wastes and decommissioning of Iraq's former nuclear facilities are the responsibility of Iraq's Ministry of Science and Technology (MoST). The majority of Iraq's former nuclear facilities are in the Al-Tuwaitha Nuclear Research Center located a few kilometers from the edge of Baghdad. These facilities include bombed and partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. Within these facilities are large numbers of silos, approximately 30 process or waste storage tanks and thousands of drums of uncharacterised radioactive waste. There are also former nuclear facilities/sites that are outside of Al-Tuwaitha and these include the former uranium processing and waste storage facility at Jesira, the dump site near Adaya, the former centrifuge facility at Rashdiya and the former enrichment plant at Tarmiya. In 2005, Iraq lacked the infrastructure needed to decommission its nuclear facilities and manage its radioactive wastes. The lack of infrastructure included: (1) the lack of an organization responsible for decommissioning and radioactive waste management, (2) the lack of a storage facility for radioactive wastes, (3) the lack of professionals with experience in decommissioning and modern waste management practices, (4) the lack of laws and regulations governing decommissioning or radioactive waste management, (5) ongoing security concerns, and (6) limited availability of electricity and internet. Since its creation eight years ago, the MoST has worked with the international community and developed an organizational structure, trained staff, and made great progress in managing radioactive wastes and decommissioning Iraq's former nuclear facilities. This progress has been made, despite the very difficult implementing conditions in Iraq. Within MoST, the Radioactive Waste Treatment and Management Directorate (RWTMD) is responsible for waste management and the Iraqi Decommissioning

  12. Decommissioning commercial nuclear facilities: a review and analysis of current regulations

    International Nuclear Information System (INIS)

    Schilling, A.H.; Lippek, H.E.; Tegeler, P.D.; Easterling, J.D.

    1979-08-01

    This report describes and analyzes the regulatory requirements and guidelines applicable to the decommissioning of commercial light water reactors, other commercial nuclear fuel cycle facilities, and byproduct utilization facilities, as contained principally in the United States Code, the United States Code of Federal Regulations, and the United States Nuclear Regulatory Commission's Regulatory Guides. State requirements are discussed where appropriate. The report provides general background informaion to license applicants and to other interested parties. Included is an outline of procedural steps required of an applicant to comply with decommissioning regulatory requiremets

  13. The decommissioning concept for nuclear facilities in Ukraine

    International Nuclear Information System (INIS)

    Yaroslavtsev, G.F.; Korchagin, P.A.

    2000-01-01

    The basic task of the conception is a formulation of the basic directions and priorities, terms of schedules and plans, calculation of costs of works on endurance, preservations, dismantlement of nuclear facilities and returning of territories in the unlimited usage. Independent of the development rate of nuclear energy in Ukraine, this problem must now be solved. (author)

  14. The ALARA assessment system based on virtual concurrent environment for decommissioning of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, KwanSeong; Moon, JeiKwon; Choi, ByungSeon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kang, ShinYoung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    This paper is intended to suggest the method and assess the exposure dose to workers in virtual decommissioning environments. To simulate a lot of decommissioning scenarios, decommissioning environments were designed in virtual reality. To simulate and assess the exposure dose to workers, human model also was designed in virtual environments. These virtual decommissioning environments made it possible to real-time simulate and assess the exposure dose to workers. To establish the plan of exposure dose to workers during decommissioning of nuclear facilities before decommissioning activities, it is necessary that assessment system is developed. This system has been successfully developed so that exposure dose to workers could be real-time measured and assessed in virtual decommissioning environments. It can be concluded that this system could be protected from accidents and enable workers to improve his familiarization about working environments. It is expected that this system can reduce human errors because workers are able to improve the proficiency of hazardous working environments due to virtual training like real decommissioning situations.

  15. The ALARA assessment system based on virtual concurrent environment for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, KwanSeong; Moon, JeiKwon; Choi, ByungSeon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kang, ShinYoung

    2016-01-01

    This paper is intended to suggest the method and assess the exposure dose to workers in virtual decommissioning environments. To simulate a lot of decommissioning scenarios, decommissioning environments were designed in virtual reality. To simulate and assess the exposure dose to workers, human model also was designed in virtual environments. These virtual decommissioning environments made it possible to real-time simulate and assess the exposure dose to workers. To establish the plan of exposure dose to workers during decommissioning of nuclear facilities before decommissioning activities, it is necessary that assessment system is developed. This system has been successfully developed so that exposure dose to workers could be real-time measured and assessed in virtual decommissioning environments. It can be concluded that this system could be protected from accidents and enable workers to improve his familiarization about working environments. It is expected that this system can reduce human errors because workers are able to improve the proficiency of hazardous working environments due to virtual training like real decommissioning situations

  16. Life time estimation of SSCs for decommissioning safety of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, Kwan-Seong; Lee, Kune-Woo; Moon, Jei-Kwon; Jeong, Seong-Young; Lee, Jung-Jun; Kim, Geun-Ho; Choi, Byung-Seon

    2012-01-01

    Highlights: ► This paper suggests the expectation algorithm of SSCs life time for decommissioning safety of nuclear facilities. ► The life time of SSCs can be estimated by using fuzzy theory. ► The estimated results depend on the membership functions and performance characteristic functions. - Abstract: This paper suggests the estimation algorithm for life time of structure, system and components (SSCs) for decommissioning safety of nuclear facilities using the performance data of linguistic languages and fuzzy theory. The fuzzy estimation algorithm of life time can be easily applicable but the estimated results depend on the relevant membership functions and performance characteristic functions. This method will be expected to be very useful for maintenance and decommissioning of nuclear facilities’ SSCs as a safety assessment tool.

  17. Development of the scenario-based training system to reduce hazards and prevent accidents during decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, KwanSeong; Choi, Jong-Won; Moon, JeiKwon; Choi, ByungSeon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kim, GeunHo; Kang, ShinYoung

    2015-01-01

    Decommissioning of nuclear facilities has to be accomplished by assuring the safety of workers. Decommissioning workers need familiarization with working environments because working environment is under high radioactivity and work difficulty during decommissioning of nuclear facilities. On-the-job training of decommissioning works could effectively train decommissioning workers but this training approach could consume much costs and poor modifications of scenarios. The efficiency of virtual training system could be much better than that of physical training system. This paper was intended to develop the training system to prevent accidents for decommissioning of nuclear facilities. The requirements for the training system were drawn. The data management modules for the training system were designed. The training system of decommissioning workers was developed on the basis of virtual reality which is flexibly modified. The visualization and measurement in the training system were real-time done according as changes of the decommissioning scenario. It can be concluded that this training system enables the subject to improve his familiarization about working environments and to prevent accidents during decommissioning of nuclear facilities. In the end, the safety during decommissioning of nuclear facilities will be guaranteed under the principle of ALARA

  18. Development of the scenario-based training system to reduce hazards and prevent accidents during decommissioning of nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, KwanSeong; Choi, Jong-Won; Moon, JeiKwon; Choi, ByungSeon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kim, GeunHo; Kang, ShinYoung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    Decommissioning of nuclear facilities has to be accomplished by assuring the safety of workers. Decommissioning workers need familiarization with working environments because working environment is under high radioactivity and work difficulty during decommissioning of nuclear facilities. On-the-job training of decommissioning works could effectively train decommissioning workers but this training approach could consume much costs and poor modifications of scenarios. The efficiency of virtual training system could be much better than that of physical training system. This paper was intended to develop the training system to prevent accidents for decommissioning of nuclear facilities. The requirements for the training system were drawn. The data management modules for the training system were designed. The training system of decommissioning workers was developed on the basis of virtual reality which is flexibly modified. The visualization and measurement in the training system were real-time done according as changes of the decommissioning scenario. It can be concluded that this training system enables the subject to improve his familiarization about working environments and to prevent accidents during decommissioning of nuclear facilities. In the end, the safety during decommissioning of nuclear facilities will be guaranteed under the principle of ALARA.

  19. Development of Decontamination and Decommissioning Technologies for Nuclear Facilities

    International Nuclear Information System (INIS)

    Moon, Jei Kwon; Lee, Kune Woo; Won, Hui Jun

    2010-04-01

    A laser ablation decontamination technology which is reportedly effective for a removal of fixed contaminants has been developed for three years as the first stage of the development. Lab scale experimental equipment was fabricated and the process variables have been assessed for determination of appropriate decontamination conditions at the laser wave lengths of 1,064 nm and 532 nm, respectively. The decontamination tests using radioactive specimens showed that the decontamination efficiency was about 100 which is quite a high value. An electrokinetic-flushing, an agglomeration leaching and a supercritical CO 2 soil decontamination technology were development for a decontamination of radioactive soil wastes from the decommissioned sites of the TRIGA research reactor and the uranium conversion facilities. An electrokinetic-flushing process was found to be effective for soil wastes aged for a long time and an agglomeration leaching process was effective for soil wastes of surface contamination. On the other hand, a supercritical CO 2 soil decontamination technology was found to be applicable for U or TRU bearing soil wastes. The remediation monitoring key technologies such as a representative sample taking and a measurement concept for the vertical distribution of radionuclides were developed for an assessment of the site remediation. Also an One-Dimensional Water Flow and Contaminant Transport in Unsaturated Zone (FTUNS) code was developed to interpretate the radionuclide migration in the unsaturated zone

  20. TRU waste-assay instrumentation and application in nuclear-facility decommissioning

    International Nuclear Information System (INIS)

    Umbarger, C.J.

    1982-01-01

    The Los Alamos TRU waste assay program is developing measurement techniques for TRU and other radioactive waste materials generated by the nuclear industry, including decommissioning programs. Systems are now being fielded for test and evaluation purposes at DOE TRU waste generators. The transfer of this technology to other facilities and the commercial instrumentation sector is well in progress. 6 figures

  1. Methodologies for and Results of Planning later Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Auler, I.; Paul, R.; Petrasch, P.

    1996-01-01

    Cost and success of decommissioning and dismantling nuclear power plants or other nuclear facilities are very much related to the chosen strategy and their implementation in practice. The strategy to be developed depends on the specific boundary conditions in a certain country and plant. Inadequate planning and equipment considered too late cause delays in the project performance and improvisations with financial and radiological consequences. For the development of a decommissioning strategy for a nuclear power plant broad experience from past D and D-projects is very important. That experience is very helpful in assessing the importance of the many factors which determine the success or failure of strategic decisions Tools for the systematic recording and investigation of the needed measures and expenditures are available, eg. the decommissioning cost program STILLKO-2, which has been established as standard tool. (author)

  2. Planning and management for the decommissioning of research reactors and other small nuclear facilities

    International Nuclear Information System (INIS)

    1993-01-01

    Many research reactors and other small nuclear facilities throughout the world date from the original nuclear research programmes in the Member States. Consequently, a large number of these plants have either been retired from service or will soon reach the end of their useful lives and are likely to become significant decommissioning tasks for those Members States. In recognition of this situation and in response to considerable interest shown by Member States, the IAEA has produced this document on planning and management for the decommissioning of research reactors and other small nuclear facilities. While not directed specifically at large nuclear installations, it is likely that much of the information presented will also be of interest to those involved in the decommissioning of such facilities. Current views, information and experience on the planning and management of decommissioning projects in Member States were collected and assessed during a Technical Committee Meeting held by the IAEA in Vienna from 29 July to 2 August 1991. It was attended by 22 participants from 14 Member States and one international organization. 28 refs, 2 figs, 3 tabs

  3. Safeguards considerations related to the decontamination and decommissioning of former nuclear weapons facilities

    International Nuclear Information System (INIS)

    Crawford, D.

    1995-01-01

    In response to the post-Cold War environment and the changes in the U. S. Department of Energy defense mission, many former nuclear operations are being permanently shut down. These operations include facilities where nuclear materials production, processing, and weapons manufacturing have occurred in support of the nation's defense industry. Since defense-related operations have ceased, many of the classification and sensitive information concerns do not exist. However, nuclear materials found at these sites are of interest to the DOE from environmental, safety and health, and materials management perspectives. Since these facilities played a role in defense activities, the nuclear materials found at these facilities are considered special nuclear materials, primarily highly enriched uranium and/or plutonium. Consequently, these materials pose significant diversion, theft, and sabotage threats, and significant nuclear security issues exist that must be addressed. This paper focuses on the nuclear materials protection issues associated with facility decommissioning and decontamination, primarily safeguards

  4. Decontamination and demolition of concrete and metal structures during the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-01-01

    The objective of this report is to give a concise technical description of the techniques and equipment being used or developed for the decontamination and demolition of nuclear facilities in sufficient detail to assist Member States to plan decommissioning operations and make preliminary evaluations of techniques and equipment. This report also reviews new and/or different aspects which have not been well covered previously in readily available review documents or IAEA publications. This report is an up to date review of techniques and equipment being used or developed for decontamination or dismantling work during the decommissioning of all types of nuclear facility except mining and milling sites. Although the information presented is aimed at countries initiating decommissioning programmes, it should also be useful to others who are responsible for or interested in the planning and implementation of decommissioning tasks. This report describes the relevant techniques and equipment, their areas of application and degree of development and the conditions in which they are used, when these details are known. However, this publication should be used in conjunction with other published technical information on these topics, experience gained as a result of previous decommissioning operations and the assistance of experts in the appropriate areas are required. 64 refs, 33 figs, 5 tabs

  5. Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; (2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing D&D activities and the reuse of the facility or area for other purposes.

  6. Conference on decontamination and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Meservey, R.H.

    1979-01-01

    A brief history of Decontamination and Decommissioning (D and D) experience at the Idaho National Engineering Laboratory is presented as an introduction to the status of current projects. Details are then presented as an introduction to the status of current projects. Details are then presented on a project to remove sodium from some major components of the Hallam reactor and on the Organic Moderated Reactor Experiment (OMRE) decommissioning project. Cost, schedule, waste volume, and other technical data from these projects are presented. In addition, a brief summary of the future INEL D and D program is presented

  7. Approaches relating to decommissioning of nuclear facilities. Peer discussions on regulatory practices

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    This report arises from the fifth series of peer discussions on regulatory practices entitled 'Approaches relating to decommissioning of nuclear facilities'. Senior regulators from 22 Member States participated in three peer group discussions during 1996-1997. This report presents the outcome of these meetings and recommendations of good practices identified by senior regulators, which do not necessarily reflect those of the governments of the nominating Member States, the nominating organizations, nor the IAEA. In many Member States nuclear facilities such as power and research reactors, nuclear fuel cycle facilities and various industrial and medical facilities have reached the end of their useful life or will reach it in the near future. These facilities need to be safely decommissioned without causing any undue radiological, chemical or other risks to workers, the public and the environment. Today, there is a growing consensus that decommissioning needs to be given consideration from the design phase of a new facility and that planning for decommissioning is to be carried out during the entire life of the nuclear facility. In most Member States, there is no comprehensive set of requirements, be it on a legal or technical level, available to plan, assess, approve and carry out decommissioning operations. Since most of the facilities to be decommissioned in the near future are demonstration or prototype facilities, case by case specific and prescriptive requirements will have to be developed. However, such case by case requirements need to be based on existing applicable regulations as well as on generally accepted principles. In order to assist Member States in ensuring safe decommissioning operations, the IAEA has convened the fifth series of peer discussions on 'Approaches relating to decommissioning of nuclear facilities'. The results and findings of these discussions are summarized in this report, concentrating on recommendations and established good

  8. Approaches relating to decommissioning of nuclear facilities. Peer discussions on regulatory practices

    International Nuclear Information System (INIS)

    1998-04-01

    This report arises from the fifth series of peer discussions on regulatory practices entitled 'Approaches relating to decommissioning of nuclear facilities'. Senior regulators from 22 Member States participated in three peer group discussions during 1996-1997. This report presents the outcome of these meetings and recommendations of good practices identified by senior regulators, which do not necessarily reflect those of the governments of the nominating Member States, the nominating organizations, nor the IAEA. In many Member States nuclear facilities such as power and research reactors, nuclear fuel cycle facilities and various industrial and medical facilities have reached the end of their useful life or will reach it in the near future. These facilities need to be safely decommissioned without causing any undue radiological, chemical or other risks to workers, the public and the environment. Today, there is a growing consensus that decommissioning needs to be given consideration from the design phase of a new facility and that planning for decommissioning is to be carried out during the entire life of the nuclear facility. In most Member States, there is no comprehensive set of requirements, be it on a legal or technical level, available to plan, assess, approve and carry out decommissioning operations. Since most of the facilities to be decommissioned in the near future are demonstration or prototype facilities, case by case specific and prescriptive requirements will have to be developed. However, such case by case requirements need to be based on existing applicable regulations as well as on generally accepted principles. In order to assist Member States in ensuring safe decommissioning operations, the IAEA has convened the fifth series of peer discussions on 'Approaches relating to decommissioning of nuclear facilities'. The results and findings of these discussions are summarized in this report, concentrating on recommendations and established good

  9. Planning, managing and organizing the decommissioning of nuclear facilities: Lessons learned

    International Nuclear Information System (INIS)

    2004-05-01

    This publication is intended to encourage the development and improvement of decommissioning planning and management techniques, with the focus on organizational aspects, reduce the duplication of efforts by different parties by transfer of experience and know-how, and provide useful results for those Member States planning or implementing decommissioning projects. In general it can be stated that any decommissioning project can be completed without any deleterious effects on the safety of the workforce and the public or any identifiable impact on the environment. However, timeliness and cost-effectiveness are not always optimal. It has been noted on several occasions that the major weakness in decommissioning projects (as well as in other industrial projects) is often not the lack of technologies, but rather poor planning and management. This publication intends to stimulate awareness of the need for early and efficient planning and to foster developments in management and organization in association with planned or ongoing decommissioning projects. A companion report on Organization and Management for Decommissioning of Large Nuclear Facilities was published by the IAEA in 2000 (Technical Report Series (TRS) No. 399). That TRS provides generic guidance on organizational and management aspects. This TECDOC is complementary to the existing report in that it highlights practical experience - in particular, typical issues, evidence of poor management, undue delays, and lack of timely funding - and distils lessons learned from this experience

  10. Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This guide addresses the development of waste management plans for potential waste streams resulting from decommissioning activities at nuclear facilities, including identifying, categorizing, and handling the waste from generation to final disposal. 1.2 This guide is applicable to potential waste streams anticipated from decommissioning activities of nuclear facilities whose operations were governed by the Nuclear Regulatory Commission (NRC) or Agreement State license, under Department of Energy (DOE) Orders, or Department of Defense (DoD) regulations. 1.3 This guide provides a description of the key elements of waste management plans that if followed will successfully allow for the characterization, packaging, transportation, and off-site treatment or disposal, or both, of conventional, hazardous, and radioactive waste streams. 1.4 This guide does not address the on-site treatment, long term storage, or on-site disposal of these potential waste streams. 1.5 This standard does not purport to address ...

  11. Decommissioning and deactivation of nuclear facilities; Desmantelamiento y clausura de instalaciones nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Anasco, Roberto; Harriague, Santiago; Hey, Alfredo M [Comision Nacional de Energia Atomica, Buenos Aires (Argentina). Gerencia de Tecnologia y Medio Ambiente; Fabbri, Silvio [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes; Garonis, Omar H [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Gestion de Calidad

    2003-07-01

    The National Atomic Energy Commission (CNEA) is responsible for the decommissioning and deactivation of all relevant nuclear facilities in Argentina. A D and D Subprogram was created in 2000, within Technology Branch of the CNEA, in order to fulfill this responsibility. The D and D Subprogram has organized its activities in four fields: Planning; Technology development; Human resources development and training; International cooperation. The paper describes the work already done in those 4 areas, as well as the nuclear facilities existing in the country. Planning is being developed for the decommissioning of research reactors, beginning with RA-1, as well as for the Atucha I nuclear power station. An integral Management System has been developed, compatibilizing requirements from ISO 9001, ISO 14001, the national norm for Safety and Occupational Health (equivalent to BS 8800), and IAEA 50-SG Q series. Technology development is for the time being concentrated on mechanical decontamination and concrete demolition. A review has been made of technologies already developed both by CNEA and Nucleoelectrica Argentina S.A. (the nuclear power utility) in areas of chemical and electrochemical decontamination, cutting techniques and robotics. Human resources development has been based on training abroad in the areas of decontamination, cutting techniques, quality assurance and planning, as well as on specific courses, seminars and workshops. An IAEA regional training course on D and D has been given on April 2002 at CNEA's Constituyentes Atomic Center, with the assistance of 22 university graduates from 13 countries in the Latin American and Caribbean Region, and 11 from Argentina. CNEA has also given fellowships for PhD and Master thesis on the subject. International cooperation has been intense, and based on: - IAEA Technical Cooperation Project and experts missions; - Cooperation agreement with the US Department of Energy; - Cooperation agreement with Germany

  12. Monitoring programmes for unrestricted release related to decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1992-01-01

    Decommissioning of nuclear facilities usually results in a large volume of radioactive and non-radioactive materials. All these materials will have to be segregated as radioactive, non-radioactive and exempt from regulatory control, and then disposed of, reused or recycled. As more and more facilities approach decommissioning, controlling these wastes and setting release criteria and limits for these materials will represent a major task for the regulatory body and the licensee. Efforts are, therefore, under way at the IAEA to help achieve international consensus on the release criteria for decommissioning and a monitoring programme to verify compliance with these criteria. Within the above context, the present report was conceived as a technical document to provide an overview of all the factors to be considered in the development, planning and implementation of a monitoring programme to assure regulatory compliance with criteria for unrestricted release of materials, buildings and sites from decommissioning. The report is intended as a planning document for the owners, operators and regulatory bodies involved in decommissioning. 41 refs, 4 figs, 2 tabs

  13. Study concerning decommissioning of nuclear facilities overseen by the IAEA in the United States and major European countries

    International Nuclear Information System (INIS)

    Hirashima, Shikazoh

    1983-01-01

    The purpose of this investigation was to know generally on the activities of decommissioning nuclear facilities in the IAEA, and to compare the regulation and finance concerning reactor decommissioning in European countries and the United States together with the decommissioning policy and the status of research and development. Recently also in Japan, attention has been paid to reactor decommissioning after the termination of operation, and the report by the Decommissioning Countermeasures Committee was published in March, 1981. In the IAEA, the investigation of Reactor decommissioning has been performed since 1973, and the meetings of the technical committee in 1975 and 1977, the international symposium in 1978, and the publication of ''Various factors concerning the decommissioning of inland nuclear facilities'' in 1980 were held. The regulation and finance concerning the decommissioning have been performed differently in each country, and the features of the main policy of decommissioning are indicated. In foreign countries, the measures of account for the decommissioning expenses have been already taken. In Japan, it is desirable to establish the technical standard for the decommissioning including legislation and finance. (Kako, I.)

  14. Factor analysis on hazards for safety assessment in decommissioning workplace of nuclear facilities using a semantic differential method

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan-Seong [Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)], E-mail: ksjeongl@kaeri.re.kr; Lim, Hyeon-Kyo [Chungbuk National University, 410 Sungbong-ro, Heungduk-gu, Cheongju, Chungbuk 361-763 (Korea, Republic of)

    2009-10-15

    The decommissioning of nuclear facilities must be accomplished according to its structural conditions and radiological characteristics. An effective risk analysis requires basic knowledge about possible risks, characteristics of potential hazards, and comprehensive understanding of the associated cause-effect relationships within a decommissioning for nuclear facilities. The hazards associated with a decommissioning plan are important not only because they may be a direct cause of harm to workers but also because their occurrence may, indirectly, result in increased radiological and non-radiological hazards. Workers need to be protected by eliminating or reducing the radiological and non-radiological hazards that may arise during routine decommissioning activities as well as during accidents. Therefore, to prepare the safety assessment for decommissioning of nuclear facilities, the radiological and non-radiological hazards should be systematically identified and classified. With a semantic differential method of screening factor and risk perception factor, the radiological and non-radiological hazards are screened and identified.

  15. Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment

    International Nuclear Information System (INIS)

    Lauridsen, Kurt

    2001-02-01

    The report is the result of a project initiated by Risoe National Laboratory in June 2000 on request from the Minister of Research and Information Technology. It describes the nuclear facilities at Risoe National Laboratory to be decommissioned and gives an assessment of the work to be done and the costs incurred. Three decommissioning scenarios were considered with decay times of 10, 25 and 40 years for the DR 3 reactor. The assessments conclude, however, that there will not be much to gain by allowing for the longer decay periods; some operations still will need to be performed remotely. Furthermore, the report describes some of the legal and licensing framework for the decommissioning and gives an assessment of the amounts of radioactive waste to be transferred to a Danish repository. (au)

  16. Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment[Denmark

    Energy Technology Data Exchange (ETDEWEB)

    Lauridsen, Kurt [ed.

    2001-02-01

    The report is the result of a project initiated by Risoe National Laboratory in June 2000 on request from the Minister of Research and Information Technology. It describes the nuclear facilities at Risoe National Laboratory to be decommissioned and gives an assessment of the work to be done and the costs incurred. Three decommissioning scenarios were considered with decay times of 10, 25 and 40 years for the DR 3 reactor. The assessments conclude, however, that there will not be much to gain by allowing for the longer decay periods; some operations still will need to be performed remotely. Furthermore, the report describes some of the legal and licensing framework for the decommissioning and gives an assessment of the amounts of radioactive waste to be transferred to a Danish repository. (au)

  17. Nuclear and non-nuclear safety aspects in nuclear facilities dismantling. The example of a PWR pilot decommissioning project

    International Nuclear Information System (INIS)

    Massaut, V.; Deboodt, P.; Dadoumont, J.; Valenduc, P.; Denissen, L.

    2002-01-01

    The dismantling of nuclear facilities, and in particular of nuclear power plants, involves new challenges for the nuclear industry. Although the dismantling of various activated and contaminated components is nowadays considered as almost industrial practice, the safety aspects of decommissioning bring some specific features which are not always taken into account in the operation of the plants. Moreover, most of the plants and facilities currently decommissioned are rather old and were never foreseen to be decommissioned. The operations involved in dismantling and decontamination, often imply new or unforeseen situations. On the nuclear, or radiological side, the radioprotection optimisation of the operations involved often requires to model the environment and to analyse different scenarios to tackle the operation. Recent 3-D software (like the Visiplan software) allowing representation of the actual environment and the influence of the various sources present, is really needed to be able to minimise the radiological impact on the operators. The risk of contamination spread, by opening loops and components or by the dismantling process itself, is also an important aspect of the radiological protection study. Nevertheless, the radiological aspects of the safety approach are not the only ones to be dealt with when decommissioning nuclear facilities. Indeed, classical industrial safety aspects are also important: the dismantling can bring handling and transporting risk (heavy loads, difficult ways, uneasy access, etc.) but also the handling of toxic or hazardous materials. For instance, the removal of asbestos in contaminated areas can lead to additional hazard; the presence of alkali metals (like Na or NaK), of toxic metals (like e.g. Beryllium) or of corrosive fluids (acid,...) have to be tackled often in unstructured environment, and sometimes with limited knowledge of the actual situation. This leads to approach the operations following the ASARA principle (As

  18. Study on scenario evaluation methodology for decommissioning nuclear facilities using fuzzy logic

    International Nuclear Information System (INIS)

    Matsuhashi, Kazuya; Yanagihara, Satoshi

    2015-01-01

    Since there are many scenarios of the process from start to completion of a decommissioning project, it is important to study scenarios of decommissioning by evaluating such properties as safety, cost, and technology. An optimum scenario with the highest feasibility in accordance with the facility and environmental conditions should be selected on the basis of the results of the study. For analyzing a scenario of decommissioning, we prepared structured work packages by using the work breakdown structures (WBS) method together with qualitative evaluation of the technologies being applied to work packages located at the bottom (the third level) of the WBS. A calculation model was constructed to evaluate the feasibility of a scenario where fuzzy logic is applied to derive a score of technology performance and TOPSIS is applied for getting a feasibility grade of the scenario from technical performance scoring. As a case study, the model was applied to the debris removal scenario of Fukushima Daiichi Nuclear Power Plant to confirm its applicability. Two scenarios, underwater and in-air debris removal cases, were characterized by extracting the work packages with the lowest feasibility and by obtaining total average scores of the scenarios. It is confirmed that the methodology developed is useful for the scenario evaluation of decommissioning nuclear facilities. (author)

  19. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 2, Indexes. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-09-01

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

  20. Research on decommissioning of nuclear facilities (Joint research)

    International Nuclear Information System (INIS)

    Shibahara, Yuji; Morishita, Yoshitsugu; Ishigami, Tsutomu; Yanagihara, Satoshi; Arita, Yuji

    2011-07-01

    To implement a decommissioning project reasonably, it is necessary and important to beforehand evaluate project management data as well as to select an optimum dismantling scenario among various scenarios postulated. Little study on the subject of selecting an optimum scenario has been carried out, and it is one of the most important subjects in terms of decision making. In FY 2009, Japan Atomic Energy Agency and University of Fukui launched the joint research of a decision making method which is important to determine a decommissioning plan. The purpose of the research is to construct a methodology for selecting an optimum dismantling scenario among various scenarios postulated based on calculated results of project management data for FUGEN. Project management data for several dismantling scenarios postulated at FUGEN were evaluated based on actual dismantling work for feed water heater at FUGEN, and an optimum scenario was discussed using the SMART, one of Multi-Criteria Decision Analysis Method. This report describes the results of the joint research in FY 2009. (author)

  1. Cost calculations for decommissioning and dismantling of nuclear research facilities, Phase 1

    International Nuclear Information System (INIS)

    Andersson, Inga; Backe, S.; Iversen, Klaus; Lindskog, S; Salmenhaara, S.; Sjoeblom, R.

    2006-11-01

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility. However, no actual international guideline on cost calculations exists at present. Intuitively, it might be tempting to regard costs for decommissioning of a nuclear facility as similar to those of any other plant. However, the presence of radionuclide contamination may imply that the cost is one or more orders of magnitude higher as compared to a corresponding inactive situation, the actual ratio being highly dependent on the level of contamination as well as design features and use of the facility in question. Moreover, the variations in such prerequisites are much larger than for nuclear power plants. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological and other prerequisites. Application of inadequate methodologies especially at early stages has often lead to large underestimations. The goals of the project and the achievements described in the report are as follows: 1) Advice on good practice with regard to: 1a) Strategy and planning; 1b) Methodology selection; 1c) Radiological surveying; 1d) Uncertainty analysis; 2) Techniques for assessment of costs: 2a) Cost structuring; 2b) Cost estimation methodologies; 3) Compilation of data for plants, state of planning, organisations, etc.; 3a) General descriptions of relevant features of the nuclear research facilities; 3b) General plant specific data; 3c) Example of the decommissioning of the R1 research reactor in Sweden; 3d) Example of the decommissioning of the DR1 research reactor in Denmark. In addition, but not described in the present report, is the establishment of a Nordic network in the area including an internet based expert system. It should be noted that the project is planned to exist for at least three years and that the present report is an interim one

  2. Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment. Danish summary

    International Nuclear Information System (INIS)

    Lauridsen, Kurt

    2001-02-01

    The report gives a brief description of relevant aspects of the decommissioning of all nuclear facilities at Risoe National Laboratory, including the necessary operations to be performed and the associated costs. Together with a more detailed report, written in English, this report is the result of a project initiated by Risoe in the summer of 2000. The English report has undergone an international review, the results of which are summarised in the present report. (au)

  3. Cost calculations for decommissioning and dismantling of nuclear research facilities, Phase 1

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Inga [StudsvikNuclear AB (Sweden); Backe, S. [Institute for Energy Technology (Norway); Iversen, Klaus [Danish Decommissioning (Denmark); Lindskog, S [Swedish Nuclear Power Inspectorate (Sweden); Salmenhaara, S. [VTT Technical Research Centre of Finland (Finland); Sjoeblom, R. [Tekedo AB (Sweden)

    2006-11-15

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility. However, no actual international guideline on cost calculations exists at present. Intuitively, it might be tempting to regard costs for decommissioning of a nuclear facility as similar to those of any other plant. However, the presence of radionuclide contamination may imply that the cost is one or more orders of magnitude higher as compared to a corresponding inactive situation, the actual ratio being highly dependent on the level of contamination as well as design features and use of the facility in question. Moreover, the variations in such prerequisites are much larger than for nuclear power plants. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological and other prerequisites. Application of inadequate methodologies especially at early stages has often lead to large underestimations. The goals of the project and the achievements described in the report are as follows: 1) Advice on good practice with regard to: 1a) Strategy and planning; 1b) Methodology selection; 1c) Radiological surveying; 1d) Uncertainty analysis; 2) Techniques for assessment of costs: 2a) Cost structuring; 2b) Cost estimation methodologies; 3) Compilation of data for plants, state of planning, organisations, etc.; 3a) General descriptions of relevant features of the nuclear research facilities; 3b) General plant specific data; 3c) Example of the decommissioning of the R1 research reactor in Sweden; 3d) Example of the decommissioning of the DR1 research reactor in Denmark. In addition, but not described in the present report, is the establishment of a Nordic network in the area including an internet based expert system. It should be noted that the project is planned to exist for at least three years and that the present report is an interim one

  4. Autonomous underwater handling system for service, measurement and cutting tasks for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Hahn, M.; Haferkamp, H.; Bach, W.; Rose, N.

    1992-01-01

    For about 10 years the Institute for Material Science at the Hanover University has worked on projects of underwater cutting and welding. Increasing tasks to be done in nuclear facilities led to the development of special handling systems to support and handle the cutting tools. Also sensors and computers for extensive and complex tasks were integrated. A small sized freediving handling system, equipped with 2 video cameras, ultrasonic and radiation sensors and a plasma cutting torch for inspection and decommissioning tasks in nuclear facilities is described in this paper. (Author)

  5. Methodology for determining acceptable residual radioactive contamination levels at decommissioned nuclear facilities/sites

    International Nuclear Information System (INIS)

    Watson, E.C.; Kennedy, W.E. Jr.; Hoenes, G.R.; Waite, D.A.

    1979-01-01

    The ultimate disposition of decommissioned nuclear facilities and their surrrounding sites depends upon the degree and type of residual contamination. Examination of existing guidelines and regulations has led to the conclusion that there is a need for a general method to derive residual radioactive contamination levels that are acceptable for public use of any decommissioned nuclear facility or site. This paper describes a methodology for determining acceptable residual radioactive contamination levels based on the concept of limiting the annual dose to members of the public. It is not the purpose of this paper to recommend or even propose dose limits for the exposure of the public to residual radioactive contamination left at decommissioned nuclear facilities or sites. Unrestricted release of facilities and/or land is based on the premise that the potential annual dose to any member of the public using this property from all possible exposure pathways will not exceed appropriate limits as may be defined by Federal regulatory agencies. For decommissioned land areas, consideration should be given to people living directly on previously contaminated areas, growing crops, grazing food animals and using well water. Mixtures of radionuclides in the residual contamination representative of fuel reprocessing plants, light water reactors and their respective sites are presented. These mixtures are then used to demonstrate the methodology. Example acceptable residual radioactive contamination levels, based on an assumed maximum annual dose of one millirem, are calculated for several selected times following shutdown of a facility. It is concluded that the methodology presented in this paper results in defensible acceptable residual contamination levels that are directly relatable to risk assessment with the proviso that an acceptable limit to the maximum annual dose will be established. (author)

  6. The state-of-the-art report on management of the decommissioning waste generated from nuclear facilities

    International Nuclear Information System (INIS)

    Kang, Il Sik; Lee, K. M.; Chung, K. H.; Kim, T. K.; Kim, K. J.

    1998-03-01

    As a result of this research on management methodologies of decommissioning waste from nuclear facilities, the state of the art of decommissioning status, plan, and management field on decommissioning waste in foreign countries as well as in Korea is evaluated. Radioactive waste for final disposal according to reusing non-radioactive waste by clear guideline on classification criteria of decommissioning waste by clear guideline on classification criteria of decommissioning waste will be reduced and metal through melting decontamination may be reused. Also, the relevant regulations on acceptance criteria of disposal site for decommissioning waste should be introduced to manage decommissioning waste effectively. It is necessary that large transport containers which satisfy relevant regulations should be designed and manufactured to transport of large waste. (author). 49 refs., 24 tabs., 30 figs

  7. Guide for International Peer Reviews of Decommissioning Cost Studies for Nuclear Facilities

    International Nuclear Information System (INIS)

    LaGuardia, Thomas S.; Pescatore, Claudio; )

    2014-01-01

    Peer reviews are a standard co-operative OECD working tool that offer member countries a framework to compare experiences and examine best practices in a host of areas. The OECD Nuclear Energy Agency (NEA) has developed a proven methodology for conducting peer reviews in radioactive waste management and nuclear R and D. Using this methodology, the NEA Radioactive Waste Management Committee's Working Party on Decommissioning and Dismantling (WPDD) developed the present guide as a framework for decommissioning cost reviewers and reviewees to prepare for and conduct international peer reviews of decommissioning cost estimate studies for nuclear facilities. It includes checklists that will help national programmes or relevant organisations to assess and improve decommissioning cost estimate practices in the future. This guide will act as the NEA reference for conducting such international peer reviews. The remainder of this guide is divided into eight chapters. Chapter 2 describes gathering the cost estimate study and underpinning documents, reviewing the study and writing a final report. Chapter 3 provides a detailed checklist approach for the review of the cost study report. Chapter 4 provides checklists to assist in reviewing benchmarked information. Chapter 5 provides comments on the approach and recommendations for use of this guide. Chapters 6 and 7 provide the background material used in developing this guide and Chapter 8 provides a list of the abbreviations and acronyms used in this guide

  8. Nuclear facility decommissioning and site remedial actions. Volume 1. A selected bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Faust, R.A.; Fore, C.S.; Knox, N.P.

    1980-09-01

    This bibliography of 633 references represents the first in a series to be produced by the Remedial Actions Program Information Center (RAPIC) containing scientific, technical, economic, and regulatory information concerning the decommissioning of nuclear facilities. Major chapters selected for this bibliography are Facility Decommissioning, Uranium Mill Tailings Cleanup, Contaminated Site Restoration, and Criteria and Standards. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for (1) author(s), (2) keywords, (3) title, (4) technology development, and (5) publication description. An appendix of 123 entries lists recently acquired references relevant to decommissioning of nuclear facilities. These references are also arranged according to one of the four subject categories and followed by author, title, and publication description indexes. The bibliography was compiled from a specialized data base established and maintained by RAPIC to provide information support for the Department of Energy's Remedial Actions Program, under the cosponsorship of its three major components: Surplus Facilities Management Program, Uranium Mill Tailings Remedial Actions Program, and Formerly Utilized Sites Remedial Actions Program. RAPIC is part of the Ecological Sciences Information Center within the Information Center Complex at Oak Ridge National Laboratory.

  9. Nuclear facility decommissioning and site remedial actions. Volume 1. A selected bibliography

    International Nuclear Information System (INIS)

    Faust, R.A.; Fore, C.S.; Knox, N.P.

    1980-09-01

    This bibliography of 633 references represents the first in a series to be produced by the Remedial Actions Program Information Center (RAPIC) containing scientific, technical, economic, and regulatory information concerning the decommissioning of nuclear facilities. Major chapters selected for this bibliography are Facility Decommissioning, Uranium Mill Tailings Cleanup, Contaminated Site Restoration, and Criteria and Standards. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. When the author is not given, the corporate affiliation appears first. If these two levels of authorship are not given, the title of the document is used as the identifying level. Indexes are provided for (1) author(s), (2) keywords, (3) title, (4) technology development, and (5) publication description. An appendix of 123 entries lists recently acquired references relevant to decommissioning of nuclear facilities. These references are also arranged according to one of the four subject categories and followed by author, title, and publication description indexes. The bibliography was compiled from a specialized data base established and maintained by RAPIC to provide information support for the Department of Energy's Remedial Actions Program, under the cosponsorship of its three major components: Surplus Facilities Management Program, Uranium Mill Tailings Remedial Actions Program, and Formerly Utilized Sites Remedial Actions Program. RAPIC is part of the Ecological Sciences Information Center within the Information Center Complex at Oak Ridge National Laboratory

  10. Uranium Determination in Samples from Decommissioning of Nuclear facilities Related to the First Stage of Nuclear Fuel Cycle

    International Nuclear Information System (INIS)

    Alvarez, A.; Correa, E.; Navarro, N.; Sancho, C.; Angeles, A.

    2000-01-01

    An adequate workplace monitoring must be carried out during the decommissioning activities, to ensure the protection of workers involved in these tasks. In addition, a large amount of waste materials are generated during the decommissioning of nuclear facilities. Clearance levels are established by regulatory authorities and are normally quite low. The determination of those activity concentration levels become more difficult when it is necessary to quantify alpha emitters such as uranium, especially when complex matrices are involved. Several methods for uranium determination in samples obtained during the decommissioning of a facility related to the first stage of the nuclear fuel cycle are presented in this work. Measurements were carried out by laboratory techniques. In situ gamma spectrometry was also used to perform measurements on site. A comparison among the different techniques was also done by analysing the results obtained in some practical applications. (Author)

  11. Decommissioning and dismantling of nuclear research facilities in Switzerland: lessons learned

    International Nuclear Information System (INIS)

    Leibundgut, Fritz

    2017-01-01

    Paul Scherrer Institute is the largest research institute for natural and engineering science in Switzerland. It operated various nuclear facilities from 1960 to 2011: Research reactors DIORIT, SAPHIR and PROTEUS, and an incineration plant for low and medium level radioactive waste. Concerning SAPHIR research reactor: in operation from 1958 to 1993, planning of decommissioning from 1998 to 2000. Decommissioning work started in 2004. Finishing is planned for 2019. Concerning DIORIT research reactor: operation as DIORIT I (20 MWth) from 1960 to 1967, then reconstruction to DIORIT II (30 MWth) and operation from 1970 until 1977. Planning of decommissioning from 1992 to 1994. Decommissioning work started in 1994 and was finished in 2012. Concerning PROTEUS research reactor: in operation from 1966 to 2011. Planning of decommissioning from 2013 to 2014. Starting of decommissioning work is planned for 2017, finishing is planned for the end of 2018 Incineration plant: In operation from 1974 to 2002. Planning of decommissioning from 2011 to 2012. Starting of decommissioning work in 2016. Finishing planned for end of 2019. Treatment of various material categories from dismantling: Concerning aluminum: because of the production of H_2 during solidification in concrete, it was necessary to minimize the surface area. When dismantling research reactors, the aluminum removed was melted in an induction furnace and poured into a 4.5 m"3 concrete container to solidify. Cutting the metal and handling it was largely accomplished remote control, using conventional technology. Concerning Steel/Cast-iron: the storage containers to be filled determined the method used for reducing the size of these materials, and the technique used for handling them. The goal was to optimize the packing density to reduce repository costs. The selected method of reducing the size of components is to cut them up using diamond-tipped tools, like saw blades. Concerning Graphite: for graphite, grinding was the

  12. Characterization of Iraq's remote nuclear facilities for decommissioning and waste management - 59167

    International Nuclear Information System (INIS)

    Al-Musawi, Fouad; Jarjies, Adnan; Miller, Ross A.

    2012-01-01

    The Government of Iraq (GOI) has undertaken efforts to decommission and dismantle former nuclear facilities. The GOI has only preliminary information on some of the former nuclear facilities. This paper will highlight the challenges involved in conducting inspections of the outlying former nuclear facilities in Iraq and present a brief summary of the results of those inspections. The facilities discussed in this paper are located at various sites throughout Iraq, from locations close to Baghdad to those in the north and far western desert areas. Some of the facilities, such as those at the Al Tuwaitha Nuclear Research Center have been visited and characterized. Other facilities, including the following, have not been visited or thoroughly characterized. - Al Jesira, Uranium feed stock production facility; - Adaya, Burial location for contaminated equipment; - Djerf al Naddah, Spent fuel storage facility; - Rashdiya, Centrifuge development center; - Al Qa'im, Uranium (yellowcake) production facility. The visits were conducted to develop an inventory of the buildings/structures that need to be included in decommissioning/dismantlement efforts. The number of buildings, type of construction, size and general condition of the buildings were noted. In addition, attempts were made to determine contamination levels on surfaces, equipment, rubble, etc. This information will be used to support the Iraqi decommissioning and dismantlement project. Because the facilities are scattered throughout the country of Iraq, significant planning and coordination was required to ensure personnel security. Teams consisting of individuals from the Iraqi Ministry of Science and Technology (MoST) and Americans were under military escort when traveling to and visiting the sites. Because of the security issues, time on the ground at each site was limited. This paper will highlight the challenges involved in conducting the inspections of the outlying former nuclear facilities In Iraq and

  13. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12

    International Nuclear Information System (INIS)

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764

  14. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  15. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P. T.; Webb, J. R.; Knox, N. P.; Goins, L. F.; Harrell, R. E.; Mallory, P. K.; Cravens, C. D.

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  16. Factors relevant to the recycling or reuse of components arising from the decommissioning and refurbishment of nuclear facilities

    International Nuclear Information System (INIS)

    1988-01-01

    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. To assist in the development of the required decommissioning expertise, the IAEA is developing reports and recommendations which will eventually form an integrated information base covering in a systematic way the wide range of topics associated with decommissioning. This information is required so that Member States can decommission their nuclear facilities in a safe, timely and cost effective manner and the IAEA can effectively respond to requests for assistance. One area which warrants more detailed analyses is an assessment of the factors important to the recycling or reuse of components arising from the refurbishment or decommissioning of nuclear plants, the topic of the present report. The document provides an up to date review of the engineering, social, scientific and administrative factors relevant to the safe recycling or reuse of components arising from decommissioning or refurbishment of nuclear facilities. This report should be of interest to owners, operators, policy makers and regulators involved with nuclear facilities, especially those in developing countries. Refs, figs and tabs

  17. Evaluation of nuclear facility decommissioning projects. Project summary report, Elk River Reactor

    International Nuclear Information System (INIS)

    Miller, R.L.; Adams, J.A.

    1982-12-01

    This report summarizes information concerning the decommissioning of the Elk River Reactor. Decommissioning data from available documents were input into a computerized data-handling system in a manner that permits specific information to be readily retrieved. The information is in a form that assists the Nuclear Regulatory Commission in its assessment of decommissioning alternatives and ALARA methods for future decommissionings projects. Samples of computer reports are included in the report. Decommissioning of other reactors, including NRC reference decommissioning studies, will be described in similar reports

  18. Development of 3D Visualization Technology for Medium-and Large-sized Radioactive Metal Wastes from Decommissioning Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, A Rim; Park, Chan Hee; Lee, Jung Min; Kim, Rinah; Moon, Joo Hyun [Dongguk Univ., Gyongju (Korea, Republic of)

    2013-10-15

    The most important point of decommissioning nuclear facilities and nuclear power plants is to spend less money and do this process safely. In order to perform a better decommissioning nuclear facilities and nuclear power plants, a data base of radioactive waste from decontamination and decommissioning of nuclear facilities should be constructed. This data base is described herein, from the radioactive nuclide to the shape of component of nuclear facilities, and representative results of the status and analysis are presented. With the increase in number of nuclear facilities at the end of their useful life, the demand of decommissioning technologies will continue to grow for years to come. This analysis of medium-and large-sized radioactive metal wastes and 3D visualization technology of the radioactive metal wastes using the 3D-SCAN are planned to be used for constructing data bases. The data bases are expected to be used on development of the basic technologies for decommissioning nuclear facilities 4 session.

  19. International conference on lessons learned from the decommissioning of nuclear facilities and the safe termination of nuclear activities. Contributed papers

    International Nuclear Information System (INIS)

    2006-12-01

    The International Atomic Energy Agency (IAEA), in cooperation with the European Commission (EC), Nuclear Energy Agency to the Organisation for Economic Co-operation and Development (OECD/NEA), and the World Nuclear Association (WNA), organized an International Conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities from 11 to 15 December 2006 in Athens, Greece. This Book of Contributed Papers contains technical papers and posters contributed by experts from operating organisations, regulatory bodies, technical support organisations, and other institutions on issues falling within the scope of the Conference. The following main topics were covered: Evolution of national and international policies and criteria for the safe and efficient decommissioning of nuclear facilities and safe termination of nuclear activities; Review of lessons learned from ongoing or completed activities associated with decommissioning; Improvement of safety and efficiency through the use of new and innovative technologies; Practical aspects in the management of material, waste and sites resulting from decommissioning, including the management of waste in the absence of repositories and waste acceptance requirements; Procedures for demonstrating compliance with clearance criteria; Experience from radiological assessments associated with decommissioning; Involvement of the local communities and the impact that decommissioning activities has on them. The presented papers and posters were reviewed and accepted following the guidelines established by the Conference Programme Committee for consideration at the Conference. The material compiled in this Book of Contributed Papers has not undergone rigorous editing by the editorial staff of the IAEA. However, certain modifications were made: a unified format was adopted for all papers; and minor corrections were made in the text where required. Each paper and poster has been indexed

  20. International conference on lessons learned from the decommissioning of nuclear facilities and the safe termination of nuclear activities. Contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-12-15

    The International Atomic Energy Agency (IAEA), in cooperation with the European Commission (EC), Nuclear Energy Agency to the Organisation for Economic Co-operation and Development (OECD/NEA), and the World Nuclear Association (WNA), organized an International Conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Nuclear Activities from 11 to 15 December 2006 in Athens, Greece. This Book of Contributed Papers contains technical papers and posters contributed by experts from operating organisations, regulatory bodies, technical support organisations, and other institutions on issues falling within the scope of the Conference. The following main topics were covered: Evolution of national and international policies and criteria for the safe and efficient decommissioning of nuclear facilities and safe termination of nuclear activities; Review of lessons learned from ongoing or completed activities associated with decommissioning; Improvement of safety and efficiency through the use of new and innovative technologies; Practical aspects in the management of material, waste and sites resulting from decommissioning, including the management of waste in the absence of repositories and waste acceptance requirements; Procedures for demonstrating compliance with clearance criteria; Experience from radiological assessments associated with decommissioning; Involvement of the local communities and the impact that decommissioning activities has on them. The presented papers and posters were reviewed and accepted following the guidelines established by the Conference Programme Committee for consideration at the Conference. The material compiled in this Book of Contributed Papers has not undergone rigorous editing by the editorial staff of the IAEA. However, certain modifications were made: a unified format was adopted for all papers; and minor corrections were made in the text where required. Each paper and poster has been indexed

  1. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    International Nuclear Information System (INIS)

    Michael R. Kruzic

    2007-01-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility was used in the early to mid-1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles in the immediate area. Identified as Corrective Action Unit 115, the TCA facility was decontaminated and decommissioned (D and D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the ''Federal Facility Agreement and Consent Order''. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously provided technical decisions are made by an experienced decision maker within the site conceptual site model, identified in the Data Quality Objective process. Facility closure involved a seven-step decommissioning strategy. Key lessons learned from the project included: (1) Targeted preliminary investigation activities provided a more solid technical approach, reduced surprises and scope creep, and made the working environment safer for the D and D worker. (2) Early identification of risks and uncertainties provided opportunities for risk management and mitigation planning to address challenges and unanticipated conditions. (3) Team reviews provided an excellent mechanism to consider all aspects of the task, integrated safety into activity performance, increase team unity and ''buy-in'' and promoted innovative and time saving ideas. (4) Development of CED protocols ensured safety and control. (5) The same proven D and D strategy is now being employed on the larger ''sister'' facility, Test Cell C

  2. An evaluation on the scenarios of work trajectory during installation of dismantling equipment for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, KwanSeong; Choi, ByungSeon; Moon, JeiKwon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kim, GeunHo; Kang, ShinYoung; Choi, JongWon; Jeong, SeongYoung; Ahn, SangMyeon; Lee, JungJun

    2016-01-01

    Highlights: • An evaluation on the scenarios of work trajectory. • An evaluation using the virtual decommissioning environments. • An evaluation on work movement under radiation environments. - Abstract: This study is intended to suggest an ergonomic evaluation on the working postural comfort. This study issued for the first time a methodology in view of combination between visual field and comfort. Especially, the ergonomic evaluation using the virtual decommissioning environments is user-friendly because setup of physical mock-up environments is difficult. This study verified the front and standing postures are best working postures during movement under radiation environments of nuclear facilities. It is expected that this methodology will make it possible to establish the ergonomic plan for decommissioning of nuclear facilities and safety of decommissioning will be improved and also decommissioning costs also can be reduced.

  3. The potential benefits and drawbacks of deferring the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Nash, R.; Pomfret, D.G.

    2000-01-01

    The need to decommission redundant plants or sites at the end of operations is accepted throughout the industry, by the timing of such work requires careful consideration. In a world where political issues dominate, safety and business drivers are often only two of the inputs, and it is therefore imperative that industry is clear in its understanding of the different drivers that affect this issue. Issues are; 1. The formal positions adopted by governments and regulators are often directed at specifically to water reactors. Should other types of facilities be constrained by the same policies? 2. Political drivers can be dominated by short to medium term considerations. Can we encourage long term strategic planning, and ? 3. The failings of the industry (especially accidents) and fear of nuclear weapons can often dominate public perception. Can industry counter these adverse associations? The key benefits relate to better risk management (especially if the radiological inventory was minimised at plant closure). Extending the decommissioning programme does allow dose reductions to take place, especially if short-lived isotopes are involved. Other benefits include more time is allowed for optioneering and planning of the decommissioning processes. This time frame also gives opportunity to develop new or better technologies. With proper control, political strategies can be developed and financial planning can take place. The concern of 'Will there be enough money to fund decommissioning' can become 'A little funding set aside early, and properly managed, can pay for decommissioning in the future'. Savings in dose, impact on the environment, and money can be achieved through a well-managed deferred programme. An extended programme of decommissioning demands the political will and the infrastructure to remain in place over a long period. Tied in to this is the need to keep money available for a long time, and to be able to retain and recover the relevant knowledge

  4. Real-time assessment of exposure dose to workers in radiological environments during decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, KwanSeong; Choi, ByungSeon; Moon, JeiKwon; Hyun, Dongjun; Lee, Jonghwan; Kim, IkJune; Kim, GeunHo; Seo, JaeSeok; Jeong, SeongYoung; Lee, JungJun; Song, HaeSang; Lee, SangWha; Son, BongKi

    2014-01-01

    Highlights: • The method of exposure dose assessment to workers during decommissioning of nuclear facilities. • The environments of simulation were designed under a virtual reality. • To assess exposure dose to workers, human model was developed within a virtual reality. - Abstract: This objective of this paper is to develop a method to simulate and assess the exposure dose to workers during decommissioning of nuclear facilities. To simulate several scenarios, decommissioning environments were designed using virtual reality. To assess exposure dose to workers, a human model was also developed using virtual reality. The exposure dose was measured and assessed under the principle of ALARA in accordance with radiological environmental change. This method will make it possible to plan for the exposure dose to workers during decommissioning of nuclear facilities

  5. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  6. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text

    International Nuclear Information System (INIS)

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

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word

  7. Approaches of Knowledge Management System for the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Iguchi, Y.; Yanagihara, S.; Kato, Y.; Tezuka, M.; Koda, Y.

    2016-01-01

    Full text: The decommissioning of a nuclear facility is a long term project, handling information beginning with design, construction and operation. Moreover, the decommissioning project is likely to be extended because of the lack of the waste disposal site. In this situation, as the transfer of knowledge to the next generation is a crucial issue, approaches of knowledge management (KM) are necessary. For this purpose, the total system of decommissioning knowledge management system (KMS) is proposed. In this system, we should arrange, organize and systematize the data and information of the plant design, maintenance history, trouble events, waste management records etc. The collected data, information and records should be organized by computer support systems. It becomes a base of the explicit knowledge. Moreover, measures of extracting tacit knowledge from retiring employees are necessary. The experience of the retirees should be documented as much as possible through effective questionnaire or interview process. In this way, various KM approaches become an integrated KMS as a whole. The system should be used for daily accumulation of knowledge thorough the planning, implementation and evaluation of decommissioning activities and it will contribute to the transfer of knowledge. (author

  8. Radiological protection and radioactive waste management aspects of the decommissioning of redundant nuclear facilities at the Rosyth Dockyard, UK

    International Nuclear Information System (INIS)

    Kerr, Robert W.; Murdo Murray; Hunter Common

    2008-01-01

    The Rosyth Dockyard is located near the city of Edinburgh in Scotland. The dockyard's nuclear activities centred around the refuelling and refitting of submarines, as well as some submarine decommissioning. In 1993, submarine refitting work was transferred to Devonport in Southern England. This meant that there were a number of facilities at the Rosyth Dockyard that were now redundant. In accordance with UK government policy a programme of works was instigated to allow for the decommissioning of these nuclear liabilities. This paper provides a brief overview of work activities performed to allow physical decommissioning to take place. Topics covered include radiological characterisation activities, development of monitoring protocols for decommissioning, obtaining relevant environmental authorisations, developing a decommissioning safety case, gaining the UK's Nuclear Installations Inspectorate approval to proceed with decommissioning and an overview of some of the post operative clean out (POCO) activities performed. Edmund Nuttall Ltd were contracted to perform the physical decommissioning of the redundant nuclear facilities, that have been subject to POCO, and this work commenced in February 2006. As part of this contract they were to provide a radiological protection infrastructure including dosimetry and health physics monitoring. This paper discusses the radiological protection infrastructure established by the decommissioning contractor, the radiological protection aspects of the decommissioning work, some of the tools and techniques utilised to date during the nuclear decommissioning, and the radioactive waste management processes established for the project. All activities are referenced to relevant aspects of UK nuclear industry best practice and to the Scottish, UK and European regulatory framework. The progress to date is discussed and lessons that have been learnt are highlighted. (author)

  9. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    International Nuclear Information System (INIS)

    Michael R, Kruzic

    2008-01-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D and D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

  10. Nuclear Rocket Facility Decommissioning Project: Controlled Explosive Demolition of Neutron-Activated Shield Wall

    Energy Technology Data Exchange (ETDEWEB)

    Michael R. Kruzic

    2008-06-01

    Located in Area 25 of the Nevada Test Site (NTS), the Test Cell A (TCA) Facility (Figure 1) was used in the early to mid-1960s for testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program, to further space travel. Nuclear rocket testing resulted in the activation of materials around the reactors and the release of fission products and fuel particles. The TCA facility, known as Corrective Action Unit 115, was decontaminated and decommissioned (D&D) from December 2004 to July 2005 using the Streamlined Approach for Environmental Restoration (SAFER) process, under the Federal Facility Agreement and Consent Order. The SAFER process allows environmental remediation and facility closure activities (i.e., decommissioning) to occur simultaneously, provided technical decisions are made by an experienced decision maker within the site conceptual site model. Facility closure involved a seven-step decommissioning strategy. First, preliminary investigation activities were performed, including review of process knowledge documentation, targeted facility radiological and hazardous material surveys, concrete core drilling and analysis, shield wall radiological characterization, and discrete sampling, which proved to be very useful and cost-effective in subsequent decommissioning planning and execution and worker safety. Second, site setup and mobilization of equipment and personnel were completed. Third, early removal of hazardous materials, including asbestos, lead, cadmium, and oil, was performed ensuring worker safety during more invasive demolition activities. Process piping was to be verified void of contents. Electrical systems were de-energized and other systems were rendered free of residual energy. Fourth, areas of high radiological contamination were decontaminated using multiple methods. Contamination levels varied across the facility. Fixed beta/gamma contamination levels ranged up to 2 million disintegrations per minute (dpm)/100

  11. A State-of-the-Art Report on Technologies of a Safety Assessment and a Radioactivity Exposure Assessment for the Decommissioning Process of Nuclear Facilities

    International Nuclear Information System (INIS)

    Jeong, Kwan Seong; Kang, Young Ae; Lee, Dong Gyu; Lee, Kune Woo; Jung, Chong Hun

    2007-09-01

    This report is to provide the reference contents of research and development for technologies of radioactivity exposure and safety assessment for development of the decommissioning technology for nuclear facilities. This report consists of as follows: - Analyzing and discussing on state-of-the-art technologies of a radioactivity exposure assessment of a decommissioning for nuclear facilities - Analyzing and discussing on state-of-the-art technologies of a safety assessment of a decommissioning for nuclear facilities

  12. A State-of-the-Art Report on Technologies of a Safety Assessment and a Radioactivity Exposure Assessment for the Decommissioning Process of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Kwan Seong; Kang, Young Ae; Lee, Dong Gyu; Lee, Kune Woo; Jung, Chong Hun

    2007-09-15

    This report is to provide the reference contents of research and development for technologies of radioactivity exposure and safety assessment for development of the decommissioning technology for nuclear facilities. This report consists of as follows: - Analyzing and discussing on state-of-the-art technologies of a radioactivity exposure assessment of a decommissioning for nuclear facilities - Analyzing and discussing on state-of-the-art technologies of a safety assessment of a decommissioning for nuclear facilities.

  13. Nuclear Rocket Test Facility Decommissioning Including Controlled Explosive Demolition of a Neutron-Activated Shield Wall

    International Nuclear Information System (INIS)

    Michael Kruzic

    2007-01-01

    Located in Area 25 of the Nevada Test Site, the Test Cell A Facility was used in the 1960s for the testing of nuclear rocket engines, as part of the Nuclear Rocket Development Program. The facility was decontaminated and decommissioned (D and D) in 2005 using the Streamlined Approach For Environmental Restoration (SAFER) process, under the Federal Facilities Agreement and Consent Order (FFACO). Utilities and process piping were verified void of contents, hazardous materials were removed, concrete with removable contamination decontaminated, large sections mechanically demolished, and the remaining five-foot, five-inch thick radiologically-activated reinforced concrete shield wall demolished using open-air controlled explosive demolition (CED). CED of the shield wall was closely monitored and resulted in no radiological exposure or atmospheric release

  14. Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 7

    International Nuclear Information System (INIS)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.; Fowler, J.W.

    1986-09-01

    The 644 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the seventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. References are arranged alphabetically by leading author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations

  15. Nuclear Facilities Decommissioning and site remedial actions: a selected bibliography. Vol. 2

    International Nuclear Information System (INIS)

    Owen, P.T.; Fielden, J.M.; Knox, N.P.; Trotter, ES.

    1981-10-01

    This bibliography of 643 references represents the second in a series on nuclear facility decommissioning and site remedial actions to be produced by the Radiation Effects Information Center (REIC) within the Information Center Complex, Information Division, Oak Ridge National Laboratory. The bibliography contains scientific, technical, economic, and regulatory information pertaining to the US Department of Energy's Remedial Action Program. Major chapters are: Surplus Facilities Management Program; Nuclear Facilities Decommissioning; Formerly Utilized Sites Remedial Action Program; and Uranium Mill Tailings Management. The references within each chapter are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by title. Indexes are provided for: (1) author; (2) corporate affiliation; (3) title; (4) publication description; (5) geographic location; and (6) keywords. The bibliography was compiled from a specialized data base established and maintained by REIC to provide information support for the US Department of Energy's Remedial Action Program, under the cosponsorship of its four major components: Surplus Facilities Management Program; Formerly Utilized Sites Remedial Action Program; Uranium Mill Tailings Remedial Action Program; and the Grand Junction Remedial Action Program

  16. Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1985-09-01

    This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description.

  17. Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1987-09-01

    The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations.

  18. Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

    International Nuclear Information System (INIS)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1985-09-01

    This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's remedial action program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Facilities Contaminated with Natural Radioactivity; (5) Uranium Mill Tailings Remedial Action Program; (6) Grand Junction Remedial Action Program; (7) Uranium Mill Tailings Management; (8) Technical Measurements Center; and (9) General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 7 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate affiliation or by publication description

  19. Nuclear facility decommissioning and site remedial actions: A selected bibliography: Volume 8

    International Nuclear Information System (INIS)

    Owen, P.T.; Michelson, D.C.; Knox, N.P.

    1987-09-01

    The 553 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eighth in a series of reports. Foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of energy's remedial action program. Major chapters are Surplus Facilities Management Program, Nuclear Facilities Decommissioning, Formerly Utilized Sites Remedial Action Program, Facilities Contaminated with Naturally Occurring Radionuclides, Uranium Mill Tailings Remedial Action Program, Uranium Mill Tailings Management, Technical Measurements Center, and General Remedial Action Program Studies. Chapter sections for chapters 1, 2, 5, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. The appendix contains a list of frequently used acronyms and abbreviations

  20. Decommissioning a nuclear reactor

    International Nuclear Information System (INIS)

    Montoya, G.M.

    1991-01-01

    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

  1. Safety assessment and surveillance of decommissioning operations at DOE's nuclear facilities

    International Nuclear Information System (INIS)

    Cowgill, M.G.; Prochnow, D.; Worthington, P.R.

    1995-01-01

    A description is provided of a systematic approach currently being developed and deployed at the Department of Energy to obtain assurance that post-operational activities at nuclear facilities will be conducted in a safe manner. Using this approach, personnel will have available a formalized set of safety principles and associated question sets to assist them in the conducting of safety assessments and surveillance. Information gathered through this means will also be analyzed to determine if there are any generic complex-wide strengths or deficiencies associated with decommissioning activities and to which attention should be drawn

  2. Technology, safety and costs of decommissioning reference nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Elder, H.K.

    1986-05-01

    The radioactive wastes expected to result from decommissioning nuclear fuel cycle facilities are reviewed and classified in accordance with 10 CFR 61. Most of the wastes from the MOX plant (exclusive of the lagoon wastes) will require interim storage (11% Class A 49 m 3 ; 89% interim storage, 383 m 3 ). The MOX plant lagoon wastes are Class A waste (2930 m 3 ). All of the wastes from the U-Fab and UF 6 plants are designated as Class A waste (U-Fab 1090 m 3 , UF 6 1259 m 3 )

  3. Development of a prototype gamma camera (Aladin) for use in decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    Imbard, G.; Carcreff, H.

    1995-01-01

    Mapping the gamma activity of irradiating zones is often an important prerequisite in dismantling nuclear facilities. This operation is necessary to define a suitable decommissioning strategy before any work begins; it is also required during the procedure to measure the residual activity wherever dose rates are too high to allow human intervention. This paper summarizes the work carried out develop a prototype imaging system designed to display radioactive sources superimposed in real time over a visible light image on a video monitor. This project was developed from an earlier off-line system. (authors). 8 refs., 7 figs., 3 tabs

  4. Waste from decommissioning of research reactors and other small nuclear facilities

    International Nuclear Information System (INIS)

    Massaut, V.

    2001-01-01

    Full text: Small nuclear facilities were often built for research or pilot purposes. It includes the research reactors of various types and various aims (physics research, nuclear research, nuclear weapons development, materials testing reactor, isotope production, pilot plant, etc.) as well as laboratories, hot cells and accelerators used for a broad spectrum of research or production purposes. These installations are characterized not only by their size (reduced footprint) but also, and even mostly, by the very diversified type of materials, products and isotopes handled within these facilities. This large variety can sometimes enhance the difficulties encountered for the dismantling of such facilities. The presence of materials like beryllium, graphite, lead, PCBs, sodium, sometimes in relatively large quantities, are also challenges to be faced by the dismantlers of such facilities, because these types of waste are either toxic or no solutions are readily available for their conditioning or long term disposal. The paper will review what is currently done in different small nuclear facilities, and what are the remaining problems and challenges for future dismantling and waste management. The question of whether Research and Development for waste handling methods and processes is needed is still pending. Even for the dismantling operation itself, important improvements can be brought in the fields of characterization, decontamination, remote handling, etc. by further developments and innovative systems. The way of funding such facilities decommissioning will be reviewed as well as the very difficult cost estimation for such facilities, often one-of-a-kind. The aspects of radioprotection optimization (ALARA principle) and classical operators safety will also be highlighted, as well as the potential solutions or improvements. In fact, small nuclear facilities encounter often, when dismantling, the same problems as the large nuclear power plants, but have in

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

    International Nuclear Information System (INIS)

    Owen, P.T.; Knox, N.P.; Chilton, B.D.; Baldauf, M.F.

    1984-09-01

    This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms

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

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Chilton, B.D.; Baldauf, M.F.

    1984-09-01

    This bibliography of 756 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fifth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - has been included in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; (6) Uranium Mill Tailings Management; and (7) Technical Measurements Center. Chapter sections for chapters 1, 2, 4, and 6 include Design, Planning, and Regulations; Environmental Studies and Site Surveys; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. The Appendix contains a list of frequently used acronyms.

  7. The Canadian Nuclear Safety Commission regulatory process for decommissioning a uranium mining facility

    International Nuclear Information System (INIS)

    Scissons, K.; Schryer, D.M.; Goulden, W.; Natomagan, C.

    2002-01-01

    The Canadian Nuclear Safety Commission (CNSC) regulates uranium mining in Canada. The CNSC regulatory process requires that a licence applicant plan for and commit to future decommissioning before irrevocable decisions are made, and throughout the life of a uranium mine. These requirements include conceptual decommissioning plans and the provision of financial assurances to ensure the availability of funds for decommissioning activities. When an application for decommissioning is submitted to the CNSC, an environmental assessment is required prior to initiating the licensing process. A case study is presented for COGEMA Resources Inc. (COGEMA), who is entering the decommissioning phase with the CNSC for the Cluff Lake uranium mine. As part of the licensing process, CNSC multidisciplinary staff assesses the decommissioning plan, associated costs, and the environmental assessment. When the CNSC is satisfied that all of its requirements are met, a decommissioning licence may be issued. (author)

  8. Innovative and adaptive technologies in decommissioning of nuclear facilities. Final report of a coordinated research project 2004-2008

    International Nuclear Information System (INIS)

    2008-10-01

    There are dozens of old reactors and other nuclear facilities worldwide that are either being actively dismantled or are candidates for decommissioning in the near term. A significant proportion of these facilities are situated in Member States or institutions that do not have adequate expertise and technologies for planning and implementing state of the art decommissioning projects. The technology selection process is critical in that regard. The main objective of the IAEA technical activities on decommissioning is to promote the exchange of lessons learned in order to improve the technologies, thereby contributing to successful planning and implementation of decommissioning. This should be achieved through a better understanding of the decision making process in technology comparison and selection and relevant issues affecting the entire decommissioning process. The specific objectives of the Coordinated Research Project (CRP) on Innovative and Adaptive Technologies in Decommissioning of Nuclear Facilities include the following general aspects: (a) To establish methodologies and data needs for developing concepts and approaches relevant to technology comparison and selection in decommissioning; (b) To improve and expand the database on applications and performance of various types of decommissioning technologies; (c) To address specific issues for individual decommissioning technologies and generate data relevant to their comparison and selection. It is also expected that this project, and in particular the papers collected in this TECDOC, will draw Member States' attention to the practicality and achievability of timely planning and implementation of decommissioning, especially for many smaller projects. Concluding reports that summarized the work undertaken under the aegis of the CRP were presented at the third and final research coordination meeting held in Rez, Czech Republic, 3-7 December 2007, and collected in this technical publication. Operating

  9. ASTM STANDARD GUIDE FOR EVALUATING DISPOSAL OPTIONS FOR REUSE OF CONCRETE FROM NUCLEAR FACILITY DECOMMISSIONING

    International Nuclear Information System (INIS)

    Phillips, Ann Marie; Meservey, Richard H.

    2003-01-01

    Within the nuclear industry, many contaminated facilities that require decommissioning contain huge volumes of concrete. This concrete is generally disposed of as low-level waste at a high cost. Much of the concrete is lightly contaminated and could be reused as roadbed, fill material, or aggregate for new concrete, thus saving millions of dollars. However, because of the possibility of volumetric contamination and the lack of a method to evaluate the risks and costs of reusing concrete, reuse is rarely considered. To address this problem, Argonne National Laboratory-East (ANL-E) and the Idaho National Engineering and Environmental Laboratory teamed to write a ''concrete protocol'' to help evaluate the ramifications of reusing concrete within the U.S. Department of Energy (DOE). This document, titled the Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Site (1) is based on ANL-E's previously developed scrap metal recycle protocols; on the 10-step method outlined in DOE's draft handbook, Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material (2); and on DOE Order 4500.5, Radiation Protection of the Public and the Environment (3). The DOE concrete protocol was the basis for the ASTM Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning, which was written to make the information available to a wider audience outside DOE. The resulting ASTM Standard Guide is a more concise version that can be used by the nuclear industry worldwide to evaluate the risks and costs of reusing concrete from nuclear facility decommissioning. The bulk of the ASTM Standard Guide focuses on evaluating the dose and cost for each disposal option. The user calculates these from the detailed formulas and tabulated data provided, then compares the dose and cost for each disposal option to select the best option that meets regulatory requirements. With this information

  10. Integration of knowledge management system for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Iguchi, Yukihiro; Yanagihara, Satoshi

    2016-01-01

    The decommissioning of a nuclear facility is a long term project, handling information which begins from the design, construction and operation. Moreover, the decommissioning project is likely to be extended because of the lack of the waste disposal site especially in Japan. In this situation, because the transfer of knowledge and education to the next generation is a crucial issue, integration and implementation of a system for knowledge management is necessary in order to solve it. For this purpose, the total system of decommissioning knowledge management system (KMS) is proposed. In this system, we have to arrange, organize and systematize the data and information of the plant design, maintenance history, trouble events, waste management records etc. The collected data, information and records should be organized by computer support system e.g. data base system. It becomes a base of the explicit knowledge. Moreover, measures of extracting tacit knowledge from retiring employees are necessary. The experience of the retirees should be documented as much as possible through effective questionnaire or interview process. The integrated knowledge mentioned above should be used for the planning, implementation of dismantlement or education for the future generation. (author)

  11. Nuclear installations: decommissioning and dismantling

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    This document is a compilation of seven talks given during the 1995 EUROFORUM conference about decommissioning and dismantling of Nuclear installations in the European Community. The first two papers give a detailed description of the legal, financial and regulatory framework of decommissioning and dismantling of nuclear facilities in the European Union and a review of the currently available decommissioning techniques for inventory, disassembly, decontamination, remote operations and management of wastes. Other papers describe some legal and technical aspects of reactor and plants dismantling in UK, Germany, Spain and France. (J.S.)

  12. Lessons learned from application of the Swedish regulations for decommissioning of nuclear facilities - The regulator's perspective

    International Nuclear Information System (INIS)

    Efraimsson, Henrik; Amft, Martin; Leisvik, Mathias

    2016-01-01

    The paper presents an overview of the Swedish regulations for decommissioning of nuclear facilities. It describes some of the experiences that the Swedish Radiation Safety Authority has gained from the application of these regulations. The focus of the present paper lies on administrative aspects of the care and maintenance operation and on the safety related documentation that has to be prepared before dismantling commences. Lessons learned during recent years will be considered when revising the regulations for decommissioning. Also these lessons learned will help to streamline the administration of the large NPP decommissioning projects that are anticipated to commence in Sweden in the near future. (authors)

  13. Planning for decommissioning of nuclear facilities - Nuclear as a semi-sustainable energy source, the views of younger stakeholders - 59222

    International Nuclear Information System (INIS)

    Lindskog, Staffan; Labor, Bea

    2012-01-01

    Document available in abstract form only. Full text of publication follows: It is planned that many nuclear facilities will be decommissioned in the near future. This challenge includes certified repositories for LLW and ILW, procedures for classification and free release, systems for transportation, planning activities, and liaison with the public. The last item can have a substantial impact on the efficiency of decommissioning projects. Insufficient dialogue with various stakeholder groups can be a factor that drives costs, whilst appropriate programs, means and environments for communication and knowledge transfer may facilitate the establishment of contemporary and comprehensive bases for decisions and thereby also enhance the possibility for consensus and thereby achieve feasible and sustainable solutions. The programs thus decided for the decommissioning of nuclear facilities and the management of the nuclear waste must then be communicated openly and constitute an integral part of the stakeholder related activities. The nuclear renaissance implies as well as calls for newer platforms for communications with the stakeholders. This communication must include how compliance with the Polluter Pays Principle (PPP) (and also preferably the Extended Polluter Responsibility, EPR) is to be achieved

  14. Setting up decommissioning funds for nuclear facilities - a competence problem for EURATOM

    International Nuclear Information System (INIS)

    Danwitz, Th. von

    2003-01-01

    The nuclear package presented by the European Commission in the autumn of 2002 has added considerable practical significance to the problem of the vertical limits of competence between the Community and its member states within the framework of the Euratom Treaty. The question most important to Germany is the authority of the European Atomic Energy Community to oblige its member states to set up funds for financing the decommissioning of nuclear facilities. As the Euratom Treaty contains no explicit competences of Euratom for regulations of this type, the article examines the content and range of Art. 30 ff. of the Euratom Treaty, the unwritten authority resulting from factual connections and the nature of the problems involved, looks at the importance of international agreements as far as legal competences are implied, and deals with a possible competence based on the right to amend the Treaty under Art. 203, Euratom Treaty. (orig.) [de

  15. Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Michelson, D.C.; Turmer, G.S.

    1988-09-01

    The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's remedial action programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626-0568.

  16. Nuclear facility decommissioning and site remedial actions: A selected bibliography, volume 9

    International Nuclear Information System (INIS)

    Owen, P.T.; Knox, N.P.; Michelson, D.C.; Turmer, G.S.

    1988-09-01

    The 604 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the ninth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--has been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's remedial action programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Subsections for sections 1, 2, 5, and 6 include: Design, Planning, and Regulations; Environmental Studies and Site Surveys; Health, Safety, and Biomedical Studies; Decontamination Studies; Dismantlement and Demolition; Site Stabilization and Reclamation; Waste Disposal; Remedial Action Experience; and General Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at (615) 576-0568 or FTS 626-0568

  17. Possibility of applying large-scale point cloud/mixed reality technology in decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Shoji, Kimiaki

    2017-01-01

    After the accident at Tokyo Electric Company's Fukushima No. 1 nuclear power plant, decommissioning projects of nuclear power plants exceeding 40 years since the start of operation began to move in full swing. And four nuclear power plants have already been under decommissioning. Several decommissioning engineering systems (ES) have been developed according to these decommissioning projects. Various problems were clarified and many findings were obtained by these efforts. On the other, advanced information technologies and products such as three-dimensional CAD, CG, 3D laser measurement, computer aided engineering (CAE) and mixed reality (MR) are progressing rapidly. By combining these technologies and products, it has become possible not only to enhance the usefulness of existing 3D CAD data but also to enable high-level digital study that combines reality and virtual models. Furthermore, it can be applied to a wide range of fields such as demolition simulation for dismantling works of nuclear facilities, which is expected to increase in future, human resource development and skill transfer. In this paper, focusing on a video see-through method capable of displaying a virtual object at a correct position of a real image accurately reflecting the positional relationship between the real image and the virtual object, we introduce items that should contribute to the feasibility and usefulness of application to decommissioning of nuclear facilities. (author)

  18. Nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Yaziz Yunus

    1986-01-01

    A number of issues have to be taken into account before the introduction of any nuclear power plant in any country. These issues include reactor safety (site and operational), waste disposal and, lastly, the decommissioning of the reactor inself. Because of the radioactive nature of the components, nuclear power plants require a different approach to decommission compared to other plants. Until recently, issues on reactor safety and waste disposal were the main topics discussed. As for reactor decommissioning, the debates have been academic until now. Although reactors have operated for 25 years, decommissioning of retired reactors has simply not been fully planned. But the Shippingport Atomic Power Plant in Pennysylvania, the first large scale power reactor to be retired, is now being decommissioned. The work has rekindled the debate in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane. (author)

  19. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 4

    International Nuclear Information System (INIS)

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Faust, R.A.

    1983-09-01

    This bibliography of 657 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fourth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic documents of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - have been references in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; and (6) Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author, or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. Appendix A lists 264 bibliographic references to literature identified during this reporting period but not abstracted due to time constraints. Title and publication description indexes are given for this appendix. Appendix B defines frequently used acronyms, and Appendix C lists the recipients of this report according to their corporate affiliation

  20. Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    Owen, P.T.; Knox, N.P.; Fielden, J.M.; Faust, R.A.

    1983-09-01

    This bibliography of 657 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fourth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic documents of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - have been references in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; and (6) Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author, or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. Appendix A lists 264 bibliographic references to literature identified during this reporting period but not abstracted due to time constraints. Title and publication description indexes are given for this appendix. Appendix B defines frequently used acronyms, and Appendix C lists the recipients of this report according to their corporate affiliation.

  1. Application of SAFRAN Tool for Knowledge Management at the Decommissioning Stage of Nuclear Facilities

    International Nuclear Information System (INIS)

    Smetnik, A.; Potapov, V.; Kapralov, E.; Murlis, D.

    2016-01-01

    Full text: As a result of the work performed by specialists of FSUE VO “Safety” under the scope of the CRAFT Project, the IAEA methodology and SAFRAN tool were used for safety assessment of radioactive waste removal from historical near-surface storage of the radon type. SAFRAN tool can be considered as an effective tool for record keeping, safety assessment and knowledge management at the stage of decommissioning of nuclear facilities. Main advantages of SAFRAN: • it uses methodologies agreed upon at the international level, namely, by IAEA standards; • several experts can work more effectively when performing the same safety assessment. SAFRAN makes it easier to exchange experience through sharing projects and data bases; • it is helpful for systematic and structured safety assessment as per safety standards; • it manages information and data in the same software environment. (author

  2. Safety Assessment for Decommissioning of Nuclear Facilities - From Methodology to the Use of Results in Decision Making

    International Nuclear Information System (INIS)

    Batandjieva, B.; Ferch, R.; Joubert, A.; Kaulard, J.; Manson, P.; Percival, K.; Thierfeldt, St.

    2008-01-01

    The safety assessment of operational facilities in the nuclear industry is well understood and methodologies have been developed and refined over several decades. Similarly safety assessment methodologies for near surface disposal facilities have been harmonized internationally during the last few years. There is however relatively less widespread and documented experience of safety assessment for decommissioning among Member States of the International Atomic Energy Agency (IAEA) and consequently there is less commonalty of approaches internationally. The importance of safety during decommissioning was further emphasized at the first review meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, and the Berlin Conference 'Safe Decommissioning for Nuclear Activities' (14-18 October 2002). As a consequence during its June 2004 meeting the IAEA Board of Governors approved an Action Plan on Decommissioning of nuclear Facilities that requested the Secretariat 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 the IAEA launched the International Project Evaluation and Demonstration of Safety during Decommissioning of Nuclear Facilities (DeSa) in November 2004 with the following objectives: - To develop a harmonized approach to safety assessment and define the elements of safety assessment for decommissioning; - To investigate the practical applicability of the methodology and performance of safety assessments for the decommissioning of various types of facilities through a selected number of test cases; - To investigate approaches for review of safety assessments for decommissioning activities and the development of a regulatory

  3. Aerosols from metal cutting techniques typical of decommissioning nuclear facilities - experimental system for collection and characterization

    International Nuclear Information System (INIS)

    Newton, G.J.; Hoover, M.D.; Barr, E.B.; Wong, B.A.; Ritter, P.D.

    1982-01-01

    Decommissioning of radioactively contaminated sites has the potential for creating radioactive and other potentially toxic aerosols. We describe an experimental system to collect and characterize aerosols from metal cutting activities typical of those used in decommissioning of nuclear facilities. A special enclosure was designed for the experiment and consisted of a 2-in. x 4-in. stud frame with double walls of flame retardant polyethylene film. Large plexiglass windows allowed the cutting operations to be directed and filmed. Ventilation was 8500 L/min (300 CFM) exhausted through HEPA filters. Seven cutting techniques were evaluated: pipe cutter, reciprocating saw, band saw, chop saw, oxy-acetylene torch, electric arc cut rod and plasma torch. Two grinding tools were also evaluated. Materials cut were 2-, 3- and 4-in. dia schedule 40, 80 and 180 type 304L stainless steel pipe. Basic studies were done on uncontaminated pipe. Four-inch-diameter sections of schedule 180 type 304L stainless steel pipe with radioactively contaminated internal surfaces were also cut. The experiments controlled important variables including tools, cutting technique, and type and thickness of material. 15 references, 4 figures, 2 tables

  4. Decommissioning Lines-of-Inquiry for Design Review of New Nuclear Facilities

    International Nuclear Information System (INIS)

    Negin, C.A.; Urland, C.S.

    2008-01-01

    An independent review of the design of the Salt Waste Processing Facility (SWPF) at Savannah River included a requirement to address the ability to decommission the facility. This paper addresses the lines of inquiry (that were developed for the review and their use in future for reviews of other projects, referred to herein as 'DDLOI'. Decommissioning activities for almost any type of facility are well within the technological state-of-the-art. The major impacts for complications resulting from insufficient consideration during design of a new facility that involves radioactive processes and/or material is the cost of: a) gaining access to high radiation areas and b) dealing with high levels of contamination. For this reason, the DDLOI were developed as a way of raising the awareness of designers and design reviewers to design features that can impede or facilitate ultimate decommissioning. The intent is that this report can be used not only for review, but also by engineers in the early stages of design development when requirements are being assembled. The focus for the DDLOI is on types of facilities that contain nuclear and/or radioactive processes and materials. The level of detail is more specific than would be found in decommissioning plans prepared for regulatory purposes. In commencing this review, the author's could find no precedent for a systematic review of design for decommissioning that included results of a review. Therefore, it was decided to create a report that would provide detailed lines of inquiry along with the rationale for each. The resulting DDLOI report included 21 topical areas for design review. The DDLOI combined the authors' experience in developing baselines for facilities to be deactivated or demolished with prior publications by the U.S. Army and the International Atomic Energy Agency. These two references were found via an Internet search and were the only ones judged to be useful at a field application level. Most others

  5. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes

    International Nuclear Information System (INIS)

    1997-09-01

    This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D ampersand D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. Citations to foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - have been included in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D ampersand D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword

  6. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Vol. 18. Part 2. Indexes

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This bibliography contains 3638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D&D), uranium mill tailings management, and site remedial actions. This report is the eighteenth in a series of bibliographies prepared annually for the U.S. Department of Energy (DOE) Office of Environmental Restoration. Citations to foreign and domestic literature of all types - technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions - have been included in Part 1 of the report. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D&D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Programs; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluations; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues. Within the 16 sections, the citations are sorted by geographic location. If a geographic location is not specified, the citations are sorted according to the document title. In Part 2 of the report, indexes are provided for author, author affiliation, selected title phrase, selected title word, publication description, geographic location, and keyword.

  7. Evolution and development of laws, regulations, criteria and human resources to ensure the safe decommissioning of nuclear facilities in Thailand

    International Nuclear Information System (INIS)

    Keinmeesuke, S.

    2006-01-01

    The Research Reactor, TRR-1 (renamed TRR-1/M1 after core replacement) in Thailand has been operated for more than 43 years. This ageing reactor will be facing shutdown in the near future. Laws and Regulations have been continually developed to assure the safe operation of nuclear facilities, particularly of the research reactor, and to ensure the safe decommissioning of the reactor after its operational life. However, the Thai nuclear legislation is still not applicable to a number of areas. Office of Atoms for Peace is working toward development of a new consolidated Act. In addition, the licensing steps for modification and decommissioning are added to the new Ministerial Regulation and to the new guidance documents on the licensing process for research reactors. Regulations, guidance and criteria for approval of decommissioning are being developed using the IAEA Safety Standards Series as the main basis for drafting. Human resource development is considered as one of the key important factor to ensure safe decommissioning of the installation. Staffing and training of the operating organization and the regulatory body personnel have been addressed to ensure the achievement of competency level. Simple methods and technologies are the best means for implementation while learning from experience of others will help and support us in our attempt to be the 'second First'. IAEA advice and assistance on the decommissioning of nuclear facilities in countries with limited resources is desirable. (author)

  8. Proceedings of the Symposium on Recycling of Metals arising from Operation and Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    2014-04-01

    The Symposium for the Recycling of Metals Arising from Operation and decommissioning of Nuclear Facilities was held in April 2014 at Studsvik's facility in Nykoeping, Sweden. The Symposium, hosted by Studsvik in conjunction with the Nuclear Energy Agency (NEA) of the Organisation for Economic Co-operation and Development (OECD) and the International Atomic Energy Agency (IAEA), covered a wide range of topics concerning current practice, experiences and innovations within the management of contaminated metallic radioactive material. The primary objective was to understand the differing approaches to clearance and recycling of materials from the nuclear industry across Europe in order to appreciate the issues faced from recovering resources once the material meets a country's clearance requirements. The outcome of the symposium has provided some interesting reflections for national and international bodies to consider when developing waste management guidance and policies. Over the three days of the symposium, presentations split into six topical sessions and posters regarding the recycling of contaminated metals were viewed by more than 150 people from 19 different countries. A series of group discussions were also held following each session to promote learning about current practices, highlight strategic issues related to metals recycling and develop professional networks across the industry. To stimulate discussion, a series of questions were posed at each group and the outcomes captured for inclusion within this report

  9. 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)

    2013-01-01

    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).

  10. Environmental assessment as a planning tool for the decommissioning of a nuclear research facility in Canada

    International Nuclear Information System (INIS)

    Klukas, M.H.; Grondin, D.J.; Helbrecht, R.A.

    2002-01-01

    Whiteshell Laboratories, a nuclear research facility operated by Atomic Energy of Canada Ltd. (AECL), have provided research facilities for the Canadian Nuclear Industry since the early 1960's. In 1997, AECL made a business decision to discontinue research programs and operations at the laboratories. Shortly thereafter the decision was made in agreement with the Federal Government of Canada to decommission the laboratories. In compliance with its own policy and to meet the requirements of the Canadian Legislation, AECL assessed the potential environmental effects of the project. The Environmental Assessment included studies to evaluate he feasibility of leaving two major project components in place; low-level radioactive waste in trenches located at the Whiteshell Laboratories site and river sediments contaminated from operational effluent releases. For both project components, it was determined that managing the wastes in the existing location was environmentally sound. An extensive follow-up program, comprising of additional monitoring and analysis to verify these findings will be implemented. As a result of these assessments and the assessments for other project components it was concluded that the project was not likely to cause significant adverse effects. The assessment decision was accepted by the Minister of the Environment in 2002 April. (author)

  11. Applicability of water-jet cutting technology to nuclear facility decommissioning

    International Nuclear Information System (INIS)

    Abe, Tadashi; Nisizaki, Tadashi; Matumura, Hiroyuki; Ikemoto, Yosikazu; Simizu, Hideki

    1991-01-01

    In nuclear facilities there exist, besides relatively simple components, such as vessels and piping, numerous complex components including the multilayered plate with water layer in between, a bunch of thin tubes and composite lamination of dissimilar materials like metal/non-metal. In conventional development of reactor dismantling technology, the technology development has been made mainly for remote cutting of thick-walled structures like the reactor pressure vessel and the reactor internals. These techniques, however, are not always suitable in cutting the above-mentioned structures. As means of cutting such structures efficiently, these is available the abrasion water-jet cutting technology. This technology is now drawing attention for cutting or shaping new materials like composite material and ceramics in high precision and high efficiency. In the present report by way of its feasibility in nuclear facilities decommissioning the following are described. Principle and features of the water-jet cutting technology, system con-figuration, cutting or shaping performance, and some examples of the cutting and shaping. (author)

  12. Preliminary dismantling for the decommissioning of nuclear licensed facilities at the CEA Centre in Fontenay aux Roses

    International Nuclear Information System (INIS)

    Estivie, D.; Bohar, M.P.; Jeanjacques, M.; Binet, C.

    2008-01-01

    Under the perimeter modification programme for the Nuclear Licensed Facilities (NLFs) of the French Atomic Energy Commission centre at Fontenay aux Roses (CEN-FAR), preliminary dismantling work proved necessary to decommission the buildings outside the nuclear perimeter and create interim storage areas for waste packages. This summary describes the dismantling of Buildings 07, 53 and 91/54, which are the most representative of the preliminary dismantling work. (author)

  13. Financial Planning as a Tool for Efficient and Timely Decommissioning of Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Cato, Anna; Lindskog, Staffan; Sjoeblom, Rolf

    2008-01-01

    It is generally recognized in the technical and economical literature that reliable cost evaluations with adequate estimates also of the errors and uncertainties involved are necessary in order for rational and appropriate management decisions to be made on any major plant investment. Such estimates are required for the selection of technologies to be applied and for selection to be made between alternative technologies and designs as well as for the overall financing issues including the one of whether to go ahead with the project. Inadequacies in the cost calculations typically lead to suboptimal decisions and ultimately substantial overruns and/or needs for retrofits. Actually, a very strict discipline has to be applied with adaptation of the approach used with regard to the stage of the planning. Deviations from the expected tend to raise the estimated cost much more frequently than they lower it. The same rationale applies to planning and cost calculations for decommissioning of nuclear research facilities. There are, however, many reasons why such estimations may be very treacherous to carry out. This will be dealt with in the following. The knowledge base underlying the present paper has been developed and accumulated as a result of the research that the Swedish Nuclear Power Inspectorate (SKI) has carried out in support of its regulatory oversight over the Swedish system of finance. The findings are, however, equally applicable and appropriate for implementers in their planning, decision, monitoring and evaluation activities. In the nineteen fifties and sixties, Sweden had a comprehensive program for utilization of nuclear power including uranium mining, fuel fabrication, reprocessing and domestically developed heavy water reactors. Examples of facilities are presented in Figures 1-5. Eventually, the development work lead to the present nuclear program with ten modern light water reactors in operation at present. According to Swedish law, those who benefit

  14. Los Alamos National Laboratory case studies on decommissioning of research reactors and a small nuclear facility

    International Nuclear Information System (INIS)

    Salazar, M.D.

    1998-01-01

    Approximately 200 contaminated surplus structures require decommissioning at Los Alamos National Laboratory. During the last 10 years, 50 of these structures have undergone decommissioning. These facilities vary from experimental research reactors to process/research facilities contaminated with plutonium-enriched uranium, tritium, and high explosives. Three case studies are presented: (1) a filter building contaminated with transuranic radionuclides; (2) a historical water boiler that operated with a uranyl-nitrate solution; and (3) the ultra-high-temperature reactor experiment, which used enriched uranium as fuel

  15. Los Alamos National Laboratory case studies on decommissioning of research reactors and a small nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Salazar, M.D.

    1998-12-01

    Approximately 200 contaminated surplus structures require decommissioning at Los Alamos National Laboratory. During the last 10 years, 50 of these structures have undergone decommissioning. These facilities vary from experimental research reactors to process/research facilities contaminated with plutonium-enriched uranium, tritium, and high explosives. Three case studies are presented: (1) a filter building contaminated with transuranic radionuclides; (2) a historical water boiler that operated with a uranyl-nitrate solution; and (3) the ultra-high-temperature reactor experiment, which used enriched uranium as fuel.

  16. Vinca nuclear decommissioning program

    International Nuclear Information System (INIS)

    Pesic, M.; Subotic, K.; Sotic, O.; Plecas, I.; Ljubenov, V.; Peric, A.

    2002-01-01

    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)

  17. Nuclear decommissioning and society

    International Nuclear Information System (INIS)

    Pasqualetti, M.J.

    1990-01-01

    Links between decommissioning in general, reactor decommissioning in particular, and the public are indexed. The established links are recognised and others, such as jobs, are discussed. Finally the links with policy, such as political geography, and wider issues of the environment and public concern over waste disposal are considered. Decommissioning is a relatively new field where public opinion must now be considered but it has implications both for existing nuclear power plants and those planned for the future, especially in their siting. This book looks especially at the situation in the United Kingdom. There are twelve papers, all indexed separately. (UK)

  18. Reasons for immediate decommissioning of all nuclear facilities put forward by union members

    International Nuclear Information System (INIS)

    Scheer, J.

    1988-01-01

    The author presents his arguments against the use of nuclear energy from the health hazard point of view, describing the damaging effects of radioactive radiation as a result of increasing environmental radioactivity due to the operation of nuclear installations, or as a consequence of nuclear accidents. The economic problems resulting from an immediate decommissioning of nuclear power plants - development of electricity demand and costs - are judged to be solvable, and decommissioning, the author says, would create new jobs. Another immediate response to the latest irregularities disclosed in the nuclear waste management industry should be to establish public supervisory bodies consisting of non-biased experts who can be found in ecologic research institutes or in other independent monitoring and measuring institutions. (HSCH) [de

  19. Decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Friske, A.; Thiele, D.

    1988-01-01

    The IAEA classification of decommissioning stages is outlined. The international development hitherto observed in decommissioning of nuclear reactors and nuclear power stations is presented. The dismantling, cutting and decontamination methods used in the decommissioning process are mentioned. The radioactive wastes from decommissioning are characterized, the state of the art of their treatment and disposal is given. The radiation burdens and the decommissioning cost in a decommissioning process are estimated. Finally, some evaluation of the trends in the decommissioning process of nuclear power plants is given. 54 refs. (author)

  20. Application of the New Decommissioning Regulation to the Nuclear Licensed Facilities (NLF) at Fontenay-aux-Roses's Nuclear Center (CEA)

    International Nuclear Information System (INIS)

    Sauret, Josiane; Piketty, Laurence; Jeanjacques, Michel

    2008-01-01

    This abstract describes the application of the new decommissioning regulation on all Nuclear Licensed Facilities (NLF is to say INB in French) at Fontenay-aux-Roses's Center (CEA/FAR). The decommissioning process has been applied in six buildings which are out of the new nuclear perimeter proposed (buildings no 7, no 40, no 94, no 39, no 52/1 and no 32) and three buildings have been reorganized (no 54, no 91 and no 53 instead of no 40 and no 94) in order to increase the space for temporary nuclear waste disposal and to reduce the internal transports of nuclear waste on the site. The advantages are the safety and radioprotection improvements and a lower operating cost. A global safety file was written in 2002 and 2003 and was sent to the French Nuclear Authority on November 2003. The list of documents required is given in the paragraph I of this paper. The main goals were two ministerial decrees (one decree for each NLF) getting the authorization to modify the NLF perimeter and to carry out cleaning and dismantling activities leading to the whole decommissioning of all NLF. Some specific authorizations were necessary to carry out the dismantling program during the decommissioning procedure. They were delivered by the French Nuclear Safety Authority (FNSA) or with limited delegation by the General Executive Director (GED) on the CEA Fontenay-aux-Roses's Center, called internal authorization. Some partial dismantling or decontamination examples are given below: - evaporator for the radioactive liquid waste treatment station (building no 53): FNSA authorization: phase realised in 2002/2003. - disposal tanks for the radioactive liquid waste treatment station (building no 53) FNSA authorization: phase realised in 2004, - incinerator for the radioactive solid waste treatment station (building no 07): FNSA authorization: operation realised in 2004, - research equipments in the building no. 54 and building no. 91: internal authorization ; realised in 2005, - sample

  1. Appendix 4. Documentation of sufficient capacity facility for spent nuclear fuel and radioactive waste management and its compliance with the decommissioning strategy and schedule

    International Nuclear Information System (INIS)

    2007-01-01

    In this chapter the documentation of sufficient capacity facility for spent nuclear fuel and radioactive waste management and its compliance with the decommissioning strategy and schedule of the NPP A-1 are presented.

  2. Recycling and Reuse of Materials Arising from the Decommissioning of Nuclear Facilities. A Report by the NEA Co-operative Program on Decommissioning

    International Nuclear Information System (INIS)

    Ooms, Bart; Verwaest, Isi; Legee, Frederic; Nokhamzon, Jean-Guy; Pieraccini, Michel; Poncet, Philippe; Franzen, Nicole; Vignaroli, Tiziano; Herschend, Bjoern; Benest, Terry; Loudon, David; Favret, Derek; Weber, Inge; )

    2017-01-01

    Large quantities of materials arising from the decommissioning of nuclear facilities are non-radioactive per se. An additional, significant share of materials is of very low-level or low-level radioactivity and can, after having undergone treatment and a clearance process, be recycled and reused in a restricted or unrestricted way. Recycle and reuse options today provide valuable solutions to minimise radioactive waste from decommissioning and at the same time maximise the recovery of valuable materials. The NEA Co-operative Programme on Decommissioning (CPD) prepared this overview on the various approaches being undertaken by international and national organisations for the management of slightly contaminated material resulting from activities in the nuclear sector. The report draws on CPD member organisations' experiences and practices related to recycling and reuse, which were gathered through an international survey. It provides information on improvements and changes in technologies, methodologies and regulations since the 1996 report on this subject, with the conclusions and recommendations taking into account 20 years of additional experience that will be useful for current and future practitioners. Case studies are provided to illustrate significant points of interest, for example in relation to scrap metals, concrete and soil

  3. Decommissioning of the nuclear licensed facilities at the Fontenay aux Roses CEA Center; cleanup of nuclear licensed facility 57 and monitoring of operations and operating feedback

    International Nuclear Information System (INIS)

    Estivie, D.; Bohar, M.P.; Jeanjacques, M.; Binet, C.; Bremond, M.P.; Poyau, C.; Mandard, L.; Boissonneau, J.F.; Fouquereau, A.; Pichereau, E.

    2008-01-01

    This is a summary of the program for the decommissioning of all the CEA Licensed Nuclear Facilities in Fontenay aux Roses. The particularity of this center is now it is located in a built-up area. It is presented like example the operations to clean up the equipment of the Nuclear Licensed Facility 57 (NLF 57). Due to the diversity of the research and development work carried out on the reprocessing of spent fuel in it, this installation is emblematic of many of the technical and organizational issues liable to be encountered in the final closure of nuclear facilities. It was developed a method applied to establish the multi-annual budget, monitor the progress of operations and integrate, as work continues, the operating feedback. (author)

  4. Safety assesment necessary in selecting the technologies for partial decommissioning of nuclear facilities. Application to research reactors

    International Nuclear Information System (INIS)

    Niculae, O.; Stan, C.; Vladescu, G.

    2005-01-01

    The main goal of this work is identification and evaluation of safety indicators - quantities used in monitoring the safety assurance during decommissioning processes in nuclear facilities identification of safety indicators is made on basis of qualitative and quantitative analysis, effected for both normal decommissioning, as well as in case of foreseen event occurrence. The safety indicators form an integrated system which can be represented by a pyramidal structural with the following levels (in increasing complexity order): specific indicators, strategic indicators, overall indicators, safety closure. This work suggests that evaluation of safety assurance level during the conduct of a decommissioning process to be based on the overall analysis of the set of indicators emphasizing not only the evaluation of individual safety indicators but also the interdependencies between them. The evaluation method is based on the 'step-by-step' principle. The evaluation was carried-out either directly or by means of dedicated evaluation forms which cover both quantitative and qualitative aspects of the analysis. At the some time identified are the adequate protection measures for the personnel implied in decommissioning, as well as for population and environment. The paper present also technologies adequate in the decommissioning. (authors)

  5. Standard Guide for Evaluating Disposal Options for Concrete from Nuclear Facility Decommissioning

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2002-01-01

    1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: (1) to show that the release meets existing release criteria, (2) to establish a basis to request release of the concrete on a case-by-case basis, (3) to develop a basis for establishing release criteria where none exists. 1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” (1) from ...

  6. A dose assessment method for arbitrary geometries with virtual reality in the nuclear facilities decommissioning

    Science.gov (United States)

    Chao, Nan; Liu, Yong-kuo; Xia, Hong; Ayodeji, Abiodun; Bai, Lu

    2018-03-01

    During the decommissioning of nuclear facilities, a large number of cutting and demolition activities are performed, which results in a frequent change in the structure and produce many irregular objects. In order to assess dose rates during the cutting and demolition process, a flexible dose assessment method for arbitrary geometries and radiation sources was proposed based on virtual reality technology and Point-Kernel method. The initial geometry is designed with the three-dimensional computer-aided design tools. An approximate model is built automatically in the process of geometric modeling via three procedures namely: space division, rough modeling of the body and fine modeling of the surface, all in combination with collision detection of virtual reality technology. Then point kernels are generated by sampling within the approximate model, and when the material and radiometric attributes are inputted, dose rates can be calculated with the Point-Kernel method. To account for radiation scattering effects, buildup factors are calculated with the Geometric-Progression formula in the fitting function. The effectiveness and accuracy of the proposed method was verified by means of simulations using different geometries and the dose rate results were compared with that derived from CIDEC code, MCNP code and experimental measurements.

  7. Virtual reality based adaptive dose assessment method for arbitrary geometries in nuclear facility decommissioning.

    Science.gov (United States)

    Liu, Yong-Kuo; Chao, Nan; Xia, Hong; Peng, Min-Jun; Ayodeji, Abiodun

    2018-05-17

    This paper presents an improved and efficient virtual reality-based adaptive dose assessment method (VRBAM) applicable to the cutting and dismantling tasks in nuclear facility decommissioning. The method combines the modeling strength of virtual reality with the flexibility of adaptive technology. The initial geometry is designed with the three-dimensional computer-aided design tools, and a hybrid model composed of cuboids and a point-cloud is generated automatically according to the virtual model of the object. In order to improve the efficiency of dose calculation while retaining accuracy, the hybrid model is converted to a weighted point-cloud model, and the point kernels are generated by adaptively simplifying the weighted point-cloud model according to the detector position, an approach that is suitable for arbitrary geometries. The dose rates are calculated with the Point-Kernel method. To account for radiation scattering effects, buildup factors are calculated with the Geometric-Progression formula in the fitting function. The geometric modeling capability of VRBAM was verified by simulating basic geometries, which included a convex surface, a concave surface, a flat surface and their combination. The simulation results show that the VRBAM is more flexible and superior to other approaches in modeling complex geometries. In this paper, the computation time and dose rate results obtained from the proposed method were also compared with those obtained using the MCNP code and an earlier virtual reality-based method (VRBM) developed by the same authors. © 2018 IOP Publishing Ltd.

  8. 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 ...

  9. Radiological, technical and financial planning for decommissioning of small nuclear facilities in Sweden - 16177

    International Nuclear Information System (INIS)

    Lindskog, Staffan; Sjoeblom, Rolf

    2009-01-01

    On November 1 2008, a new ordinance came into force in Sweden. It extends the implementation of nuclear liability to all nuclear facilities and companies, regardless of size. The Government has authorized the Swedish Radiation Safety Authority (SSM) to issue further regulation as warranted and appropriate, and commissioned the same Authority to oversee the implementation. Consequently, SSM is presently conducting research in order to establish a basis for the implementation of the ordinance to smaller facilities and enterprises. The goal is to enable finance to be assured in an efficient manner so that any burden on the companies is as small as possible. Thus, 'functional requirements' are identified, and used as a basis for various investigations. The aspects include technical and cost calculation prerequisites, as well as various domains of law: the environmental code, radiation and nuclear safety, financial reporting, and criminal law. It is found that the basis for the differentiation among the facility operators and owners should be the cost and the associated uncertainty. Thus, a cost calculation will have to be carried out by all. It should be based on available standards and guidance documents. It is found that this is a requirement that already exists elsewhere in the legislation, and thus no additional burden is imposed on the companies. It is found that segregated funds is the preferred option for long-term liabilities. Securities are suitable for short-term liabilities provided that the economy of the company in question is sound. Securities might also be used for long-term liabilities to cover uncertainty. It is proposed that a de minimis limit of at least kSEK 25 (about keuros 2,4 and k$ 3,4) is used. An important reason for this is that lower limits might be incompatible with the rules for financial reporting. It is also proposed that securities might be used also for long-term commitments if the total environmental liability does not exceed 1

  10. Impact of the decommissioning of nuclear facilities and radioactive waste trafficking in Africa

    International Nuclear Information System (INIS)

    Abukabar, B. G.

    2007-01-01

    Africa is the world's second largest and the most populated continent after Asia, it has a total population of approximately 800 million people. It comprises of 54 sovereign nations out of which 36 are coastal countries and blessed with over 100 Seaports. Apart from Nigeria, South Africa, Egypt, Libya, Morocco, Tunisia and Libya, all the other remaining African countries are extremely poor and unviable. As a result of this, Africa has been experiencing a lot of civil unrest since the 1960s when most of the African countries gained their independence from their former colonial masters, the civil unrest in countries like Angola, Democratic Republic of Congo, Sudan, Burundi, Rwanda, Mozambique, Liberia, Sierra Leon and recently in Cote D'Ivoire, are good examples. In addition to abject poverty of less than 1$ per person per day makes trafficking in drugs, arms, humans and weaponry trade on the continent becomes much more rampant. Today the continent is experiencing the coming of a new evil deal called 'Trade in radioactive waste'; which involves the transporting of materials from existing or decommissioned nuclear plants ranging from fairly used Trucks, laboratory equipment s, office facilities, clothing materials like booths and raincoats, roofing sheets and even toxic waste from the developed countries to it's waste bin in Africa, where it is unsafely disposed after collecting millions of dollars from It's original owners (UN report, 2001). Recent statistics have revealed that most of the people involved in the evil businesses of trafficking in drugs, human, arms and trading in weaponry, are diverting in to the so called new evil business of 'Trade in Radioactive waste' because this new evil business financially exceeds the rest of the above listed evil businesses. This is clearly proved by the recent toxic waste disposed in Abidjan Cot Devoir in August 2006. The materials from the decommissioned nuclear plant sites can be hazardous if for example a roofing sheet

  11. Summary of some Recent Work on Financial Planning for Decommissioning of Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lindskog, Staffan (Swedish Nuclear Power Inspectorate, Stockholm (Sweden)); Sjoeblom, Rolf (Tekedo AB, Nykoeping (Sweden))

    2008-06-15

    The new European Union Environmental Liability Directive (ELD) together with the new standard and the increased awareness of the implications of the statements on Environmental liabilities in the IFRS/IA high-light the need for appropriate planning for decommissioning including cost estimations and waste fund management. These new regulations and standards are in some respects more stringent than the strictly nuclear rules. Consequently, The Swedish Nuclear Power Inspectorate has sought communication with non-nuclear actors in the area, including the participation in the recent meeting Environmental Economics and Investment Assessment 11, 27-30 May, 2008, Cadiz, Spain. The present compilation of publications on decommissioning and associated cost calculations in Sweden was prompted by these contacts. The compilation comprises 14 reports published during the last four years

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-07-15

    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.

  13. Decommissioning of Facilities. General Safety Requirements. Pt. 6 (Spanish Edition)

    International Nuclear Information System (INIS)

    2017-01-01

    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.

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

    International Nuclear Information System (INIS)

    2015-01-01

    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

  15. Decommissioning nuclear installations

    International Nuclear Information System (INIS)

    Dadoumont, J.

    2010-01-01

    When a nuclear installation is permanently shut down, it is crucial to completely dismantle and decontaminate it on account of radiological safety. The expertise that SCK-CEN has built up in the decommissioning operation of its own BR3 reactor is now available nationally and internationally. Last year SCK-CEN played an important role in the newly started dismantling and decontamination of the MOX plant (Mixed Oxide) of Belgonucleaire in Dessel, and the decommissioning of the university research reactor Thetis in Ghent.

  16. Decommissioning of Active Ventilation Systems in a Nuclear R and D Facility to Prepare for Building Demolition (Whiteshell Laboratories Decommissioning Project, Canada) - 13073

    International Nuclear Information System (INIS)

    Wilcox, Brian; May, Doug; Howlett, Don; Bilinsky, Dennis

    2013-01-01

    Whiteshell Laboratories (WL) is a nuclear research establishment owned by the Canadian government and operated by Atomic Energy of Canada Limited (AECL) since the early 1960's. WL is currently under a decommissioning license and the mandate is to remediate the nuclear legacy liabilities in a safe and cost effective manner. The WL Project is the first major nuclear decommissioning project in Canada. A major initiative underway is to decommission and demolish the main R and D Laboratory complex. The Building 300 R and D complex was constructed to accommodate laboratories and offices which were mainly used for research and development associated with organic-cooled reactors, nuclear fuel waste management, reactor safety, advanced fuel cycles and other applications of nuclear energy. Building 300 is a three storey structure of approximately 16,000 m 2 . In order to proceed with building demolition, the contaminated systems inside the building have to be characterized, removed, and the waste managed. There is a significant focus on volume reduction of radioactive waste for the WL project. The active ventilation system is one of the significant contaminated systems in Building 300 that requires decommissioning and removal. The active ventilation system was designed to manage hazardous fumes and radioactivity from ventilation devices (e.g., fume hoods, snorkels and glove boxes) and to prevent the escape of airborne hazardous material outside of the laboratory boundary in the event of an upset condition. The system includes over 200 ventilation devices and 32 active exhaust fan units and high efficiency particulate air (HEPA) filters. The strategy to remove the ventilation system was to work from the laboratory end back to the fan/filter system. Each ventilation duct was radiologically characterized. Fogging was used to minimize loose contamination. Sections of the duct were removed by various cutting methods and bagged for temporary storage prior to disposition

  17. Current significant challenges in the decommissioning and environmental remediation of radioactive facilities: A perspective from outside the nuclear industry.

    Science.gov (United States)

    Gil-Cerezo, V; Domínguez-Vilches, E; González-Barrios, A J

    2017-05-01

    This paper presents the results of implementing an extrajudicial environmental mediation procedure in the socioenvironmental conflict associated with routine operation of the El Cabril Disposal Facility for low- and medium- activity radioactive waste (Spain). We analyse the socio-ethical perspective of this facility's operation with regard to its nearby residents, detailing the structure and development of the environmental mediation procedure through the participation of society and interested parties who are or may become involved in such a conflict. The research, action, and participation method was used to apply the environmental mediation procedure. This experience provides lessons that could help improve decision-making processes in nuclear or radioactive facility decommissioning projects or in environmental remediation projects dealing with ageing facilities or with those in which nuclear or radioactive accidents/incidents may have occurred. Copyright © 2017 Elsevier Ltd. All rights reserved.

  18. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  19. The use of modern engineered polymer coatings and products in decommissioning of nuclear facilities and plant

    International Nuclear Information System (INIS)

    Christie, K.; Harris, C.W.; Morris, O.P.; Atkinson, P.

    2014-01-01

    During decommissioning of nuclear plant, problems can arise whereby leaks and cracks appear which may require repair or remediation. Following clean-up processes radionuclides may be exposed in concrete or structures such ponds which require sealing to prevent atmospheric release and to obtain a reduction in operator dose. There are a number of polymer based products on the market which with care and skillful selection can be utilised to aid decommissioning and to add reassurance to regulators that radionuclide release cannot occur. Choosing between them is difficult due to the fact that the standard coating tests cannot reliably distinguish between the various products since these modern polymers are all significantly tougher than previous generations of coating technologies. There is therefore a need to develop new bespoke tests which replicate the likely failure modes of the plant and which demonstrate which products are likely to perform well in real life situations. (authors)

  20. Overview of management of low and intermediate level radioactive wastes at the Institute for Nuclear Research for to save management of the waste from decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Bujoreanu, D.; Bujoreanu, L.

    2010-01-01

    The national policy of radioactive waste management fully complies with the international requirements established by 'Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management and with the EURATOM treaty, directives, recommendations and policy of radioactive waste management promoted at the level of the European Union. The Institute for Nuclear Research Pitesti (INR) has its own Radwaste Treatment Plant. The object of activity is to treat and condition radioactive waste resulted from the nuclear facility. According to the National Nuclear Program, the institute is the main support for implementation of the methods and technologies for conditioning and disposal of radioactive waste generated by Cernavoda NPP. For all these, in accordance with the Governmental order no. 11/2003, INR shall must prepare and manage the decommissioning projects of its own facilities and to upgrade the facilities for the management of the radioactive waste resulting from decommissioning activities. (authors)

  1. REVIEW OF INDUSTRIES AND GOVERNMENT AGENCIES FOR TECHNOLOGIES APPLICABLE TO DEACTIVATION AND DECOMMISSIONING OF NUCLEAR WEAPONS FACILITIES

    Energy Technology Data Exchange (ETDEWEB)

    Reilkoff, T. E.; Hetland, M. D.; O' Leary, E. M.

    2002-02-25

    The Deactivation and Decommissioning Focus Area's (DDFA's) mission is to develop, demonstrate, and deploy improved deactivation and decommissioning (D&D) technologies. This mission requires that emphasis be continually placed on identifying technologies currently employed or under development in other nuclear as well as nonnuclear industries and government agencies. In support of DDFA efforts to clean up the U.S. Department of Energy's (DOE's) radiologically contaminated surplus facilities using technologies that improve worker safety, reduce costs, and accelerate cleanup schedules, a study was conducted to identify innovative technologies developed for use in nonnuclear arenas that are appropriate for D&D applications.

  2. Russian conceptions of plant life management and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Bugaenko, S.E.; Butorin, S.L.

    2000-01-01

    Plant life management (PLIM) of nuclear power plant is the concept and practice to provide profitability of safe operation of nuclear electricity-generating installations. Therefore, application of the PLIM technology is a unique possibility for the nuclear power not only to preserve its presence at the generated electricity market but also to enlarge it there at the first quarter of the third millennium. PLIM is considered as the concept and procedure covering the whole life cycle of NPP, consisting of three main phases: pre-operation, operation, post-operation. When considering the list of the main standard works for PLIM, one can notice that the structure of a full volume of works can be presented as the sum of two constituents: specific for a particular power unit and universal one. A specific constituent implies realising the PLIM process at a particular power unit, and universal one implies development scientific-methodological, technological and normative basis supporting PLIM process. The concept of decommissioning NPP power units was developed and adopted in 1991, and nowadays is renewed. Its main principles and provisions correspond to a general approach to decommissioning nuclear power plants which was adopted in international practice and recommended in the IAEA documents. Elimination of NPP power unit is adopted in it as the basic option

  3. Summary of feasibility studies on in situ disposal as a decommissioning option for nuclear facilities

    International Nuclear Information System (INIS)

    Helbrecht, R.A.

    2002-01-01

    A scoping study was conducted over the period 1998-2000 to consider the feasibility of in situ disposal as a decommissioning option for AECL's Nuclear Power Demonstration Reactor located at Rolphton, Ontario. The results of a detailed assessment are summarized and the study concludes that in situ disposal appears feasible. Additional work required to confirm the results is also identified. A second in situ component, contaminated Winnipeg River sediments at AECL's Whiteshell Laboratory located in Manitoba, was also evaluated. That study concluded that in situ abandonment would have no adverse impact on aquatic life, humans and the environment. A summary of the study is presented as an appendix to the report. (author)

  4. Decommissioning three nuclear reactors at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Montoya, G.M.; Salazar, M.

    1992-01-01

    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

  5. Ethics of nuclear decommissioning

    International Nuclear Information System (INIS)

    Surrey, John

    1992-01-01

    What to do with the numerous reactors that reach the end of their operating lives over the next 30 years involves ethical issues of an intergenerational kind. This essay examines various nuclear decommissioning options in the light of the ethical issues. Prompt dismantlement seems preferable to other options involving postponed dismantlement, entombment of some kind or doing nothing. It would avoid bequeathing future generations with the disamenity of entombed reactors or responsibility for dismantling other disused reactors. The choice of option also depends on the health risks through time and whether a sufficient decommissioning fund exists to avoid handing down debt and constrained choice. There is a strong case for supporting research and development from public funds to develop the technology and reduce both the health risks and the costs, especially if dismantlement is left to a future generation. (author)

  6. Decommissioning Licensing Process of Nuclear Installations in Spain

    International Nuclear Information System (INIS)

    Correa Sainz, Cristina

    2016-01-01

    The Enresa experience related to the decommissioning of nuclear facilities includes the decommissioning of the Vandellos I and Jose Cabrera NPPs. The Vandellos I gas-graphite reactor was decommissioned in about five years (from 1998 to 2003) to what is known as level 2. In February 2010, the decommissioning of Jose Cabrera power plant has been initiated and it is scheduled to be finished by 2018. The decommissioning of a nuclear power plant is a complex administrative process, the procedure for changing from operation to decommissioning is established in the Spanish law. This paper summarizes the legal framework defining the strategies, the main activities and the basic roles of the various agents involved in the decommissioning of nuclear facilities in Spain. It also describes briefly the Licensing documents required to obtain the decommissioning authorization and the Enresa point of view, as licensee, on the licensing decommissioning process. (author)

  7. Nuclear decommissioning in Italy

    International Nuclear Information System (INIS)

    Tripputi, I.

    2005-01-01

    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

  8. Study on the state-of-the-arts technologies and policy trends for the decommissioning of nuclear installations and facilities

    International Nuclear Information System (INIS)

    Jeong, G. J.; Park, J. H.; Jeong, U. S. and others

    2005-12-01

    D and D project of the nuclear facilities is now the one of the biggest projects among the nuclear ones in the world. The nuclear facilities have their unique characteristics so making preparations about technical research in advance is very important in economic side and worker's protection side. Especially, because workers have a high possibility to contact radioactive material directly, an automation technology and shielding technology for worker's protection as well as a system development which can perform D and D work efficiently are necessary for D and D project. The waste reduction technology development, D and D equipment development, container development, and the study related the establishment of the level of the release regulation for radioactive waste are also important. The purpose of this research is to grasp of the national and internal D and D status for the nuclear facilities and to estimate them so we expect to prevent the possibility of a tremendous economical loss as the initiative of the nuclear D and D market is lost due to not understand the situation about the status of the related technologies. And we also expect to practical use the accumulated experience to decommissioning facilities in North

  9. Environmental survey near a decommissioning nuclear facility: example of tritium monitoring in the terrestrial environment of Creys-Malville - Environmental survey near a nuclear facility undergoing decommissioning: example of tritium monitoring in the terrestrial environment of Creys-Malville

    Energy Technology Data Exchange (ETDEWEB)

    Boyer, C.; Gontier, G.; Chauveau, J.L. [EDF CIDEN, Division Environnement, 154 Avenue Thiers, 69458 Lyon (France); Pourcelot, L.; Roussel-Debet, S.; Cossonnet, P.C. [IRSN, LERCM Cadarache and LMRE Orsay (France); Jean-Baptiste, P. [LSCE, UMR 1572-CEA/CNRS/UVQS, 91198 Gif sur Yvette (France)

    2014-07-01

    and adapts it to the specific radionuclides generated by the decommissioning phase. Some results from the terrestrial monitoring of the decommissioning site of Creys-Malville are presented here. Data highlight the very weak influence of gaseous discharges during all the operating phases and the decommissioning of the facility. Since the beginning (1985) to the end of plant operation (1998), tritium detected in the terrestrial environment near the Creys-Malville site (some Bq.L{sup -1} to a few tens of Bq.L{sup -1}) is almost exclusively linked to the global fall-out of nuclear bomb tests. During decommissioning operations, most of the observed environmental values remain very close to the ambient levels measured in zones not influenced by radioactive releases from nuclear activities i.e. 1 to 10 Bq.L{sup -1} (depending on the nature of the samples analyzed). In connection with the specific decommissioning operations, a slight influence of discharges had been briefly observed in the terrestrial environment; the measured concentrations were from 1 to 18 Bq.L{sup -1} for free water tritium, and from 1 to 11 Bq.L{sup -1} for organically bound tritium. (authors)

  10. Decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Vollradt, J.

    1977-01-01

    A survey of the main questions of decommissioning of nuclear power plants will be given in the sight of German utilities (VDEW-Working group 'Stillegung'). The main topics are: 1) Definitions of decommissioning, entombment, removal and combinations of such alternatives; 2) Radioactive inventory (build up and decay); 3) Experience up to now; 4) Possibilities to dismantle are given by possibility to repair nuclear power plants; 5) Estimated costs, waste, occupational radiation dose; 6) German concept of decommissioning. (orig./HK) [de

  11. Waste management facility remediation and decommissioning at a national nuclear research site

    International Nuclear Information System (INIS)

    Cameron, D.J.; Dolinar, G.M.; Killey, R.W.D.

    1994-01-01

    Historic waste management practices at eight locations on AECL's Chalk River site have resulted in the formation of contaminated groundwater plumes, some of which have surfaced and contaminated surface materials. A priority setting process has been used to establish a plan of attack that will lead to the eventual decommissioning of these facilities. In general terms, the preferred approach is to install impermeable covers to prevent further leaching of waste sources and to prevent escape of leachate to the biosphere, followed by cleanup of surface contamination and remediation of aquifers. Final disposal of the waste sources would be delayed for perhaps 20 years. Substantial progress has been made in the treatment of contaminated groundwater, with one field installation in place and another under development. This paper describes how the prioritization task was tackled to produce a long term plan of action and describes initial interventions that have been attempted and their results. 4 refs., 3 tabs., 3 figs

  12. Stakeholder issues and involvement in decommissioning nuclear facilities. Lessons learnt from WPDD and FSC activities and documentation

    International Nuclear Information System (INIS)

    Pescatore, Claudio; Vari, Anna; Mays, C.; O'Sullivan, P.

    2007-01-01

    The expectation that significant numbers of nuclear power plants will reach the end of their operating lives in the coming decade or so, or will be shut down for economic or other reasons, is resulting in increasing emphasis being given in member countries to the involvement of stakeholders in the associated decision procedures. Although the need for public involvement during the siting process for a new nuclear facility is well established - given the potential for community disruption in terms of population changes and construction nuisance - the role of stakeholders during the shutdown and decommissioning phases is perhaps less well understood. The decision to shut down a nuclear facility before the end of its design lifetime is usually taken for economic, safety or political reasons. In general, there is no requirement in legislation to involve stakeholders directly in this decision; though there can be substantial consequences for local communities in terms of decreasing employment rate and an eventual reduction of revenues for the host municipality. On the other hand, stakeholders do generally have the legal right to be involved in the consequential decision about the strategy for decommissioning the shutdown plant - i.e. the actions taken to facilitate the end of regulatory oversight of the facility - typically through participation in an environmental impact assessment process. In this document, the arguments advanced in favour of stakeholder involvement, and the fostering of relationships with affected communities that are based on trust, are generally applicable to both the above decisions. Although those likely to be most affected by a decision to shut down a nuclear facility are those living nearby, it needs to be remembered that such decisions will sometimes have wider consequences, perhaps even at a national level, e.g. in the event that alternative sources of electricity need to be found to replace that from the shutdown plant. In these situations

  13. Decommissioning of surface facilities associated with repositories for the deep geological disposal of high-level nuclear wastes

    International Nuclear Information System (INIS)

    Heckman, R.A.

    1978-11-01

    A methodology is presented in this paper to evaluate the decommissioning of the surface facilities associated with repositories for the deep geological disposal of high-level nuclear wastes. A cost/risk index (figure of merit), expressed as $/manrem, is proposed as an evaluation criteria. On the basis of this cost/risk index, we gain insight into the advisability of adapting certain decontamination design options into the original facility. Three modes are considered: protective storage, entombment, and dismantlement. Cost estimates are made for the direct labor involved in each of the alternative modes for a baseline design case. Similarly, occupational radiation exposures are estimated, with a larger degree of uncertainty, for each of the modes. Combination of these estimates produces the cost/risk index. To illustrate the methodology, an example using a preliminary baseline repository design is discussed

  14. The calculation and estimation of wastes generated by decommissioning of nuclear facilities. Tokai works and Ningyo-toge Environmental Engineering Center

    International Nuclear Information System (INIS)

    Ayame, Y.; Tanabe, T.; Takahashi, K.; Takeda, S.

    2001-07-01

    This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decommissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decommissioning of the nuclear facilities are as follows. (1) Tokai works: The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2) Ningyo-toge Environmental Engineering Center: The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton. (author)

  15. DECOMMISSIONING OF SHIELDED FACILITIES AT WINFRITH USED FOR POST IRRADIATION EXAMINATION OF NUCLEAR FUELS and OTHER ACTIVE ITEMS

    International Nuclear Information System (INIS)

    Miller, K.D.; Parkinson, S.J.; Cornell, R.M.; Staples, A.T.

    2003-01-01

    This paper describes the approaches used in the clearing, cleaning, decontamination and decommissioning of a very large suite of seven concrete shielded caves and other facilities used by UKAEA at Winfrith Technology Centre, England over a period of about 30 years for the postirradiation examination (PIE) of a wide range of nuclear fuels and other very active components. The basic construction of the facilities will first be described, setting the scene for the major challenges that 1970s' thinking posed for decommissioning engineers. The tendency then to use large and heavy items of equipment supported upon massive steel bench structures produced a series of major problems that had to be overcome. The means of solving these problems by utilization of relatively simple and inexpensive equipment will be described. Later, a further set of challenges was experienced to decontaminate the interior surfaces to allow man entries to be undertaken at acceptable dose rates. The paper will describe the types of tooling used and the range of complementary techniques that were employed to steadily reduce the dose rates down to acceptable levels. Some explanations will also be given for the creation of realistic dose budgets and the methods of recording and continuously assessing the progress against these budgets throughout the project. Some final considerations are given to the commercial approaches to be adopted throughout this major project by the decommissioning engineers. Particular emphasis will be given to the selection of equipment and techniques that are effective so that the whole process can be carried out in a cost-effective and timely manner. The paper also provides brief complementary information obtained during the decommissioning of a plutonium-contaminated facility used for a range of semi-experimental purposes in the late 1970s. The main objective here was to remove the alpha contamination in such a manner that the volume of Plutonium Contaminated Materials (P

  16. The management of financial resources intended for radioactive waste and decommissioning of the nuclear facilities in the european union

    International Nuclear Information System (INIS)

    Tatar, F.; Dima, A.; Glodeanu, F.; Miller, B.; Mosmonea, R.

    2015-01-01

    The European Commission has developed policies and made recommendations on how financial resources should be established and managed by Member States for the purpose of radioactive waste management. The manner in which these recommendations have been accepted, and are applied, varies between European countries. To some extent, this variation reflects the maturity of the nuclear programs in each country and whether or not nuclear facilities are largely state or privately owned and operated. This paper reviews the European Commission.s policy on financial resourcing for radioactive waste management and decommissioning and evaluates how financial resources are practically established and managed by Member States. The findings from the review are then used to benchmark the situation in Romania. (authors)

  17. IAEA Assistance on Decommissioning of Small Facilities with Limited Resources

    International Nuclear Information System (INIS)

    Batandjieva, B.; Warnecke, E.

    2008-01-01

    The number of facilities reaching their lifetime is increasing and drawing the attention of operators, regulators, public and other interested parties (potential users of the site after decommissioning) on the importance of adequate planning, funding and implementation of decommissioning activities in compliance with regulatory requirements and criteria. Specific attention is required for small facilities that have been used for research purposes and in most cases state owned by and dependent on state funding. With the current tendency for expansion of the nuclear industry such small facilities could become less of importance for the operators which can increase the probability that these facilities become abandoned, hazardous and imposing undue burden to future generations. This concern is more related to countries with limited human and financial resources at the operating organizations and the regulatory body. The International Atomic Energy Agency (IAEA) has been working on the; (i) establishment of internationally recognized safety standards on decommissioning and (ii) providing Member States with assistance on the application of these standards. The recent international conference on Lessons Learned from the Decommissioning of Nuclear Facilities and the Safe Termination of Practices (Athens, Greece, 2006) has demonstrated that the set of IAEA standards is almost complete and that the International Action Plan on Decommissioning (2004), that is addressing decommissioning of small facilities, is being successfully implemented. However the need for further assistance on decommissioning of small facilities in countries with limited resources was also recognized and the Agency is planning its future work in this field. The IAEA also addresses the needs of small nuclear countries that have only a limited number of nuclear facilities, e.g. a research reactor, in its R esearch Reactor Decommissioning Demonstration Project (R 2 D 2 P. The Philippine Research Reactor

  18. Planning, Management and Organizational Aspects of the Decommissioning of Nuclear Facilities in Bangladesh

    Energy Technology Data Exchange (ETDEWEB)

    Mollah, A. S.; Begum, A.; Pal, D. [Bangladesh Atomic Energy Commission Agargaon, Dhaka (Bangladesh)

    2013-08-15

    This report summarizes the main results obtained by the Bangladesh Atomic Energy Commission in the decommissioning of spent {sup 60}Co gamma irradiator at GammaTech Limited, Chittagong, and preparation of decommissioning plan of the 3 MW TRIGA Mark-II research reactor in Bangladesh. (author)

  19. The Preliminary Decommissioning Plan of the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lam, Pham Van; Vien, Luong Ba; Vinh, Le Vinh; Nghiem, Huynh Ton; Tuan, Nguyen Minh; Phuong, Pham Hoai [Nuclear Research Institute, Da Lat (Viet Nam)

    2013-08-15

    Recently, after 25 years of operation, a preliminary decommissioning plan for the Dalat Nuclear Research Reactor (DNRR) has been produced but as yet it has not been implemented due to the continued operations of the reactor. However, from the early phases of facility design and construction and during operation, the aspects that facilitate decommissioning process have been considered. This paper outlines the DNRR general description, the organization that manages the facility, the decommissioning strategy and associated project management, and the expected decommissioning activities. The paper also considers associated cost and funding, safety and environmental issues and waste management aspects amongst other considerations associated with decommissioning a nuclear research reactor. (author)

  20. Decommissioning of nuclear power stations

    International Nuclear Information System (INIS)

    Gregory, A.R.

    1988-01-01

    In the United Kingdom the Electricity Boards, the United Kingdom Atomic Energy Authority (UKAEA) and BNFL cooperate on all matters relating to the decommissioning of nuclear plant. The Central Electricity Generating Board's (CEGB) policy endorses the continuing need for nuclear power, the principle of reusing existing sites where possible and the building up of sufficient funds during the operating life of a nuclear power station to meet the cost of its complete clearance in the future. The safety of the plant is the responsibility of the licensee even in the decommissioning phase. The CEGB has carried out decommissioning studies on Magnox stations in general and Bradwell and Berkeley in particular. It has also been involved in the UKAEA Windscale AGR decommissioning programme. The options as to which stage to decommission to are considered. Methods, costs and waste management are also considered. (U.K.)

  1. Abrasive-waterjet cutting of thick concrete and waterjet cleaning for nuclear facility decommissioning and decontamination

    International Nuclear Information System (INIS)

    Echert, D.C.; Hashish, M.; Marvin, M.H.

    1987-01-01

    Two tools have been developed for use by the nuclear industry: the Deep Kerf tool and the Cleaner/Scarifier tool. The Deep Kerf tool is designed to cut through thick, reinforced concrete structures to facilitate their decommissioning. It employs the abrasive-waterjet (AWJ) cutting technology. The basis of the system is a rotary nozzle that makes a slot in the concrete wide enough to accommodate the cutting tool as it advances. In this program, concrete as thick as 1.5 m was cut through from one side. A shroud and vacuum system covers the opening of the slot during cutting to contain the spoils with greater than 99% efficiency. The Cleaner/Scarifier tool was designed for removing the surface layers of contaminated concrete and decontaminating metal surfaces. It uses ultrahigh-pressure waterjets mounted on a rotating arm to remove or clean the target surface. Spoils recovery with a shroud and vacuum system is over 99% complete for both horizontal and vertical surfaces

  2. Parameters of Dismantling Techniques Related to Costs for Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    Jeong, Kwanseong; Moon, Jeikwon; Choi, Byungseon

    2012-01-01

    Reliable cost estimating is one of the most important elements of decommissioning operation. Reliable cost estimating is one of the most important elements of decommissioning planning. Alternative technologies may be evaluated and compared on their efficiency and effectiveness, and measured against a baseline cost as to the feasibility and benefit derived from the technology. This principle ensures that the cost consideration is economically sound and practical for funding. This paper provides a list with basic review of cutting and dismantling techniques, including some typical characteristics if available, as well as aspects of implementation, parameters of cutting and dismantling techniques in decommissioning costing. This paper gives an overview of the principles of the unit factor approach and its implementation in costing in relation to dismantling activities. In general, proper evaluation of decommissioning costs is important for following issues and relevant measures for achieving the listed aspects are: · Selection of a decommissioning strategy and activities: several decommissioning options should be evaluated: · Support to a cost-benefit analysis to ensure that the principle of optimization and reasonably practicable measures are applied: the extent of evaluated decommissioning options should cover all possible scenarios for dismantling activities; · Estimate of required financial resources for the selected strategy: the selected option should involve the dismantling activities in a structure and extent relevant to real procedure of dismantling activities; · Preparation of the project schedule, workforce requirements and phased funding needs: dismantling activities should be structured according to the tasks of the decommissioning schedule; · Definition of measures for proper management and maintenance of resources for safe and timely decommissioning: the time distribution and safety related parameters of dismantling activities should be known

  3. Summary, analysis, and response to public comments on proposed amendments to 10 CFR Parts 30, 40, 50, 51, 70, and 72: Decommissioning criteria for nuclear facilities

    International Nuclear Information System (INIS)

    1988-06-01

    On February 11, 1985, the NRC issued for public comment proposed rules on decommissioning of nuclear facilities (50 FR 5600). Comment letters were received from 143 organizations and individuals. This report provides a summary and analysis and response to the public comments received

  4. Decommissioning of the nuclear facilities at Risø National Laboratory. Descriptions and cost assessment

    DEFF Research Database (Denmark)

    Lauridsen, K.

    2001-01-01

    and the costs incurred. Three decommissioning scenarios were considered with decay times of 10, 25 and 40 years for the DR 3 reactor. The assessments conclude, however, that there will not be much to gain by allowing forthe longer decay periods; some operations still will need to be performed remotely....... Furthermore, the report describes some of the legal and licensing framework for the decommissioning and gives an assessment of the amounts of radioactive waste to betransferred to a Danish repository. For a revision of the cost estimate for the decommissioning of the research Reactor DR 3 please consult...

  5. The estimation of the amount of radioactive waste from decommissioning of the nuclear facilities in Oarai Engineering Center

    International Nuclear Information System (INIS)

    Tanimoto, Kenichi; Aihara, Nagafumi; Imai, Katutomo; Tobita, Kazunori; Nemoto, Masaaki; Imahori, Shinji; Noguchi, Kouichi; Hasegawa, Makoto

    1998-11-01

    The estimation of the amount of radioactive waste produced from nuclear facilities in Oarai Engineering Center was performed for the purpose of using it for countermeasure of decommissioning planning. The conditions and the result of the estimation are as follows; (1) The total amount of occurrence of radioactive waste is 18,820 tons. As the items of the amount in radioactive level, the amount of 1 GBq/t and over is 820 tons and that of under 1 GBq/t is 18,000 tons. (2) The amount of metal waste is 5,820 tons and the amount of concrete is 13,000 tons. (3) Above calculation was based on related specifications, complete drawings, and visual observation. (4) To dismantle facilities, if must exfoliate the surface of wall. As for the polluted zone and the zone with possibility of pollution, it decided to exfoliate 5 cm in thickness from the surface of the wall. And, as for the zone that fundamentally pollution was not there, it decided to exfoliate surface 1 cm in thickness from the surface of the wall. (5) Using the suitable decontamination technology and exfoliation technology can reduce the amount of radioactive waste. (6) In the facilities dealing with sealed source judging from the past record of operation, there is no contact with the radioactive material, etc. Therefore, it can be disposed of all the waste that comes out from the facilities as non-radioactive waste. (author)

  6. International Good Practice on Practical Implementation of Characterisation in Decommissioning. Radiological Characterization in Decommissioning of Nuclear Facilities: International Good Practice on Practical Implementation

    International Nuclear Information System (INIS)

    Larsson, A.; Empdage, M.; Weber, I.; )

    2017-01-01

    Within the Nuclear Energy Agency (NEA), the Working Party on Decommissioning and Dismantling (WPDD) operates under the umbrella of the Radioactive Waste Management Committee (RWMC). The WPDD provides a focus for the analysis of decommissioning policy, strategy and regulation, including the related issues of waste management, release of buildings and sites from regulatory control and associated cost estimation and funding. WPDD also convenes task groups comprised of experts from the NEA member countries to review related topics such as characterisation techniques which support decommissioning and associated waste management. The Task Group on Radiological Characterisation and Decommissioning was established in 2011 to identify and present characterisation good practice at different stages of decommissioning and to identify areas that could, or should, be developed further through international cooperation and coordination. By the end of 2016 two phases of work will be complete. The first phase developed strategic guidance for decision makers on the selection and tailoring of strategies for radiological characterisation, which gives an overview of good practice for radiological characterisation at different phases of the life cycle of a nuclear installation. The second phase has focused on strategies for practical implementation of radiological characterisation from a waste and materials end-state perspective. This paper provides a summary of the phase 2 findings, covering: -) a major international survey (questionnaire) to elicit the views of characterisation experts regarding good practice; -) Learning drawn from recent international case studies; -) The collation and analysis of regulations, standards and guidance documents; -) Learning distilled from an international conference on characterisation co-organised by the task group; and -) Overall conclusions regarding characterisation good practice, recommendations and identified areas for further international

  7. Decommissioning high-level waste surface facilities

    International Nuclear Information System (INIS)

    1978-04-01

    The protective storage, entombment and dismantlement options of decommissioning a High-Level Waste Surface Facility (HLWSF) was investigated. A reference conceptual design for the facility was developed based on the designs of similar facilities. State-of-the-art decommissioning technologies were identified. Program plans and cost estimates for decommissioning the reference conceptual designs were developed. Good engineering design concepts were on the basis of this work identified

  8. Decommissioning of nuclear facilities: COGEMA expertise devoted to UP1 reprocessing plant dismantling programme

    International Nuclear Information System (INIS)

    Gay, A.

    2001-01-01

    Over the last past decades, the French nuclear industry has acquired a great experience and know-how in the field of dismantling. Today this experience amounts to more than 200,000 hours. The fundamental aims within dismantling strategy are the same as for all nuclear facilities: minimising doses received by workers, minimising waste volume and adapting waste management to radioactivity levels, minimising costs. French experience is based on technologies which are currently used in nuclear maintenance facilities. Dismantling is a dynamic process especially in the field of decontamination (chemical and mechanical), cleaning, robotics and remote control operations. The strategy for the dismantling of former UP1 reprocessing plant is based on the feedback of experience gained through the dismantling of other facilities such as the AT1 workshop at La Hague. This workshop, a pilot plant for reprocessing of fast-breeder reactor fuels (Rapsodie and Phenix) has to be dismantled to IAEA level 3 (unrestricted site use), excluding civil works structures. Currently conducted by trained shifts, this dismantling project should end in 1999. The experience already acquired proves that chemical rinsings with the use of specific reagents is sufficient to decontaminate the hot cells and that the use of remote operations or robotics is not as important as previously envisaged. The UP1 reprocessing plant of Marcoule operated from 1958 to 1997. End of the operation was pronounced on the 31st of December 1997. 20,000 tons of spent fuels were reprocessed at UP1. The cleaning and dismantling operations at the Marcoule site depend upon the CEA, EDF and COGEMA. The Defence and Industry Ministries asked for a specific structure to be set up. An economic interest group called CODEM was created in May 1996. CODEM decides, finances and supervises dismantling operations, while respecting the constraints of nuclear safety, environmental protection and cost-effectiveness. The cleaning operations of

  9. Development of the international Chornobyl center in Slavutych its role in nuclear facilities decommissioning

    International Nuclear Information System (INIS)

    Nosovskij, A.

    2002-01-01

    ChNPP site should be actively used for development and realizing the efforts on RBMK reactors decommissioning technologies, as well as Unit 'Shelter' transformation into ecologically safe system. Those technologies and methods will be required in future both in Ukraine and abroad. So, it is wise to employ another direction of ChNPP site utilization as a polygon for development and implementing new technologies associated with decommissioning. Besides, it could be used for exercising the methods and technologies of large-scale man-caused accidents elimination

  10. Background as a residual radioactivity criterion for decommissioning: Appendix A to the Generic Environmental Impact Statement in support of rulemaking on radiological criteria for decommissioning of NRC-licensed nuclear facilities. Draft report

    International Nuclear Information System (INIS)

    Huffert, A.M.; Meck, R.A.; Miller, K.M.

    1994-08-01

    This report was originally published as an appendix to the draft U.S. Nuclear Regulatory Commission (NRC) document entitled, open-quotes Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for Decommissioning of NRC-Licensed Nuclear Facilities.close quotes Because of the great interest in this report by members of the public, citizen and environmental organizations, academicians, licensees, and regulators, the NRC staff is publishing this report separately, so that it can be readily available to a diverse audience. This report was created to assist both the NRC staff and interested members of the public in evaluating background radiation (background) as a decommissioning criterion, by serving as a primer on background and providing information on the existing applications of background in regulatory criteria and standards. This report also discusses some of the methods available to measure and distinguish between the very low radiation levels associated with background and man-made sources of radiation. Two approaches are considered for applying background as a decommissioning criterion; these are the use of background dose rates and background radionuclide concentrations. This report concludes that the temporal and spatial variability of background produces a wide range of doses to United States residents, which prevents the application of background dose rates as a decommissioning criterion. Instead, this report recommends that local background radionuclide concentrations serve as a benchmark for decommissioning criteria, while taking into account the concept of reducing residual radioactivity to a level as low as is reasonably achievable

  11. Nuclear data in the problem of fission reactor decommissioning

    International Nuclear Information System (INIS)

    Manokhin, V.N.; Kulagin, N.T.

    1993-01-01

    This report presents a review of the works published in Russia during last several years and devoted to the problem of nuclear data and calculations of nuclear facilities activation for fission reactor decommissioning. 6 refs

  12. Role of the statistician in the decommissioning of the New Brunswick Laboratory and other nuclear facilities

    International Nuclear Information System (INIS)

    Gilbert, R.O.

    1980-12-01

    This report examines what the statistician can contribute to decommissioning operations, with particular emphasis on the New Brunswick Laboratory (NBL) currently scheduled for decommissioning beginning in FY81. In the opinion of the author, a professional statistician should be a full member of the planning team directing decommissioning operations at the New Brunswick Laboratory. This opinion is based in part on the familiarity with the valuable contributions made by statisticians toward the cleanup of transuranics in soil on the Enewetak Atoll. More generally, however, the professional statistician can help plan the decommissioning effort to help ensure that representative data are obtained, analyzed and, interpreted in appropriate ways so that RA decisions can be made with the required confidence. The statistician's contributions at the NBL could include providing guidance on the number and location of samples and in-situ measurements, analyzing and interpreting these data, designing a data management and documentation system, interfacing with the certification contractor's statistician, and assisting in writing documentation and final reports. In all cases, the statistician should work closely with the professional health physicist and others on the planning team in a closely coordinated effort of planning and data analysis

  13. The study of the container types used for transport and final disposal of the radioactive wastes resulting from decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Postelnicu, C.

    1998-01-01

    The purpose of the present paper is to select from a variety of package forms and capacities some containers which will be used for transport and disposal of the radioactive wastes resulting from decommissioning of nuclear facilities into the National Repository for Radioactive Waste - Baita, Bihor county. Taken into account the possibilities of railway and / or road transport and waste disposal in our country, detailed container classification was given in order to use them for radioactive waste transport and final disposal from decommissioning of IFIN-HH Research Reactor. (author)

  14. Needs for R and D and innovations to address challenges of nuclear facility decommissioning after its normal shutdown versus advanced approaches required for Fukushima Daiichi NPS decommissioning. Needs and emergency technologies for decommissioning

    International Nuclear Information System (INIS)

    Laurent, G.

    2017-01-01

    Taking into account several attempts to address variety of needs for R and D related to the decommissioning challenges such as: - Characterisation and survey prior to dismantling, - Technologies for dismantling, - Decontamination and on-site remediation, - Material and waste management, - Site characterisation and environmental monitoring. This presentation will give an update of approaches in several countries for R and D to aim at more efficient and effective decommissioning and, above all, to reduce current labour intensive needs to implement this kind of work. The evidence of the particular needs to coordinate efforts both for 'normal decommissioning' and accident cases like Fukushima Daiichi will be offered by demonstrating that, for a large part, that needs might be considered as similar. Some examples of particular interest will be given and it will be emphasized the need to adapt existing and/or new technologies from 'non-nuclear' areas to use them for nuclear decommissioning. The global interest to evaluate and to coordinate R and D efforts will be demonstrated. Consequently there might be a large international interest to increase the consensus where R and D can be better directed. The more comprehensive coordination should support improvement of the overview of future decommissioning needs to implement the decommissioning activities more effectively in terms of time and finance, not compromising safety. (author)

  15. Requirement Management between Regulatory Framework and Dismantling Activities for Decommissioning of a Nuclear Facility

    International Nuclear Information System (INIS)

    Park, H.S.; Jin, H.G.; Hong, Y.J.; Choi, J.W.; Park, S.

    2016-01-01

    Full text: The decommissioning and environmental remediation (D&ER) projects require stepwise long-term research and development (R&D) such as a shutdown, transition, decontamination and decommissioning (D&D) activities, radioactive waste management, and site restoration. During each step of the D&ER projects, a significant amount of information and knowledge such as experimental data, databases, design drawings, technical reports, guidelines, operation manuals, and modeling and simulation reports are produced. Knowledge based on experiences by staff members participating in each step of the D&ER project are also very important. Such knowledge based on experiences may disappear with the retirement of staff members if there are no effective and systematic approaches for its acquisition and storage. Therefore, to perform the D&ER project successfully, it is necessary to preserve written theses and experiences systematically. The integrated knowledge management system (KMS) for the D&ER projects have never been developed. Therefore, the establishment of an integrated KMS is necessary for the effective performance of D&ER projects. This study introduces a decommissioning procedure requirement management system as a part of the KMS related to the D&ER projects. (author

  16. Lessons learned from the decommissioning of NORM facility in Malaysia

    International Nuclear Information System (INIS)

    Kontol, Khairuddin M.; Omar, Muhamat; Ahmad, Syed H.S.S.

    2008-01-01

    Full text: Malaysia Decommissioning of Naturally Occurring Radioactive Materials (NORM) facility in Malaysia will run into unforeseeable complications and difficulties if there is no proper planning. The Atomic Energy Licensing Board (AELB) plays important role in guiding and assisting the operator/contractor in this NORM decommissioning project. A local Naturally Occurring Radioactive Materials (NORM) processing plant located in the northern region of peninsular Malaysia had ceased its operations and decided to decommission and remediate its site for the final release of the site. The remediated site is earmarked as an industrial site. During its operations, monazites are processed for rare earth elements such as cerium and lanthanum. It's plant capable of processing monazite to produce rare earth chloride and rare earth carbonate. The main by-product of monazite processing is the radioactive cake containing primarily thorium hydroxide. Operation of the monazite processing plant started in early eighties and terminated in early nineties. The decommissioning of the plant site started in late 2003 and completed its decommissioning and remediation works in early 2006. This paper described the lesson learned by Malaysian Nuclear Agency (Nuclear Malaysia) in conducting third party independent audit for the decommissioning of the NORM contaminated facility. By continuously reviewing the lessons learned, mistakes and/or inefficiencies in this plant decommissioning project, hopefully will result in a smoother, less costly and more productive future decommissioning works on NORM facilities in Malaysia. (author)

  17. Uranium Determination in Samples from Decommissioning of Nuclear facilities Related to the First Stage of Nuclear Fuel Cycle; Determinacion de Uranio en Muestras Procedentes del Desmantelamiento de Instalaciones de la Primera Parte del Cielo del Combustible Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Alvarez, A; Correa, E; Navarro, N; Sancho, C [Ciemat, Madrid (Spain); Angeles, A

    2000-07-01

    An adequate workplace monitoring must be carried out during the decommissioning activities, to ensure the protection of workers involved in these tasks. In addition, a large amount of waste materials are generated during the decommissioning of nuclear facilities. Clearance levels are established by regulatory authorities and are normally quite low. The determination of those activity concentration levels become more difficult when it is necessary to quantify alpha emitters such as uranium, especially when complex matrices are involved. Several methods for uranium determination in samples obtained during the decommissioning of a facility related to the first stage of the nuclear fuel cycle are presented in this work. Measurements were carried out by laboratory techniques. In situ gamma spectrometry was also used to perform measurements on site. A comparison among the different techniques was also done by analysing the results obtained in some practical applications. (Author)

  18. Stimulation of innovation in the course of decommissioning and dismantling of nuclear facilities

    International Nuclear Information System (INIS)

    Bach, F.W.

    1996-01-01

    For the last 30 years, national and international projects have been performed for development and testing of dismantling and cutting technology, covering theoretical experiments as well as laboratory work and applications in pilot projects. An aspect of major interest of the scientific and technical studies was the adjustment of conventional thermal, mechanical, hydraulic and (electro)chemical cutting processes to the specific requirements posed by nuclear facilities. At first sight, one would not expect much innovative potential in the field of cutting technology alone, except for, perhaps, process optimizations such as extensions of dwell times or process stability. However, the intelligent application of available cutting techniques and tools or instruments, leading in their proper combinations to novel techniques and experience, is an interesting challenge to scientists and engineers and hold a wide range of innovative potential. The paper presents some cutting techniques of particular interest in this context. (orig./DG)

  19. Methods for the minimization of radioactive waste from decontamination and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    2001-01-01

    The objective of this report is to provide Member States and their decision makers (ranging from regulators, strategists, planners and designers, to operators) with relevant information on opportunities for minimizing radioactive wastes arising from the D and D of nuclear facilities. This will allow waste minimization options to be properly planned and assessed as part of national, site and plant waste management policies. This objective will be achieved by: reviewing the sources and characteristics of radioactive materials arising from D and D activities; reviewing waste minimization principles and current practical applications, together with regulatory, technical, financial and political factors influencing waste minimization practices; and reviewing current trends in improving waste minimization practices during D and D

  20. Interim Storage Facility decommissioning. Final report

    International Nuclear Information System (INIS)

    Johnson, R.P.; Speed, D.L.

    1985-01-01

    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

  1. Demonstration of safety of decommissioning of facilities using radioactive material

    International Nuclear Information System (INIS)

    Batandjieva, Borislava; O'Donnell, Patricio

    2008-01-01

    Full text:The development of nuclear industry worldwide in the recent years has particular impact on the approach of operators, regulators and interested parties to the implementation of the final phases (decommissioning) of all facilities that use radioactive material (from nuclear power plants, fuel fabrication facilities, research reactors to small research or medical laboratories). Decommissioning is becoming an increasingly important activity for two main reasons - termination of the practice in a safe manner with the view to use the facility or the site for other purposes, or termination of the practice and reuse the facility or site for new built nuclear facilities. The latter is of special relevance to multi-facility sites where for example new nuclear power plants and envisaged. However, limited countries have the adequate legal and regulatory framework, and experience necessary for decommissioning. In order to respond to this challenge of the nuclear industry and assist Member States in the adequate planning, conduct and termination of decommissioning of wide range of facilities, over the last decade the IAEA has implemented and initiated several projects in this field. One of the main focuses of this assistance to operators, regulators and specialists involved in decommissioning is the evaluation and demonstration of safety of decommissioning. This importance of these Agency activities was also highlighted in the International Action Plan on Decommissioning, during the second Joint Convention meeting in 2006 and the International Conference on Lessons Learned from Decommissioning in Athens in 2006. The IAEA has been providing technical support to its Member States in this field through several mechanisms: (1) the establishment of a framework of safety standards on decommissioning and development of a supporting technical documents; (2) the establishment of an international peer review mechanism for decommissioning; (3) the technical cooperation projects

  2. Application of Regulation for recycling metals arising from Decommissioning of an Italian Nuclear Facility - Application of national regulations for metallic materials' recycling from the decommissioning of an Italian nuclear facility

    International Nuclear Information System (INIS)

    Varasano, Giovanni; Baldassarre, Leonardo; Petagna, Edoardo

    2014-01-01

    The start of the decommissioning of nuclear Italian sites requires proper management of clearance for large volumes of metallic materials. This paper describes the current legal framework relating to the Italian regulatory system of reference for the verification of the conditions of unconditional release of materials from nuclear installations, with particular reference to the recycling of metals. The definition of clearance levels, whether general or specific, ensures the clearance of materials arising from nuclear sites without further examinations. The Italian legislation on radiation protection requires that the removal of materials from authorized practices be subject to special requirements included in the authorization provisions. These requirements provide clearance levels that take account of the recommendations and technical guidelines supplied by the European Commission. The regulatory framework requires compliance with current technical and managerial requirements, issued by the National Regulatory Authority and annexed to the Ministerial Authorization, in which are shown the levels of surface activity and specific activity established for the unconditional release of metals from nuclear sites. The real challenge for the nuclear operator is the management of large amounts of waste materials arising from decommissioning activities. For the Italian operator SOGIN SpA is of extreme importance the correct application of national regulatory framework, in order to allow the most effective reduction of the amount of radioactive waste during decommissioning activities. (authors)

  3. Dismantlement of nuclear facilities decommissioned from the Russian navy: Enhancing regulatory supervision of nuclear and radiation safety

    International Nuclear Information System (INIS)

    Sneve, M.K.

    2013-01-01

    The availability of up to date regulatory norms and standards for nuclear and radiation safety, relevant to the management of nuclear legacy situations, combined with effective and efficient regulatory procedures for licensing and monitoring compliance, are considered to be extremely important. Accordingly the NRPA has set up regulatory cooperation programs with corresponding authorities in the Russian Federation. Cooperation began with the civilian regulatory authorities and was more recently extended to include the military authority and this joint cooperation supposed to develop the regulatory documents to improve supervision over nuclear and radiation safety while managing the nuclear military legacy facilities in Northwest Russia and other regions of the country. (Author)

  4. Dismantlement of nuclear facilities decommissioned from the Russian navy: Enhancing regulatory supervision of nuclear and radiation safety

    Energy Technology Data Exchange (ETDEWEB)

    Sneve, M.K.

    2013-03-01

    The availability of up to date regulatory norms and standards for nuclear and radiation safety, relevant to the management of nuclear legacy situations, combined with effective and efficient regulatory procedures for licensing and monitoring compliance, are considered to be extremely important. Accordingly the NRPA has set up regulatory cooperation programs with corresponding authorities in the Russian Federation. Cooperation began with the civilian regulatory authorities and was more recently extended to include the military authority and this joint cooperation supposed to develop the regulatory documents to improve supervision over nuclear and radiation safety while managing the nuclear military legacy facilities in Northwest Russia and other regions of the country. (Author)

  5. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 18. Part 1B: Citations with abstracts, sections 10 through 16

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This bibliography contains 3,638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D and D), uranium mill tailings management, and site remedial actions. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration Program; (2) DOE D and D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized sites Remedial Action Program; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluation; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues.

  6. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 18. Part 1A: Citations with abstracts, sections 1 through 9

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    This bibliography contains 3,638 citations with abstracts of documents relevant to environmental restoration, nuclear facility decontamination and decommissioning (D and D), uranium mill tailings management, and site remedial actions. The bibliography contains scientific, technical, financial, and regulatory information that pertains to DOE environmental restoration programs. The citations are separated by topic into 16 sections, including (1) DOE Environmental Restoration program; (2) DOE D and D Program; (3) Nuclear Facilities Decommissioning; (4) DOE Formerly Utilized Sites Remedial Action Program; (5) NORM-Contaminated Site Restoration; (6) DOE Uranium Mill Tailings Remedial Action Project; (7) Uranium Mill Tailings Management; (8) DOE Site-Wide Remedial Actions; (9) DOE Onsite Remedial Action Projects; (10) Contaminated Site Remedial Actions; (11) DOE Underground Storage Tank Remediation; (12) DOE Technology Development, Demonstration, and Evaluation; (13) Soil Remediation; (14) Groundwater Remediation; (15) Environmental Measurements, Analysis, and Decision-Making; and (16) Environmental Management Issues.

  7. The safety assessment system based on virtual networked environment for evaluation on the hazards from human errors during decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Jeong, Kwan Seong; Choi, Byung Seon; Moon, Jei Kwon; Hyun, Dong Jun; Lee, Jong Hwan; Kim, Ik June; Kang, Shin Young; Choi, Jong Won; Ahn, Sang Myeon; Lee, Jung Jun; Lee, Byung Sik

    2016-01-01

    This paper is intended to suggest a system for evaluation on the hazards from human errors during decommissioning of nuclear facilities. The system was developed under virtual networked environment. The innovative features are real-time changing direction of workers in a scenario and real-time measuring personal exposure dose and collective exposure dose. The system will be expected to be utilized as a training tool for improving familiarization of a workplace and for preventing workers from accidents. - Highlights: • A system for evaluation on the hazards from human errors during decommissioning of nuclear facilities. • Real-time changing direction of workers in a scenario. • Real-time measuring personal exposure dose and collective exposure dose. • A tool for improving familiarization of a workplace and for preventing workers from accidents.

  8. Nuclear facilities

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    Here is given the decree (2000-1065) of the 25. of October 2000 reporting the publication of the convention between the Government of the French Republic and the CERN concerning the safety of the LHC (Large Hadron Collider) and the SPS (Proton Supersynchrotron) facilities, signed in Geneva on July 11, 2000. By this convention, the CERN undertakes to ensure the safety of the LHC and SPS facilities and those of the operations of the LEP decommissioning. The French legislation and regulations on basic nuclear facilities (concerning more particularly the protection against ionizing radiations, the protection of the environment and the safety of facilities) and those which could be decided later on apply to the LHC, SPS and auxiliary facilities. (O.M.)

  9. Research on decommissioning of nuclear facilities 2. Study on optimum scenario using the AHP (Joint research)

    International Nuclear Information System (INIS)

    Shibahara, Yuji; Morishita, Yoshitsugu; Ishigami, Tsutomu; Yanagihara, Satoshi; Arita, Yuji

    2013-01-01

    To implement a decommissioning project reasonably, it is necessary and important to calculate project management data beforehand as well as to select an optimum dismantling scenario among various scenarios postulated. Little study on the subject of selecting an optimum scenario has been carried out, and it is one of the most important issues in terms of decision making. In FY 2009, Japan Atomic Energy Agency and University of Fukui launched the joint research of a decision making method which is important to determine a decommissioning plan. The purpose of this research is to formulate a methodology for selecting an optimum dismantling scenario among various scenarios postulated based on calculated results of project management data for FUGEN. Project management data for several dismantling scenarios postulated at FUGEN were evaluated based on actual dismantling work for feedwater heater at FUGEN, and an optimum scenario was discussed using the AHP, one of Multi-Criteria Decision Analysis Methods. This report describes the results of the joint research in FY 2010. (author)

  10. Study on a new calibration methods of in-situ HPGe γ spectrometers used for non-destructive analyzing radioactivity in nuclear facilities decommissioning

    International Nuclear Information System (INIS)

    Xiao Xuefu; Song Lijun; Wang Yulai; Wen Fuping; Liao Haitao; Ban Ying; Xia Yihua; Li Ruixiang; Li Hang; Tu Xingmin

    2007-06-01

    A new calibration technique, which is the Monte Carlo modeling technique, of in-situ HPGe γ spectrometers used for non-destructive analyzing radioactivity in nuclear facilities decommissioning, is presented. A series of assay for some stainless steel pipes and tanks in some nuclear facilities/laboratories of CIAE are taken on site with the in-situ HPGe γ spectrometer. At the same time, some examples are taken and analyzed in laboratories. The relative bias/variation between the values of activity measured by in-situ HPGe γ spectrometers on site and that analyzed in laboratory is less than ±45.0%. (authors)

  11. Decommissioning Operations at the Cadarache Nuclear Research Center

    International Nuclear Information System (INIS)

    Gouhier, E.

    2008-01-01

    Among the different activities of the CEA research center of Cadarache, located in the south of France, one of the most important involves decommissioning. As old facilities close, decommissioning activity increases. This presentation will give an overview of the existing organization and the different ongoing decommissioning and cleanup operations on the site. We shall also present some of the new facilities under construction the purpose of which is to replace the decommissioned ones. Cadarache research center was created on October 14, 1959. Today, the activities of the research center are shared out among several technological R and D platforms, essentially devoted to nuclear energy (fission and fusion) Acting as a support to these R and D activities, the center of Cadarache has a platform of services which groups the auxiliary services required by the nuclear facilities and those necessary to the management of nuclear materials, waste, nuclear facility releases and decommissioning. Many old facilities have shut down in recent years (replaced by new facilities) and a whole decommissioning program is now underway involving the dismantling of nuclear reactors (Rapsodie, Harmonie), processing facilities (ATUE uranium treatment facility, LECA UO 2 facility) as well as waste treatment and storage facilities (INB37, INB 56. In conclusion: other dismantling and cleanup operations that are now underway in Cadarache include the following: - Waste treatment and storage facilities, - Historical VLLW and HLW storage facility, - Fissile material storage building, - Historical spent fuel storage facility. Thanks to the project organization: - Costs and risks on these projects can be reduced. - Engineers and technicians can easily move from one project to another. In some cases, when a new facility is under construction for the purpose of replacing a decommissioned one, some of the project team can integrate the new facility as members of the operation team. Today

  12. Underwater-manipulation system for measuring- and cutting tasks in dismantling decommissioned nuclear facilities. Final report

    International Nuclear Information System (INIS)

    Stegemann, D.; Reimche, W.; Hansch, M.; Spitzer, M.

    1995-01-01

    Not only manipulators are necessary for dismantling and inspection of structure parts in decomissioned nuclear facilities, but flexible underwater-vehicles. Free-diving underwater-vehicles for inspection and dismantling tasks are still not developed and tested. Aim of the project is the development of sensors and devices for the position determination and the depth regulation. For inspection tasks an ultrasonic measurement and dosimeter device shall be built up. A measurement device has been developed which evaluates the ultrasonic time of flight from a transmitter at the vehicle to several receivers, installed in the reactor pressure vessel. The depth regulation is based on a pressure sensor and the direct control of the thrusters. The ultrasonic measurements are realized by an adapted ultrasonic card, the γ-dosimetry with an ionization chamber and a pA-amplifier. An acoustic orientation system was built up, which measures very accurately with one transmitter mounted on the vehicle and four receivers. Problem occur by reflection from the walls of the basin. The depth regulation is working faultless. The ultrasonic device is preferably used for distance measurement. The radiation measurement device was tested and mounted in the vehicle. (orig./HP) [de

  13. Development of containment system for application to decommissioning of nuclear facilities. 2

    International Nuclear Information System (INIS)

    Mizuno, Oichi; Iwasaki, Yukio; Miyao, Hidehiko; Uchikoshi, Tadaaki; Furuya, Hirotaka; Kamata, Hirofumi

    1998-01-01

    New greenhouse/containment was developed to apply for confining the radioactive materials and preventing the dispersion of radioactive contamination during the maintenance and dismantling of the nuclear facility. The pressed-air tubes for columns and beams of the structure frame were applied and the vinyl chloride sheet reinforced with the polyester fiber was used as a canvas of wall and ceiling. This canvas is possible to use repeatedly and has high efficiency of safe enclosing. The containment can be easily assembled and disassembled by charge and discharge of the pressed air in the tubes of columns and beams. Two standard units (2.5mL x 2.5mW x 2.5mH, 5mL x 5mW x 2.5mH) are prepared, and lateral connection of these standard units makes it applicable to the wide working area. Expansion model up to 5m in height is also available. (author)

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

    International Nuclear Information System (INIS)

    Robinson, I.F.

    1999-01-01

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

  15. Workshop on decommissioning

    International Nuclear Information System (INIS)

    Broden, K.

    2005-12-01

    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)

  16. Decommissioning of the Risoe Hot Cell facility

    International Nuclear Information System (INIS)

    Carlsen, H.

    1991-02-01

    The Hot Cell facility at Risoe has been in active use since 1964. During the years several types of nuclear fuels have been handled and examined: test reactor fuel pins from the Danish reactor DR3, the Norwegian Halden reactor, etc; power reactor fuel pins from several foreign reactors, including plutonium enriched pins; HTGR fuel from the Dragon reactor. All kinds of physical and chemical non-destructive and destructive post irradiation examinations have been performed. Besides, different radiotherapy sources have been produced, mainly cobalt sources. The general object of the decommissioning programme for the Hot Cell facility was to obtain a safe condition for the total building that does not require the special safety provisions. The hot cell building will be usable for other purposes after decommissioning. The facilicy comprised six concrete cells, lead cells, glove boxes, a shielded unit for temporary storage of waste, frogman area, decontamination areas, workshops, various installations of importance for safe operation of the plant, offices, etc. The tasks comprised e.g. removal of all irradiated fuel items, removal of other radioactive items, removal of contaminated equipment, and decontamination of all the cells and rooms. The goal was to decontaminate all the concrete cells to a degree where no loose contamination exists in the cells, and where the radiation level is so low, that total removal of the cell structures can be done at any time in the future without significant dose commitments. (AB)

  17. Safety problems in decommissioning nuclear power plants

    International Nuclear Information System (INIS)

    Auler, I.; Bardtenschlager, R.; Gasch, A.; Majohr, N.

    1975-12-01

    The safety problems at decommissioning are illustrated by the example of a LWR with 1300 MW electric power after 40 years of specified normal operation. For such a facility the radioactivity in the form of activation and contamination one year after being finally taken out of service is in the order of magnitude of 10 7 Ci, not counting the fuel assemblies. The dose rates occurring during work on the reactor vessel at nozzle level may amount to some 10 4 rem/h. After a rough estimation the accumulated dose for the decommissioning personnel during total dismantling will be about 1200 rem. During performance of the decommissioning activities the problems are mainly caused by direct radiation of the active components and systems and by the release of radioactive particles, aerosols and liquids if these components are crushed. The extent of later dismantling problems may be reduced by selecting appropriate materials as well as considering the requirements for dismantling in design and arrangement of the components already in the design stage of new facilities. Apart from plant design also the concept for the disposal of the radioactive waste from decommissioning will provide important boundary conditions. E.g. the maximum size of the pieces to be stored in the ultimate storage place will very much influence the dose expenditure for handling these parts. For complete dismantling of nuclear power plants an ultimate store must be available where large amounts of bulky decommissioning waste, containing relatively low activity, can be stored. The problems and also the cost for decommissioning may be considerably reduced by delaying complete disposal of the radioactive material >= 40 years and during this period, keeping the radioactivity enclosed within the plant in the form of a safe containment. (orig./HP) [de

  18. Safety Oversight of Decommissioning Activities at DOE Nuclear Sites

    International Nuclear Information System (INIS)

    Zull, Lawrence M.; Yeniscavich, William

    2008-01-01

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

  19. Decommissioning of the nuclear licensed facilities at the Fontenay aux Roses CEA center

    International Nuclear Information System (INIS)

    Jeanjacques, Michel; Piketty, Laurence; Letuhaire, Nathalie; Mandard, Lionel; Meden, Igor; Estivie, David; Boissonneau, Jean Francois; Fouquereau, Alain; Pichereau, Eric; Binet, Cedric

    2007-01-01

    Available in abstract form only. Full text of publication follows: The French Atomic Energy Commission (CEA) center at Fontenay aux Roses (CEN-FAR) is the Commission's oldest center is located in the southern suburbs of Paris. It was opened on 26 March 1946 to host the first French nuclear reactor ZOE that went critical on 12 December 1946. The first laboratories were installed in existing buildings on the site. (authors)

  20. Management of toxic waste resulting from decommissioning and environmental remediation of nuclear facilities in Northwest Russia

    International Nuclear Information System (INIS)

    Vysotskij, V.L.; Nikitin, V.S.; Kulikov, K.N.; Ivanov, S.A.; Bogdanova, G.S.; Zakharov, A.A.

    2008-01-01

    Integrated information on toxic wastes formed during utilization and rehabilitation of shutdown naval nuclear object at Northwest Russia is performed. Dynamics of their accumulation to 2025 is estimated. Necessity of present waste management review and search of new methods with the view of decrease of environmental risks by means of systematic reprocessing or economic favorable destruction. Several strategies are treated. Advantages and imperfections of each of them are estimated by safety factors and economic costs, and the most acceptable strategy is selected. Functional model is found. Lists of projects, technical means are given, periods, costs for its realization are evaluated. Guidelines are provided [ru

  1. Technical aspects regarding the management of radioactive waste from decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Dragolici, F.; Turcanu, C.N.; Rotarescu, Gh.; Paunica, I.

    2002-01-01

    The proper application of the nuclear techniques and technologies in Romania started in 1957 with the commissioning of the VVR-S Research Reactor at IFIN-HH-Magurele. During the past 40 years, this reactor was used for thousands of nuclear applications with extremely diverse profiles (research, biology, medicine, education, agriculture, transport, all types of industry) which used radioactive sources in their activity and produced radioactive waste. The Radioactive Waste Treatment Plant (STDR) at IFIN-HH was constructed in collaboration with companies from the United Kingdom and became operational in 1975. It was the only authorized and specialized institution for the management of non-fuel cycle radioactive waste in Romania. Using the concepts existing in the 1980's concerning the final disposal of the low and intermediate level radioactive wastes, and applying internal standards and international recommendations, the National Repository for Low and Intermediate Radioactive Waste (DNDR) was built in 1985 in Baita, Bihor county and placed into operation. Therefore, through the construction and operation of the treatment and final disposal capabilities, Romania has solved the management of the low and intermediate level radioactive waste while providing for the protection of the people and environment. (author)

  2. New Materials Developed To Meet Regulatory And Technical Requirements Associated With In-Situ Decommissioning Of Nuclear Reactors And Associated Facilities

    International Nuclear Information System (INIS)

    Blankenship, J.; Langton, C.; Musall, J.; Griffin, W.

    2012-01-01

    For the 2010 ANS Embedded Topical Meeting on Decommissioning, Decontamination and Reutilization and Technology, Savannah River National Laboratory's Mike Serrato reported initial information on the newly developed specialty grout materials necessary to satisfy all requirements associated with in-situ decommissioning of P-Reactor and R-Reactor at the U.S. Department of Energy's Savannah River Site. Since that report, both projects have been successfully completed and extensive test data on both fresh properties and cured properties has been gathered and analyzed for a total of almost 191,150 m 3 (250,000 yd 3 ) of new materials placed. The focus of this paper is to describe the (1) special grout mix for filling the P-Reactor vessel (RV) and (2) the new flowable structural fill materials used to fill the below grade portions of the facilities. With a wealth of data now in hand, this paper also captures the test results and reports on the performance of these new materials. Both reactors were constructed and entered service in the early 1950s, producing weapons grade materials for the nation's defense nuclear program. R-Reactor was shut down in 1964 and the P-Reactor in 1991. In-situ decommissioning (ISD) was selected for both facilities and performed as Comprehensive Environmental Response, Compensations and Liability Act actions (an early action for P-Reactor and a removal action for R-Reactor), beginning in October 2009. The U.S. Department of Energy concept for ISD is to physically stabilize and isolate intact, structurally robust facilities that are no longer needed for their original purpose of producing (reactor facilities), processing (isotope separation facilities), or storing radioactive materials. Funding for accelerated decommissioning was provided under the American Recovery and Reinvestment Act. Decommissioning of both facilities was completed in September 2011. ISD objectives for these CERCLA actions included: (1) Prevent industrial worker exposure to

  3. Evaluation of Nuclear Facility Decommissioning Projects. Summary Report. Three Mile Island Unit 2 Polar Crane Recovery

    International Nuclear Information System (INIS)

    Doerge, D. H.; Miller, R. L.

    1984-08-01

    This document summarizes information concerning restoration of the Three Mile Island-Unit 2 Polar Crane to a fully operational condition following the loss of coolant accident experienced on March 28, 1979. The data collected from activity reports, reactor containment entry records, and other sources were placed in a computerized information retrieval/manipulation system which permits extraction/manipulation of specific data which could be utilized in planning for recovery activities should a similar accident occur in a nuclear generating plant. The information is presented in both computer output form and a manually assembled summarization. This report contains only the manpower requirements and radiation exposures actually incurred during recovery operations within the reactor containment and does not include support activities or costs. (author)

  4. Decommissioning Strategies Selection for Facilities Using Radioactive Material

    International Nuclear Information System (INIS)

    Husen Zamroni; Jaka Rachmadetin

    2008-01-01

    The facilities using radioactive material that have been stopped operation will require some form of the decommissioning for public and environment safety. The approaches are identified by three decommissioning strategies: immediate dismantling, deferred dismantling and entombment. If a facility undergoes immediate dismantling, most radio nuclides will have no such sufficient time to decay and therefore this strategy may not provide reduction in the worker exposure. A facility that undergoes deferred dismantling may advantage from the radioactive decay of residual radio nuclides during the long term storage period and entombment could be a viable option for other nuclear facilities containing only short lived or limited concentrations of long lived radionuclides. Mostly, only two types of the decommissioning used to be done in the world, immediate and deferred dismantling. (author)

  5. Preliminary identification of contaminating α- and β-emitting radionuclides in nuclear facilities to be decommissioned through Digital Autoradiography

    International Nuclear Information System (INIS)

    Haudebourg, Raphael; Fichet, Pascal

    2016-01-01

    In previous publications, we presented how Digital Autoradiography (DA) could be of the most useful help in a preparation to decommissioning context: with this technique, a radiological mapping of the facility to dismantle can be obtained at a rate of around 2 weeks/100 m 2 . The technique is sensitive to all types of radioactivity (including α and 3 H- or 14 C-emitted β) and to both labile and fixed radioactivity. The method (radiosensitive screens exposure followed by a scanning step at the laboratory in a small-size device) neither involves nuclear material transportation, neither produces wastes, nor requires operators' presence during signal acquisition. The purpose is to accurately locate possible contamination spots, in order to relevantly perform targeted sampling and thus limit destructive analyses runs at the laboratory. In the latest developments, additional methods were implemented to analyze various nuclear samples (wastes, blocks, rubbles, pieces of furniture, drilled cores...) through this technique, to preliminary check for contamination, and to evaluate contamination location, homogeneity, and activity. These methods have proven themselves relevant and useful to build appropriate analyses and optimized decontamination protocols at the LASE (Laboratory of Analyses and Operators' Support). In this paper, we propose a new autoradiographic tool providing the identification of the contaminating radionuclide of a sample or an area, based on the stacking of several screens. The decrease of the signal screen after screen could be considered specific to one radionuclide. Modeling results obtained through Monte Carlo N-Particle transport code (MCNP) were in excellent agreement with experimental results obtained with sealed sources. Moreover, a method was developed to scan all the screens in the stack in only one run (instead of as many runs as screens) to shorten analysis duration. In the case of non-penetrating radiations (α particles, 3 H- or

  6. Re-utilization of concrete from decommissioned nuclear facilities by re-clinkering

    International Nuclear Information System (INIS)

    Costes, J.R.

    1998-01-01

    Usually concrete is reused as aggregates. To maximize reusing by producing a new concrete, separation of its fundamental components (aggregates, sand, cement) is required. But can already hydrated cement be re-clinkered and become new good cement again? This paper shows how specimen of pure cement paste of ordinary Portland cement was hydrated then crushed and reclinkerised. Chemical and, X ray diffraction analysis, electronic microscope coupled with X fluorescence observations, demonstrate that very few differences occurs in the cement paste before and after re-clinkering; mechanical properties of the reactivated powder are very satisfactory, even exceeding the strength of the original pure cement paste. As this process involves heating up to 1450 deg C, some of the contamination (caesium, ruthenium) may also be eliminated by volatilization and recovery on filters. This process could be very promising to complete recycle large quantities of low level contaminated concrete inside the nuclear industry as alternative to storage in specific and expensive dump, as it is now the case for steel materials. (authors)

  7. Costs of Decommissioning Nuclear Power Plants

    International Nuclear Information System (INIS)

    Neri, Emilio; French, Amanda; Urso, Maria Elena; Deffrennes, Marc; Rothwell, Geoffrey; ); Rehak, Ivan; Weber, Inge; ); Carroll, Simon; Daniska, Vladislav

    2016-01-01

    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)

  8. Decommissioning of naval nuclear ships

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1993-10-01

    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)

  9. Generic environmental impact statement in support of rulemaking on radiological criteria for decommissioning of NRC-licensed nuclear facilities. Appendices; Draft report for comment -- Volume 2

    International Nuclear Information System (INIS)

    1994-08-01

    The action being considered in this draft Generic Environmental Impact Statement (GEIS) is an amendment to the Nuclear Regulatory Commission's (NRC) regulations in 10 CFR Part 20 to include radiological criteria for decommissioning of lands and structures at nuclear facilities. Under the National Environmental Policy Act (NEPA), all Federal agencies must consider the effect of their actions on the environment. To fulfill NRC's responsibilities under NEPA, the Commission is preparing this GEIS which analyzes alternative courses of action and the costs and impacts associated with those alternatives. In preparing the GEIS, the following approach was taken: (1) a listing was developed of regulatory alternatives for establishing radiological criteria for decommissioning; (2) for each alternative, a detailed analysis and comparison of incremental impacts, both radiological and nonradiological, to workers, members of the public, and the environment, and costs, were performed; and (3) based on the analysis of impacts and costs, preliminary recommendations were provided. Contained in the GEIS are recommendations related to the definition of decommissioning, the scope of rulemaking, the radiological criteria, restrictions on use, citizen participation, use of the GEIS in site-specific cases, and minimization of contamination

  10. Generic environmental impact statement in support of rulemaking on radiological criteria for decommissioning of NRC-licensed nuclear facilities. Main report; Draft report for comment: Volume 1

    International Nuclear Information System (INIS)

    1994-08-01

    The action being considered in this draft Generic Environmental Impact Statement (GEIS) is an amendment to the Nuclear Regulatory Commission's (NRC) regulations in 10 CFR Part 20 to include radiological criteria for decommissioning of lands and structures at nuclear facilities. Under the National Environmental Policy Act (NEPA), all Federal agencies must consider the effect of their actions on the environment. To fulfill NRC's responsibilities under NEPA, the Commission is preparing this GEIS which analyzes alternative courses of action and the costs and impacts associated with those alternatives. In preparing the GEIS, the following approach was taken: (1) a listing was developed of regulatory alternatives for establishing radiological criteria for decommissioning; (2) for each alternative, a detailed analysis and comparison of incremental impacts, both radiological and nonradiological, to workers, members of the public, and the environment, and costs, were performed; and (3) based on the analysis of impacts and costs, preliminary recommendations were provided. Contained in the GEIS are recommendations related to the definition of decommissioning, the scope of rulemaking, the radiological criteria, restrictions on use, citizen participation, use of the GEIS in site-specific cases, and minimization of contamination

  11. Project management for the decommissioning and dismantling of nuclear facilities; Projektmanagement fuer Stilllegung und Rueckbau kerntechnischer Anlagen

    Energy Technology Data Exchange (ETDEWEB)

    Klasen, Joerg; Wilhelm, Oliver [ENBW Kernkraft GmbH, Neckarwestheim (Germany); Seizer, Burkhard; Schuetz, Tobias [Drees und Sommer, Stuttgart (Germany)

    2015-12-15

    The decommissioning of nuclear power plants is executed in a classic project manner as it is known from other construction projects. It is obvious to use the known portfolio of project management tools. The complexity that is created by the large size of the project in combination with safety requirements of the nuclear industry has to be handled. Complexity can only be managed addressing two main drivers: Prioritization and speed (agility) in project execution. Prioritization can be realized by applying tools like Earned Value Management. A high speed of project execution is established by applying Agile Management like SCRUM-methods. This method is adopted in the context of the cooperation ''Complex Projects'' to the needs of nuclear industry.

  12. The decommissioning of nuclear power stations

    International Nuclear Information System (INIS)

    Barker, F.

    1992-01-01

    This report has been commissioned by the National Steering Committee of Nuclear Free Local Authorities to provide: a comprehensive introduction to the technical, social, political, environmental and economic dimensions to nuclear power station decommissioning; an independent analysis of Nuclear Electric's recent change of decommissioning strategy; the case for wider public involvement in decision making about decommissioning; and a preliminary assessment of the potential mechanisms for achieving that essential wider public involvement

  13. Green Vinca - Vinca Institute nuclear decommissioning program

    International Nuclear Information System (INIS)

    Pesic, M.; Subotic, K.; Ljubenov, V.; Sotic, O.

    2003-01-01

    Current conditions related to the nuclear and radiation safety in the Vinca Institute of Nuclear Sciences, Belgrade, Serbia and Montenegro are the result of the previous nuclear programs in the former Yugoslavia and strong economic crisis during the previous decade. These conditions have to be improved as soon as possible. The process of establishment and initialisation of the Vinca Institute Nuclear Decommissioning (VIND) Program, known also as the 'Green Vinca' Program supported by the Government of the Republic Serbia, is described in this paper. It is supposed to solve all problems related to the accumulated spent nuclear fuel, radioactive waste and decommissioning of RA research reactor. Particularly, materials associated to the RA reactor facility and radioactive wastes from the research, industrial, medical and other applications, generated in the previous period, which are stored in the Vinca Institute, are supposed to be proper repackaged and removed from the Vinca site to some other disposal site, to be decided yet. Beside that, a research and development program in the modern nuclear technologies is proposed with the aim to preserve experts, manpower and to establish a solid ground for new researchers in field of nuclear research and development. (author)

  14. Development programs on decommissioning technology for reactors and fuel cycle facilities in Japan

    International Nuclear Information System (INIS)

    Fujiki, K.

    1992-01-01

    The Science and Technology Agency (STA) of Japan is promoting technology development for decommissioning of nuclear facilities by entrusting various research programs to concerned research organisations: JAERI, PNC and RANDEC, including first full scale reactor decommissioning of JPDR. According to the results of these programs, significant improvement on dismantling techniques, decontamination, measurement etc. has been achieved. Further development of advanced decommissioning technology has been started in order to achieve reduction of duration of decommissioning work and occupational exposures in consideration of the decommissioning of reactors and fuel cycle facilities. (author) 5 refs.; 7 figs.; 1 tab

  15. Preliminary nuclear decommissioning cost study

    International Nuclear Information System (INIS)

    Sissingh, R.A.P.

    1981-04-01

    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)

  16. Decommission of nuclear ship 'MUTSU'

    International Nuclear Information System (INIS)

    Tateyama, Takeshi

    1996-01-01

    The nuclear-powered ship 'MUTSU' was decommissioned by removing the reactor room in June 1995, which was hoisted and transported by a floating crane to a shore storage room at Sekinehama, Aomori Prefecture. This work was carried out in three stages: extraction of the spent fuel assemblies and neutron sources, dismantling of the machinery in the reactor auxiliary room, and separation and transportation of the reactor together with the secondary shielding structure and surrounding hull. IHI mainly conducted the third stage work. The separation work of the reactor room structure using a semisubmersible barge is outlined. Stress analysis and design of the reactor room for lifting work is also described. (author)

  17. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    International Nuclear Information System (INIS)

    Bierschbach, M.C.; Haffner, D.R.; Schneider, K.J.; Short, S.M.

    2002-01-01

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of 3 H-labeled compounds; a laboratory for the manufacture of 14 C-labeled compounds; a laboratory for the manufacture of 123 I-labeled compounds; a laboratory for the manufacture of 137 Cs sealed sources; a laboratory for the manufacture of 241 Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a facility, DECON requires

  18. Revised Analyses of Decommissioning Reference Non-Fuel-Cycle Facilities

    Energy Technology Data Exchange (ETDEWEB)

    MC Bierschbach; DR Haffner; KJ Schneider; SM Short

    2002-12-01

    Cost information is developed for the conceptual decommissioning of non-fuel-cycle nuclear facilities that represent a significant decommissioning task in terms of decontamination and disposal activities. This study is a re-evaluation of the original study (NUREG/CR-1754 and NUREG/CR-1754, Addendum 1). The reference facilities examined in this study are the same as in the original study and include: a laboratory for the manufacture of {sup 3}H-labeled compounds; a laboratory for the manufacture of {sup 14}C-labeled compounds; a laboratory for the manufacture of {sup 123}I-labeled compounds; a laboratory for the manufacture of {sup 137}Cs sealed sources; a laboratory for the manufacture of {sup 241}Am sealed sources; and an institutional user laboratory. In addition to the laboratories, three reference sites that require some decommissioning effort were also examined. These sites are: (1) a site with a contaminated drain line and hold-up tank; (2) a site with a contaminated ground surface; and (3) a tailings pile containing uranium and thorium residues. Decommissioning of these reference facilities and sites can be accomplished using techniques and equipment that are in common industrial use. Essentially the same technology assumed in the original study is used in this study. For the reference laboratory-type facilities, the study approach is to first evaluate the decommissioning of individual components (e.g., fume hoods, glove boxes, and building surfaces) that are common to many laboratory facilities. The information obtained from analyzing the individual components of each facility are then used to determine the cost, manpower requirements and dose information for the decommissioning of the entire facility. DECON, the objective of the 1988 Rulemaking for materials facilities, is the decommissioning alternative evaluated for the reference laboratories because it results in the release of the facility for restricted or unrestricted use as soon as possible. For a

  19. Aspects related to the decommissioning of the nuclear power plants

    International Nuclear Information System (INIS)

    Goicea, Andrei; Andrei, Veronica

    2003-01-01

    All power plants, either coal, gas or nuclear, at the end of their life needs to be decommissioned and demolished and thus, to made the site available for other uses. The first generation nuclear power plants were designed for a life of about 30 years and some of them proved capable of continuing well beyond this term. Newer plants have been designed for a 40 to 60 years operating life. To date, other 90 commercial power reactors have been retired from operation. For nuclear power plants and nuclear facilities in general the decommissioning process consists of some or all of the following activities: the safe management of nuclear materials held in the facility, cleaning-up of radioactivity (decontamination), plant dismantling, progressive demolition of the plant and site remediation. Following the decommissioning, the regulatory controls covering facility end, partially or totally, and the safe site is released for appropriate alternative use. Cernavoda NPP is a young plant and it can benefit from the continuously developing experience of the decommissioning process at the international level. The current experience allows the most metallic parts of a nuclear power to be decontaminated and recycled and makes available proven techniques and equipment to dismantle nuclear facilities safely. As experience is gained, decommissioning costs for nuclear power plants, including disposal of associated wastes, are reducing and thus, contribute in a smaller fraction to the total cost of electricity generation. The new specific Romanian regulations establish a funding system for decommissioning and provisions for long-term radioactive waste management. In the near future a decommissioning plan will be made available for Cernavoda NPP. Since the plant has only 7 years operation, that plan can be improved in order to benefit from international experience that is growing. (authors)

  20. Factors influencing the decommissioning of large-scale nuclear plants

    International Nuclear Information System (INIS)

    Large, J.H.

    1988-01-01

    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. For the final stage of decommissioning the nuclear industry could either completely dismantle the reactor island leaving a green-field site or, alternatively, the reactor island could be maintained indefinitely with additional super- and substructure containment. At this time the first of these options, or deferred decommissioning, prevails and with this 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 deferred decommissioning strategy is wrong and it is not possible to completely dismantle the reactor islands a century into the future, then it may be too late to effect sufficient longer term containment to maintain the reactor hulks in a reliable condition. With respect to the final decommissioning of large-scale nuclear plant, it is concluded that the nuclear industry does not know quite how to do it, when it will be attempted and when it will be completed, and they do not know how much it will eventually cost. (author)

  1. Deregulation in the field of decommissioning and dismantling of nuclear facilities. Legal frame conditions and regulations in the field of nuclear engineering; Deregulierung bei der Stillegung und Beseitigung nuklearer Anlagen; Rechtliche Rahmenbedingungen und kerntechnisches Regelwerk

    Energy Technology Data Exchange (ETDEWEB)

    Kurz, A [Kernforschungszentrum Karlsruhe GmbH (Germany). Vorstandsbereich 2 - Neue Technologien und Grundlagenforschung; Baumgaertel, G [Kernforschungszentrum Karlsruhe GmbH (Germany). Koordinationsstelle Genehmigungsverfahren (KGV)

    1994-05-01

    The report comprises two articles covering current topics of the decommissioning and dismantling of nuclear facilities. In the first article written by Kurz, the legal standards are listed together with conclusions and proposals regarding their implementation for the further development of this field of law. The article by Baumgaertel is aimed at evaluating the regulations governing nuclear technology as regards their applicability to the decommissioning and dismantling of nuclear facilities. These articles shall contribute to the discussions taking place in this field at the moment. As a result, an appropriate and project-specific application of the legal provisions and not legally binding (technical) regulations in the field of nuclear technology (deregulation) in the licensing procedures required for the decommissioning and dismantling of nuclear facilities is requested by the authors. (orig.) [Deutsch] Der Bericht enthaelt zwei Ausarbeitungen zu aktuellen Themenstellungen der Stillegung und Beseitigung nuklearer Anlagen. Der Bericht von Kurz beinhaltet eine thesenartige Auflistung der normativen Voraussetzungen mit Schlussfolgerungen und Umsetzungsvorschlaegen zur Weiterentwicklung dieses Rechtsgebietes; die Ausarbeitung von Baumgaertel beinhaltet eine wertende Durchsicht des kerntechnischen Regelwerkes im Hinblick auf die Anwendbarkeit bei der Stillegung und Beseitigung nuklearer Anlagen. Die Ausarbeitungen dienen als Beitrag zur aktuellen Diskussion in diesem Themenfeld. Im Ergebnis fordern die Autoren die angemessene, vorhabensspezifische Anwendung der rechtlichen Voraussetzungen des kerntechnischen Regelwerkes (Deregulierung) in den zur Stillegung und Beseitigung nuklearer Anlagen erforderlichen Genehmigungsverfahren. (orig.)

  2. EPRI nuclear power plant decommissioning technology program

    International Nuclear Information System (INIS)

    Kim, Karen S.; Bushart, Sean P.; Naughton, Michael; McGrath, Richard

    2011-01-01

    The Electric Power Research Institute (EPRI) is a non-profit research organization that supports the energy industry. The Nuclear Power Plant Decommissioning Technology Program conducts research and develops technology for the safe and efficient decommissioning of nuclear power plants. (author)

  3. Model Regulations for Decommissioning of Facilities

    International Nuclear Information System (INIS)

    2017-07-01

    The IAEA has systematic programmes to provide Member States with the guidance, services and training necessary for establishing a legal and regulatory framework, including the planning and implementation of decommissioning. The model regulations provided in this publication cover all aspects of the planning, conduct and termination of the decommissioning of facilities and management of the associated waste, in accordance with the relevant requirements of the IAEA safety standards. They provide a framework for establishing regulatory requirements and conditions of authorization to be incorporated into individual authorizations for the decommissioning of specific facilities. The model regulations also establish criteria to be used for assessing compliance with regulatory requirements. The publication will be of assistance to Member States in appraising the adequacy of their existing regulations and regulatory guides, and serves as a reference for those Member States developing regulations for the first time.

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

    International Nuclear Information System (INIS)

    Yanagihara, Satoshi

    2014-01-01

    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)

  5. Commercialization of nuclear power plant decommissioning technology

    International Nuclear Information System (INIS)

    Williams, D.H.

    1983-01-01

    The commercialization of nuclear power plant decommissioning is presented as a step in the commercialization of nuclear energy. Opportunities for technology application advances are identified. Utility planning needs are presented

  6. Decommissioning of the Risoe Hot Cell facility

    International Nuclear Information System (INIS)

    Carlsen, H.

    1994-06-01

    Nuclear fuels have been handled and examined after irradiation by physical and chemical techniques, and radiotherapy sources, mainly 60 Co, have been produced at Risoe National Laboratory since 1964. The aims of decommissioning (during 1990-94, at IAEA Stage 2 level for reactors) were to obtain safe conditions for the remaining parts of the facility and to produce clean space areas for new projects. The facility comprises 6 concrete cells, several lead-shielded steel cells, glove boxes, shielded storage for waste, a remotely operated optical microscope, a frogman area for personnel access to the concrete cells, a decontamination facility, workshops and safety installations. All steel cells, glove boxes and the microscope were emptied and removed. The concrete cells were emptied of fissile material, scientific equipment, general tools and scrap. Decontamination should facilitate waste packing and reduce amount of waste to be stored temporarily at the Risoe waste treatment facility together with highly active waste. The concrete cells were cleaned remotely by wiping, hot spot removal, by mechanical means and vacuum cleaning. The interiors of 2 cells were decontaminated by high pressure water jetting. All master-slave manipulators and part of the contaminated ventilation system at the cells were removed. The cells are left in a non-ventilated state, connected to the atmosphere by an absolute filter. The main contaminants measured before cell closure were 60 Co, 137 Cs and alpha-emitters. Dismantling, decontamination waste disposal and received doses are described. Simple techniques involving low doses were found to be very effective. (AB)

  7. Radioactive waste isolation in salt: peer review of the Office of Nuclear Waste Isolation's plan to decommission and reclaim exploratory shafts and related facilities

    International Nuclear Information System (INIS)

    Fenster, D.F.; Schubert, J.P.; Zellmer, S.D.; Harrison, W.; Simpson, D.G.; Busch, J.S.

    1984-07-01

    The following recommendations are made for improving the Office of Nuclear Waste Isolation's plan for decommissioning and reclaiming exploratory shafts and other facilities associated with site characterization: (1) Discuss more comprehensively the technical aspects of activities related to decommissioning and reclamation. More detailed information will help convince the staff of the US Nuclear Regulatory Commission and others that the activities as outlined in the plan are properly structured and that the stated goals can be achieved. (2) Address in considerably greater detail how the proposed activities will satisfy specific federal, state, and local laws and regulations. (3) State clearly the precise purpose of the plan, preferably at the beginning and under an appropriate heading. (4) Also under an appropriate heading and immediately after the section on purpose, describe the scope of the plan. The tasks covered by this plan and closely related tasks covered by other appropriate plans should be clearly differentiated. (5) Discuss the possible environmental effects of drilling the exploratory shaft, excavating drifts in salt, and drilling boreholes as part of site characterization. Mitigation activities should be designed to counter specific potential impacts. High priority should be given to minimizing groundwater contamination and restoring the surface to a condition consistent with the proposed land use following completion of characterization activities at sites not chosen for repository construction. (6) Define ambiguous technical terms, either in the text when first introduced or in an appended glossary

  8. Decommissioning and dismantling: evaluation of possible radiological impacts from exceeding clearance levels at nuclear facilities. Final report

    International Nuclear Information System (INIS)

    Kirchhoff, J.; Stasch, W.P.; Thierfeldt, S.; Kugeler, E.

    2001-01-01

    On June 14, 2000 the German power utilities have reached an agreement with the German government (energy consent). According to that all nuclear power plants in Germany shall be shut down approximately until the year 2020 and shall be decommissioned afterwards. Almost 95% of the mass of a nuclear power plant can be re-used or recycled as normal material and waste after the necessary handling (decontamination) and clearance measurements. For the release of the entire mass of a NPP several hundreds of thousand radioactivity measurements (so called free release measurements) are necessary. With this huge number of measurements mistakes cannot be excluded. The study includes several radiological scenarios which could result from mistakes during the release/clearance procedure. The radiation doses calculated during the simulation show that some faulty releases can give rise to doses above the trivial dose level of some 10 μSv. An effective dose up to 400 μSv for individuals has been determined. However, with a high certainty it can be excluded that the individual effective dose will reach the range of 1000 μSv even with a hypothetical consideration of a concatenation of several conditions. Because of the low probability of appearance and their minimal radiological effects mistakes during the release procedure pose no hazards. (orig.) [de

  9. Decommissioning of Salaspils nuclear reactor

    International Nuclear Information System (INIS)

    Abramenkovs, A.; Malnachs, J.; Popelis, A.

    2002-01-01

    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)

  10. Program change management during nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Bushart, Sean; Kim, Karen; Naughton, Michael

    2011-01-01

    Decommissioning a nuclear power plant is a complex project. The project involves the coordination of several different departments and the management of changing plant conditions, programs, and regulations. As certain project Milestones are met, the evolution of such plant programs and regulations can help optimize project execution and cost. This paper will provide information about these Milestones and the plant departments and programs that change throughout a decommissioning project. The initial challenge in the decommissioning of a nuclear plant is the development of a definitive plan for such a complex project. EPRI has published several reports related to decommissioning planning. These earlier reports provided general guidance in formulating a Decommissioning Plan. This Change Management paper will draw from the experience gained in the last decade in decommissioning of nuclear plants. The paper discusses decommissioning in terms of a sequence of major Milestones. The plant programs, associated plans and actions, and staffing are discussed based upon experiences from the following power reactor facilities: Maine Yankee Atomic Power Plant, Yankee Nuclear Power Station, and the Haddam Neck Plant. Significant lessons learned from other sites are also discussed as appropriate. Planning is a crucial ingredient of successful decommissioning projects. The development of a definitive Decommissioning Plan can result in considerable project savings. The decommissioning plants in the U.S. have planned and executed their projects using different strategies based on their unique plant circumstances. However, experience has shown that similar project milestones and actions applied through all of these projects. This allows each plant to learn from the experiences of the preceding projects. As the plant transitions from an operating plant through decommissioning, the reduction and termination of defunct programs and regulations can help optimize all facets of

  11. Preliminary plan for decommissioning - repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    Hallberg, Bengt; Tiberg, Liselotte

    2010-06-01

    The final disposal facility for spent nuclear fuel is part of the KBS-3 system, which also consists of a central facility for interim storage and encapsulation of the spent nuclear fuel and a transport system. The nuclear fuel repository will be a nuclear facility. Regulation SSMFS 2008:1 (Swedish Radiation Safety Authority's regulations on safety of nuclear facilities) requires that the licensee must have a current decommissioning plan throughout the facility lifecycle. Before the facility is constructed, a preliminary decommissioning plan should be reported to the Swedish Radiation Safety Authority. This document is a preliminary decommissioning plan, and submitted as an attachment to SKB's application for a license under the Nuclear Activities Act to construct, own and operate the facility. The final disposal facility for spent nuclear fuel consists of an above ground part and a below ground part and will be built near Forsmark and the final repository for radioactive operational waste, SFR. The parts above and below ground are connected by a ramp and several shafts, e.g. for ventilation. The below ground part consists of a central area, and several landfill sites. The latter form the repository area. The sealed below ground part constitutes the final repository. The decommissioning is taking place after the main operation has ended, that is, when all spent nuclear fuel has been deposited and the deposition tunnels have been backfilled and plugged. The decommissioning involves sealing of the remaining parts of the below ground part and demolition of above ground part. When decommissioning begins, there will be no contamination in the facility. The demolition is therefore performed as for a conventional plant. Demolition waste is sorted and recycled whenever possible or placed in landfill. Hazardous waste is managed in accordance with current regulations. A ground investigation is performed and is the basis for after-treatment of the site. The timetable for the

  12. Decommissioning of surplus facilities at ORNL

    International Nuclear Information System (INIS)

    Myrick, T.E.; Coobs, J.H.

    1985-01-01

    The Surplus Facilities Management Program (SFMP) at Oak Ridge National Laboratory (ORNL) is part of the Department of Energy's (DOE) National SFMP, administered by the Richland Operations Office. This program was established to provide for the management of certain DOE surplus radioactively contaminated facilities from the end of their operating life until final facility disposition is completed. As part of this program, the ORNL SFMP oversees some 75 facilities, ranging in complexity from abandoned waste storage tanks to large experimental reactors. This paper describes the scope of the ORNL program and outlines the decommissioning activities currently underway, including a brief description of the decontamination techniques being utilized. 4 refs., 3 figs., 2 tabs

  13. Evaluating decommissioning costs for nuclear power plants

    International Nuclear Information System (INIS)

    MacDonald, R.R.

    1980-01-01

    An overview is presented of the economic aspects of decommissioning of large nuclear power plants in an attempt to put the subject in proper perspective. This is accomplished by first surveying the work that has been done to date in evaluating the requirements for decommissioning. A review is presented of the current concepts of decommissioning and a discussion of a few of the uncertainties involved. This study identifies the key factors to be considered in the econmic evaluation of decommissioning alternatives and highlights areas in which further study appears to be desirable. 12 refs

  14. Decommissioning strategies for facilities using radioactive material

    International Nuclear Information System (INIS)

    2007-01-01

    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

  15. Regulatory aspects of nuclear reactor decommissioning

    International Nuclear Information System (INIS)

    Ross, W.M.

    1990-01-01

    The paper discusses the regulatory aspects of decommissioning commercial nuclear power stations in the UK. The way in which the relevant legislation has been used for the first time in dealing with the early stages of decommissioning commercial nuclear reactor is described. International requirements and how they infit with the UK system are also covered. The discussion focusses on the changes which have been required, under the Nuclear Site Licence, to ensure that the licensee carries out of work of reactor decommissioning in a safe and controlled manner. (Author)

  16. Decommissioning and dismantling of nuclear installations

    International Nuclear Information System (INIS)

    Pelzer, N.

    1993-01-01

    The German law governing decommissioning and dismantling of nuclear installations can be called to be embryonic as compared to other areas of the nuclear regulatory system, and this is why the AIDN/INLA regional meeting organised by the German national committee in July 1992 in Schwerin has been intended to elaborate an assessment of the current legal situation and on this basis establish proposals for enhancement and development, taking into account the experience reported by experts from abroad. The proceedings comprise the paper of the opening session, 'Engineering and safety aspects of the decommissioning of nuclear installations', and the papers and discussions of the technical sessions entitled: - Comparative assessment of the regulatory regimes. - Legislation governing the decommissioning of nuclear installations in Germany. - Analysis of the purpose and law making substance of existing regulatory provisions for the decommissioning of nuclear installations. All seventeen papers of the meeting have been prepared for separate retrieval from the database. (orig./HSCH) [de

  17. Preservation and Implementation of Decommissioning Lessons Learned in the United States Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Rodriguez, Rafael L.

    2008-01-01

    Over the past several years, the United States Nuclear Regulatory Commission (NRC) has actively worked to capture and preserve lessons learned from the decommissioning of nuclear facilities. More recently, NRC has involved industry groups, the Organization of Agreement States (OAS), and the Department of Energy (DOE) in the effort to develop approaches to capture, preserve and disseminate decommissioning lessons learned. This paper discusses the accomplishments of the working group, some lessons learned by the NRC in the recent past, and how NRC will incorporate these lessons learned into its regulatory framework. This should help ensure that the design and operation of current and future nuclear facilities will result in less environmental impact and more efficient decommissioning. In summary, the NRC will continue capturing today's experience in decommissioning so that future facilities can take advantage of lessons learned from today's decommissioning projects. NRC, both individually and collectively with industry groups, OAS, and DOE, is aggressively working on the preservation and implementation of decommissioning lessons learned. The joint effort has helped to ensure the lessons from the whole spectrum of decommissioning facilities (i.e., reactor, fuel cycle, and material facilities) are better understood, thus maximizing the amount of knowledge and best practices obtained from decommissioning activities. Anticipated regulatory activities at the NRC will make sure that the knowledge gained from today's decommissioning projects is preserved and implemented to benefit the nuclear facilities that will decommission in the future

  18. Decommissioning of U.S. uranium production facilities

    Energy Technology Data Exchange (ETDEWEB)

    1995-02-01

    From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U{sub 3}O{sub 8} to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with decommissioning-environmental, political, and financial-this report will concentrate on the answers to three questions: (1) What is required? (2) How is the process implemented? (3) What are the costs? Regulatory control is exercised principally through the NRC licensing process. Before receiving a license to construct and operate an uranium producing facility, the applicant is required to present a decommissioning plan to the NRC. Once the plan is approved, the licensee must post a surety to guarantee that funds will be available to execute the plan and reclaim the site. This report by the Energy Information Administration (EIA) represents the most comprehensive study on this topic by analyzing data on 33 (out of 43) uranium production facilities located in Colorado, Nebraska, New Mexico, South Dakota, Texas, Utah, and Washington.

  19. Decommissioning of U.S. uranium production facilities

    International Nuclear Information System (INIS)

    1995-02-01

    From 1980 to 1993, the domestic production of uranium declined from almost 44 million pounds U 3 O 8 to about 3 million pounds. This retrenchment of the U.S. uranium industry resulted in the permanent closing of many uranium-producing facilities. Current low uranium prices, excess world supply, and low expectations for future uranium demand indicate that it is unlikely existing plants will be reopened. Because of this situation, these facilities eventually will have to be decommissioned. The Uranium Mill Tailings and Radiation Control Act of 1978 (UMTRCA) vests the U.S. Environmental Protection Agency (EPA) with overall responsibility for establishing environmental standards for decommissioning of uranium production facilities. UMTRCA also gave the U.S. Nuclear Regulatory Commission (NRC) the responsibility for licensing and regulating uranium production and related activities, including decommissioning. Because there are many issues associated with decommissioning-environmental, political, and financial-this report will concentrate on the answers to three questions: (1) What is required? (2) How is the process implemented? (3) What are the costs? Regulatory control is exercised principally through the NRC licensing process. Before receiving a license to construct and operate an uranium producing facility, the applicant is required to present a decommissioning plan to the NRC. Once the plan is approved, the licensee must post a surety to guarantee that funds will be available to execute the plan and reclaim the site. This report by the Energy Information Administration (EIA) represents the most comprehensive study on this topic by analyzing data on 33 (out of 43) uranium production facilities located in Colorado, Nebraska, New Mexico, South Dakota, Texas, Utah, and Washington

  20. Decommissioning of small medical, industrial and research facilities

    International Nuclear Information System (INIS)

    2003-01-01

    Most of the technical literature on decommissioning addresses the regulatory, organizational, technical and other aspects for large facilities such as nuclear power plants, reprocessing plants and relatively large prototype, research and test reactors. There are, however, a much larger number of licensed users of radioactive material in the fields of medicine, research and industry. Most of these nuclear facilities are smaller in size and complexity and may present a lower radiological risk during their decommissioning. Such facilities are located at research establishments, biological and medical laboratories, universities, medical centres, and industrial and manufacturing premises. They are often operated by users who have not been trained or are unfamiliar with the decommissioning, waste management and associated safety aspects of these types of facility at the end of their operating lives. Also, for many small users of radioactive material such as radiation sources, nuclear applications are a small part of the overall business or process and, although the operating safety requirements may be adhered to, concern or responsibility may not go much beyond this. There is concern that even the minimum requirements of decommissioning may be disregarded, resulting in avoidable delays, risks and safety implications (e.g. a loss of radioactive material and a loss of all records). Incidents have occurred in which persons have been injured or put at risk. It is recognized that the strategies and specific requirements for small facilities may be much less onerous than for large ones such as nuclear power plants or fuel processing facilities, but many of the same principles apply. There has been considerable attention given to nuclear facilities and many IAEA publications are complementary to this report. This report, however, attempts to give specific guidance for small facilities. 'Small' in this report does not necessarily mean small in size but generally modest in terms

  1. Decommissioning of the Risoe Hot Cell facility

    International Nuclear Information System (INIS)

    Carlsen, H.

    1994-02-01

    Concise description of progress in hot cell facility decommissioning at Risoe National Laboratory is presented. Removal of the large contaminated equipment has been completed, all the concrete cells have been finally cleaned. The total contamination left on the concrete walls is of the order of 1850 GBq. Preliminary smear tests proved the stack to be probably clean. The delay in project completion seems to be around 7 months, the remaining work being of rather conventional character. (EG)

  2. Decommissioning of the Risoe Hot Cell facility

    International Nuclear Information System (INIS)

    Carlsen, H.

    1991-08-01

    Concise descriptions of actions taken in relation to the decommissioning of the hot cell facility at Risoe National Laboratory are presented. The removal of fissile material, removal and decontamination of large cell internals, and of large equipment such as glove boxes and steel boxes, in addition to dose commitments, are explained. Tables illustrating the analysis of smear tests, constants for contamination level examination, contamination and radiation levels after cleaning and total contamination versus measured radiation are included. (AB)

  3. Russian nuclear-powered submarine decommissioning

    International Nuclear Information System (INIS)

    Bukharin, O.; Handler, J.

    1995-01-01

    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

  4. BN-350 nuclear power plant. Regulatory aspects of decommissioning

    International Nuclear Information System (INIS)

    Shiganakov, S.; Zhantikin, T.; Kim, A.

    2002-01-01

    Full text: The BN-350 reactor is a fast breeder reactor using liquid sodium as a coolant [1]. This reactor was commissioned in 1973 and operated for its design life of 20 years. Thereafter, it was operated on the basis of annual licenses, and the final shutdown was initially planned in 2003. In 1999, however, the Government of the Republic of Kazakhstan adopted Decree on the Decommissioning of BN-350 Reactor. This Decree establishes the conception of the reactor plant decommissioning. The conception envisages three stages of decommissioning. The first stage of decommissioning aims at putting the installation into a state of long term safe enclosure. The main goal is an achievement of nuclear-and radiation-safe condition and industrial safety level. The completion criteria for the stage are as follows: spent fuel is removed and placed in long term storage; radioactive liquid metal coolant is drained from the reactor and processed; liquid and solid radioactive wastes are reprocessed and long-term stored; systems and equipment, that are decommissioned at the moment of reactor safe store, are disassembled; radiation monitoring of the reactor building and environment is provided. The completion criteria of the second stage are as follows: 50 years is up; a decision about beginning of works by realization of dismantling and burial design is accepted. The goal of the third stage is partial or total dismantling of equipment, buildings and structure and burial. Since the decision on the decommissioning of BN-350 Reactor Facility was accepted before end of scheduled service life (2003), to this moment 'The Decommissioning Plan' (which in Kazakhstan is called 'Design of BN-350 reactor Decommission') was not worked out. For realization of the Governmental Decree and for determination of activities by the reactor safety provision and for preparation of its decommission for the period till Design approval the following documents were developed: 1. Special Technical Requirements

  5. Changing the Focus of Knowledge Management for Nuclear Decommissioning

    International Nuclear Information System (INIS)

    Radford, R.

    2016-01-01

    Full text: Knowledge Management (KM) has long been a recognized tool for improving the safety, efficiency and effectiveness of nuclear facilities. However, the objectives, tools and mechanisms utilized are often focused on steady-state maintenance of established knowledge and on incremental improvements to current practice. When nuclear facilities transition from routine operations to project-based decommissioning activities there is a need to reconsider the knowledge objectives, methodologies and tools to ensure that KM practices are relevant to the new activities being carried out and provide solutions to the new challenges posed in decommissioning. It is important that the changes required in preparation for and during the decommissioning phase are factored in to knowledge planning to ensure that KM activities are efficient and effective. This transition requires a change in the KM mind-set and a different way of setting new KM objectives. (author

  6. Nuclear decommissioning - practical experience of the private sector

    International Nuclear Information System (INIS)

    Brant, A.W.

    1988-01-01

    There is a growing requirement for decommissioning of redundant nuclear facilities. This has led to a number of opportunities for private sector organisations to carry out the work. This paper, based on two actual projects in the United Kingdom, outlines the input required from private sector contractors in executing such work. (author)

  7. Nuclear power plant decommissioning costs in perspective

    International Nuclear Information System (INIS)

    Rothwell, Geoffrey; Deffrennes, Marc; Weber, Inge

    2016-01-01

    At the international level, actual experience is limited in the completion of nuclear power plant decommissioning projects. Cost data for decommissioning projects are thus largely unavailable, with few examples of analyses or comparisons between estimates and actual costs at the project level. The Nuclear Energy Agency (NEA) initiated a project to address this knowledge gap and in early 2016 published the outcomes in the report on Costs of Decommissioning Nuclear Power Plants. The study reviews decommissioning costs and funding practices adopted by NEA member countries, based on the collection and analysis of survey data via a questionnaire. The work was carried out in co-operation with the International Atomic Energy Agency (IAEA) and the European Commission (EC). (authors)

  8. The regulatory framework for safe decommissioning of nuclear power plants in Korea

    International Nuclear Information System (INIS)

    Sangmyeon Ahn; Jungjoon Lee; Chanwoo Jeong; Kyungwoo Choi

    2013-01-01

    We are having 23 units of nuclear power plants in operation and 5 units of nuclear power plants under construction in Korea as of September 2012. However, we don't have any experience on shutdown permanently and decommissioning of nuclear power plants. There are only two research reactors being decommissioned since 1997. It is realized that improvement of the regulatory framework for decommissioning of nuclear facilities has been emphasized constantly from the point of view of IAEA's safety standards. It is also known that IAEA will prepare the safety requirement on decommissioning of facilities; its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA's Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we focus on identifying the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA's safety standards in order to achieve our goal. And then the plan is established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. It is expected that if the things will go forward as planned, the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards. (authors)

  9. Decommissioning of fuel PIE caves at Berkeley Nuclear Laboratories

    International Nuclear Information System (INIS)

    Brant, A.W.

    1990-01-01

    This paper describes the first major contract awarded to private industry to carry out decommissioning of a facility with significant radiation levels. The work required operatives to work in pressurised suits, entry times were significantly affected by sources of radiation in the Caves, being as low as thirty minutes per day initially. The Caves at Berkeley Nuclear Laboratories carry out post irradiation examination of fuel elements support units and reactor core components from CEGB power stations. The decommissioning work is part of an overall refurbishment of the facility to allow the receipt of AGR Fuel Stringer Component direct from power stations. The paper describes the decommissioning and decontamination of the facility from the remote removal and clean up work carried out by the client to the hands-on work. It includes reference to entry times, work patterns, interfaces with the client and the operations of the laboratory. Details of a specially adapted size reduction method are given. (Author)

  10. Management of Decommissioning on a Multi-Facility Site

    International Nuclear Information System (INIS)

    Laraia, Michele; McIntyre, Peter; Visagie, Abrie

    2008-01-01

    The management of the decommissioning of multi-facility sites may be inadequate or inappropriate if based on approaches and strategies developed for sites consisting of only a single facility. The varied nature of activities undertaken, their interfaces and their interdependencies are likely to complicate the management of decommissioning. These issues can be exacerbated where some facilities are entering the decommissioning phase while others are still operational or even new facilities are being built. Multi-facility sites are not uncommon worldwide but perhaps insufficient attention has been paid to optimizing the overall site decommissioning in the context of the entire life cycle of facilities. Decommissioning management arrangements need to be established taking a view across the whole site. A site-wide decommissioning management system is required. This should include a project evaluation and approval process and specific arrangements to manage identified interfaces and interdependencies. A group should be created to manage decommissioning across the site, ensuring adequate and consistent practices in accordance with the management system. Decommissioning management should be aimed at the entire life cycle of facilities. In the case of multi facility sites, the process becomes more complex and decommissioning management arrangements need to be established with a view to the whole site. A site decommissioning management system, a group that is responsible for decommissioning on site, a site project evaluation and approval process and specific arrangements to manage the identified interfaces are key areas of a site decommissioning management structure that need to be addressed to ensure adequate and consistent decommissioning practices. A decommissioning strategy based on single facilities in a sequential manner is deemed inadequate

  11. Decommissioning plan depleted uranium manufacturing facility

    International Nuclear Information System (INIS)

    Bernhardt, D.E.; Pittman, J.D.; Prewett, S.V.

    1987-01-01

    Aerojet Ordnance Tennessee, Inc. (Aerojet) is decommissioning its California depleted uranium (DU) manufacturing facility. Aerojet has conducted manufacturing and research and development activities at the facility since 1977 under a State of California Source Materials License. The decontamination is being performed by a contractor selector for technical competence through competitive bid. Since the facility will be released for uncontrolled use it will be decontaminated to levels as low as reasonably achievable (ALARA). In order to fully apply the principles of ALARA, and ensure the decontamination is in full compliance with appropriate guides, Aerojet has retained Rogers and Associaties Engineering Corporation (RAE) to assist in the decommissioning. RAE has assisted in characterizing the facility and preparing contract bid documents and technical specifications to obtain a qualified decontamination contractor. RAE will monitor the decontamination work effort to assure the contractor's performance complies with the contract specifications and the decontamination plan. The specifications require a thorough cleaning and decontamination of the facility, not just sufficient cleaning to meet the numeric cleanup criteria

  12. Civil engineering design for decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Paton, A.A.; Benwell, P.; Irwin, T.F.; Hunter, I.

    1984-01-01

    This report describes the work carried out by Taylor Woodrow Construction Limited (TWC) in a study aimed at identifying features which may be incorporated at the design stage of future nuclear power plants to facilitate their eventual decommissioning and, in so doing, promote economic and radiological benefits at teh decommissioning stage. For the purposes of this study, decommissioning of a nuclear facility means those measures taken at the end of the facility's operating life to remove it from the site and restore the site to green field conditions, and, while so doing, ensure the continued protection of the public from any residual radioactivity or other potential hazards present in or emanating from the facility. The overall decommissioning process involves eventual dismantling and demolition and may also include, where possible and appropriate, the intermediate steps of renewal and refurbishing. The work has been carried out in a number of sequential stages consisting principally of a literature review, identification of problems likely to arise in decommissioning, generation of possible solutions to the problems, first assessment of the feasibility of these solutions, closer investigation of promising solutions and, finally, preparation of conclusions and recommendations. (author)

  13. The Relevance of Metal Recycling for Nuclear Industry Decommissioning Programmes

    Energy Technology Data Exchange (ETDEWEB)

    O' Sullivan, P.J., E-mail: nea@nea.fr [OECD Nuclear Energy Agency, Paris (France)

    2011-07-15

    The large amount of scrap metal arising from the decommissioning of nuclear facilities may present significant problems in the event that the facility owners seek to implement a management strategy based largely or fully on disposal in dedicated disposal facilities. Depending on whether disposal facilities currently exist or need to be developed, this option can be very expensive. Also, public reluctance to accept the expansion of existing disposal facilities, or the siting of new ones, mean that the disposal option should be used only after a wide consideration of all available management options. A comparison of health, environmental and socio-economic impacts of the recycling of lightly contaminated scrap metal, as compared with equivalent impacts associated with the production of replacement material, suggests that recycling has significant overall advantages. With present-day technologies, a large proportion of the metal waste from decommissioning can be decontaminated to clearance levels because most of the contamination is on or near the surface of the metal. In purely economic terms, it makes little sense for lightly contaminated scrap metal from decommissioning, which tends to be of high quality, to be removed from the supply chain and replaced with metal from newly-mined ore. In many countries, the metal recycling industry remains reluctant to accept metal from decommissioning. In Germany, the recycling industry and the decommissioning industry have worked together to develop an approach whereby such material is accepted for melting and the recycled material and is then used for certain defined end uses. Sweden also uses dedicated melting facilities for the recycling of metal from the nuclear industry. Following this approach, the needs of the decommissioning industry are being met in a way that also addresses the needs of the recycling industry. (author)

  14. 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. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  15. 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)

  16. Cost estimation of the decommissioning of nuclear fuel cycle plants

    International Nuclear Information System (INIS)

    Barbe, A.; Pech, R.

    1991-01-01

    Most studies conducted to date on the cost of decommissioning nuclear facilities pertain to reactors. Few such studies have been performed on the cost of decommissioning nuclear fuel cycle plants, particularly spent fuel reprocessing plants. Present operators of these plants nevertheless need to assess such costs, at least in order to include the related expenses in their short-, medium- or long-term projections. They also need to determine now, for example, suitable production costs that the plant owners will have to propose to their customers. Unlike nuclear reactors for which a series effect is involved (PWRs, BWRs, etc.) and where radioactivity is relatively concentrated, industrial-scale reprocessing plants are large, complex installations for which decommissioning is a long and costly operation that requires a special approach. Faced with this problem, Cogema, the owner and operator of the La Hague and Marcoule reprocessing plants in France, called on SGN to assess the total decommissioning costs for its plants. This assessment led SGN to development by SGN engineers of a novel methodology and a computerized calculation model described below. The resulting methodology and model are applicable to other complex nuclear facilities besides reprocessing plants, such as laboratories and nuclear auxiliaries of reactor cores. (author)

  17. Decommissioning of nuclear power plant

    International Nuclear Information System (INIS)

    Sato, Tadamichi

    2002-01-01

    On nuclear energy facilities, an abolished one is often difficult to reuse, and is difficult to subdivide because of its strong structure and its inclusion of many apparatus and constructions containing radioactive materials in them. And, it is required to consider radiation management under dismantling operation and radioactive wastes forming at its subdivision. Abolishment of nuclear power station is a measure carrying out subdivision removing of a facility ended its role to a condition unnecessary for its radiation administration, and is defined as all of measures to be done after unused condition before reaching green field condition. Here were described on basic principle on abolishment measure in Japan, processing and disposition of subdivided wastes, and system preparation. (G.K.)

  18. Nuclear data requirements for fission reactor decommissioning

    International Nuclear Information System (INIS)

    Kocherov, N.P.

    1993-01-01

    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

  19. Decommissioning of the Risoe hot cell facility

    International Nuclear Information System (INIS)

    Carlsen, H.

    1992-02-01

    Concise descriptions of actions taken in relation to the decommissioning of the hot cell facility at Risoe National Laboratory are presented. The removal of fissile material, of large contaminated equipment from the concrete cell line and a separate shielded storage facility, and the removal of large contaminated facilities such as out cell parts of a tube transport system between a concrete cell and a lead shielded steel box and a remotely operated Reichert Telatom microscope housed in a lead shielded glove box is described in addition to the initial mapping of radiation levels related to the decontamination of concrete cells. The dose commitment of 17.7 mSv was ascribed to 12 persons in the 2nd half of 1991. The work resulting in these doses was mainly handling of waste together with the frogman entrances in order to repair the in-cell crane and power manipulator. The overall time schedule for the project still appears to be applicable. (AB)

  20. Development of an integrated cost model for nuclear plant decommissioning

    International Nuclear Information System (INIS)

    Amos, G.; Roy, R.

    2003-01-01

    A need for an integrated cost estimating tool for nuclear decommissioning and associated waste processing and storage facilities for Intermediate Level Waste (ILW) was defined during the authors recent MSc studies. In order to close the defined gap a prototype tool was developed using logically derived CER's and cost driver variables. The challenge in developing this was to be able to produce a model that could produce realistic cost estimates from the limited levels of historic cost data that was available for analysis. The model is an excel based tool supported by 3 point risk estimating output and is suitable for producing estimates for strategic or optional cost estimates (±30%) early in the conceptual stage of a decommissioning project. The model was validated using minimal numbers of case studies supported by expert opinion discussion. The model provides an enhanced approach for integrated decommissioning estimates which will be produced concurrently with strategic options analysis on a nuclear site

  1. 78 FR 64028 - Decommissioning of Nuclear Power Reactors

    Science.gov (United States)

    2013-10-25

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0035] Decommissioning of Nuclear Power Reactors AGENCY... the NRC's regulations relating to the decommissioning process for nuclear power reactors. The revision... Commission (NRC) is issuing Revision 1 of regulatory guide (RG) 1.184 ``Decommissioning of Nuclear Power...

  2. Evaluation of nuclear facility decommissioning projects: Summary status report: Three Mile Island Unit 2 radioactive waste and laundry shipments

    International Nuclear Information System (INIS)

    Doerge, D.H.; Haffner, D.R.

    1988-06-01

    This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 through April 19, 1987. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order

  3. Assuring the availability of funds for decommissioning nuclear reactors

    International Nuclear Information System (INIS)

    1990-08-01

    The general requirements for applications for license termination and decommissioning nuclear power, research, and test reactors are contained in 10 CFR Part 50, ''Domestic Licensing of Production and Utilization Facilities.'' On June 27, 1988, the Commission published amendments to 10 CFR Part 50 (53 FR 24018) concerning specific criteria for decommissioning nuclear facilities. Amended 10 CFR 50.33(k), 50.75, and 50.82(b) require operating license applicants and existing licensees to submit information on how reasonable assurance will be provided that funds are available to decommission the facility. Amended section 50.75 establishes requirements for indicating how this assurance will be provided, namely the amount of funds that must provided, including updates, and the methods to be used for assuring funds. This regulatory guide has been developed in conjunction with the rule amendments and was published for public comment in May 1989. This version incorporates, where appropriate, the public comments received. Its purpose is to provide guidance to applicants and licensees of nuclear power, research, and test reactors concerning methods acceptable to the NRC staff for complying with requirements in the amended rule regarding the amount of funds for decommissioning. It also provides guidance on the content and form of the financial assurance mechanisms indicated in the rule amendments. 9 refs

  4. New requirements to collect operational data that are essential for facility decommissioning

    International Nuclear Information System (INIS)

    Kristofova, K.; Valcuha, P.

    2017-01-01

    The paper describes the features of the first nuclear regulatory safety guide to be released by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in field of decommissioning. This safety guide specifies requirements to collect those nuclear facility operational data that are essential for its decommissioning. Recommendations of international organisations as well as experience in selected countries are provided. The following operational data types necessary for decommissioning process are identified and analysed: design documentation including modifications and changes during operation, photo-documentation, operational events and material and radiological inventory of the nuclear facility. The guide establishes requirements for collection of the operational data that can be recorded in interconnected database modules. In addition, a structure of decommissioning database is proposed, representing material and radiological inventory of a nuclear facility. This inventory database forms a basis for planning of the decommissioning process. At last, the guide summarises recommendations for data collection, archiving and maintenance of database records and also their applications in safety documentation necessary for decommissioning of nuclear facilities in Slovakia. (authors)

  5. Radiological characterization of nuclear plants under decommissioning

    International Nuclear Information System (INIS)

    Mincarini, M.

    1989-01-01

    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

  6. 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: 0.894, year: 2015

  7. The Reuse of Decommissioned Facilities and Sites as an Emerging Means to Alleviate the Decommissioning Burden and its Potential Applications within IAEA's International Decommissioning Network

    International Nuclear Information System (INIS)

    Laraia, M.

    2009-01-01

    Around the world, but particularly in developing Member States, there are disused nuclear facilities or those approaching the end of their useful lives, for which appropriate decommissioning steps have not been taken, primarily due to limited technical and financial resources or competing priorities. One way of alleviating the financial and social burden associated with the final shutdown and decommissioning of nuclear facilities is the redevelopment of decommissioned facilities and sites for new, productive uses, either nuclear or non-nuclear. Sustainable development implies economic development with maintenance of social and community integrity. This objective can best be served by the sensitive redevelopment of sites to provide continuity of employment and new productive activity. Finally, experience to date with redevelopment both inside and outside the nuclear field suggests that successful engagement of the stakeholders can be a key success factor in promoting outcomes which are both profitable for the operator and recognised as responsible and worthwhile by the wider community. Following a generic discussion on factors and issues inherent to the re-development of decommissioned sites, this paper expands on several examples. It is noted that experience from the non-nuclear industrial sector is much more extensive than from the nuclear sector, and lessons from this sector should not be neglected. Many of world's nuclear facilities are small and widely distributed geographically, e.g. ∼300 aging or shut-down research reactors. Requests for assistance to address this issue from Member States exceed the capability of IAEA (and others) to deliver. However, integrating individual initiative into a designed-for-purpose network may compensate for these limitations. A new IAEA initiative amongst organizations from both potential 'donor' and 'recipient' Member States has taken the form of an 'International Decommissioning Network (IDN)'. The objectives of the IDN are

  8. The brief introduction to decommissioning of nuclear reactor projects

    International Nuclear Information System (INIS)

    Zhao Shixin

    1991-01-01

    The basic concept and procedure of the decommissioning of nuclear reactor project and the three stages of decommissioning defined by IAEA are introduced. The main work of decommissioning of nuclear reactor are as following: (1) the documentary and technological preparation; (2) the site preparation of decommissioning project; (3) the dismantling of equipment piping system and components; (4) the decontamination of the piping system before and after decomminssioning; (5) the storage and disposal of the operational and decommissioning waste

  9. The brief introduction to decommissioning of nuclear reactor projects

    Energy Technology Data Exchange (ETDEWEB)

    Shixin, Zhao [Beijing Inst. of Nuclear Engineering (China)

    1991-08-01

    The basic concept and procedure of the decommissioning of nuclear reactor project and the three stages of decommissioning defined by IAEA are introduced. The main work of decommissioning of nuclear reactor are as following: (1) the documentary and technological preparation; (2) the site preparation of decommissioning project; (3) the dismantling of equipment piping system and components; (4) the decontamination of the piping system before and after decomminssioning; (5) the storage and disposal of the operational and decommissioning waste.

  10. Several issues of uranium geology exploration facilities decommissioning

    International Nuclear Information System (INIS)

    Zhang Lu; Lu Caixia; Sheng Qing; Zhuang Jingqi; Xie Shujun; Liao Yunxuan

    2013-01-01

    The environmental protection completion acceptance review work of uranium geology exploration facilities 'llth five-year plan' decommissioned and remediation projects is introduced. Some questions related to norms and standards for uranium geology exploration facilities decommissioning and remediation, scheme of decommissioning and remediation, process inspection and acceptance of project and so on are discussed, and corresponding countermeasures and suggestions are put forward, Some references can be provided for the later development of uranium geological exploration facility '12th five-year plan' decommissioning and remediation projects. (authors)

  11. Regulatory experience in nuclear power station decommissioning

    International Nuclear Information System (INIS)

    Ross, W.M.; Waters, R.E.; Taylor, F.E.; Burrows, P.I.

    1995-01-01

    In the UK, decommissioning on a licensed nuclear site is regulated and controlled by HM Nuclear Installations Inspectorate on behalf of the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to decommissioning activities and provides a continuous but flexible safety regime until there is no danger from ionising radiations. The regulatory strategy is discussed, taking into account Government policy and international guidance for decommissioning and the implications of the recent white paper reviewing radioactive waste management policy. Although each site is treated on a case by case basis as regulatory experience is gained from decommissioning commercial nuclear power stations in the UK, generic issues have been identified and current regulatory thinking on them is indicated. Overall it is concluded that decommissioning is an evolving process where dismantling and waste disposal should be carried out as soon as reasonably practicable. Waste stored on site should, where it is practical and cost effective, be in a state of passive safety. (Author)

  12. The Ministry of Dilemmas [decommissioning nuclear submarines

    International Nuclear Information System (INIS)

    Peden, W.

    1995-01-01

    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.)

  13. Waste from decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Nielsen, P.O.

    1992-05-01

    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)

  14. The decommissioning plan of the Nuclear Ship MUTSU

    International Nuclear Information System (INIS)

    Adachi, M.; Matsuo, R.; Fujikawa, S.; Nomura, T.

    1995-01-01

    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)

  15. The possibility of creating a new low power nuclear facility with slightly enriched nuclear fuel on the basis of the decommissioned IRT-M reactor intended for applied purposes

    International Nuclear Information System (INIS)

    Abramidze, Sh.P.; Katamadze, N.M.; Kiknadze, G.G.; Rostomashvili, Z.I.; Saralidze, Z.K.

    2002-01-01

    Nearly 50 years have passed since the appearance of the first nuclear research reactors. Most of them have completed their operating life and must be dismantled. But it is known that the dismantling of permanently shut down nuclear reactors is a very complex process, full realization that it generates a lot of radioactive waste (both solid and liquid), it is connected with high financial expenditures, and its solution is apparently beyond the possibilities of many countries, including Georgia In the given paper we consider a radiologically safe, ecologically clean and economically beneficial version of the decommissioning of the IRT-M nuclear research reactor and the stages of its implementation that are not connected with the dismantling of its highly radioactive technological components. We justify the possibility of creating a new Low Power Nuclear Facility on the basis of the decommissioned IRT-M reactor to solve the problems of applied nature in different fields of science and technology being very important for Georgia. (author)

  16. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

    Nuclear power plants may be decommissioned by one of three primary methods - mothballing, entombing, or dismantling, or by using combinations such as mothballing or entombing for a period of time followed by dismantling. Mothballing or entombing both result in an end-product which requires surveillance and maintenance for a significant period to ensure protection of public health and safety. This paper discusses costs for each of the decommissioning methods, including factors that will influence the method selected as well as the total costs. Decommissioning costs have been estimated for an 1100-MW(e) light-water reactor within one year after shutdown following forty years of operation. The basic economic parameters for each decommissioning method were developed using unit cost factors based on known costs of previously decommissioned reactors. Decommissioning cost estimates range from less than four million dollars for mothballing to about forty million dollars for complete dismantling. Estimated cost of entombment is about ten million dollars. Subsequent annual cost of surveillance and maintenance for a reactor facility using the mothballing or entombment method could be as high as US $200,000. Although some tooling development will be needed for removing highly activated reactor vessel segments and internals, technology is currently available and has been demonstrated on prior decommissionings, e.g. the BONUS and HALLUM reactor entombments and the Elk River Reactor complete dismantling. Costs associated with decommissioning are significant; however, allowance for them either as a one-time construction period sinking fund, or annual depreciation type operating allowance, will have little effect on construction or on operating costs. (author)

  17. Technical and economic aspects of nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Glauberman, H.; Manion, W.J.

    1977-01-01

    Nuclear power plants may be decommissioned by one of three primary methods, namely, mothballing, entombing, or dismantling or by using combinations such as mothballing or entombing for a period of time followed by dismantling. Mothballing or entombing both result in an end-product which require surveillance and maintenance for a significant period of time to ensure protection of public health and safety. This paper discusses costs for each of the decommissioning methods, including factors that will influence the method selected as well as the total costs. Decommissioning costs have been estimated for a 1100 MW(e) light water reactor within one year after shutdown following forty years of operation. The basic economic parameters for each decommissioning method were developed using unit cost factors based on known costs of previously decommissioned reactors. Decommissioning cost estimates range from less than four million dollars for mothballing to about forty million dollars for complete dismantling. Estimated cost of entombment is about ten million dollars. Subsequent annual cost of surveillance and maintenance for a reactor facility using the mothballing or entombment method could be as high as $200,000. Although some tooling development will be needed for the removal of the highly activated reactor vessel segments and internals, technology is currently available and has been demonstrated on prior decommissionings, e.g., the BONUS and HALLUM reactor entombments and the Elk River Reactor complete dismantling. Costs associated with decommissioning are significant; however, allowance for them either as a one-time construction period sinking fund or annual depreciation type operating allowance will have little impact on either construction or operating costs

  18. Decommissioning of the nuclear facilities at Risoe National Laboratory. Descriptions and cost assessment. Danish summary[Denmark]; Dekommissionering af Risoes nukleare anlaeg - vurdering af opgaver og omkostninger. Dansk sammenfatning

    Energy Technology Data Exchange (ETDEWEB)

    Lauridsen, Kurt

    2001-02-01

    The report gives a brief description of relevant aspects of the decommissioning of all nuclear facilities at Risoe National Laboratory, including the necessary operations to be performed and the associated costs. Together with a more detailed report, written in English, this report is the result of a project initiated by Risoe in the summer of 2000. The English report has undergone an international review, the results of which are summarised in the present report. (au)

  19. Site release in the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  20. Engineering and planning for decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Gans, G.M. Jr.

    1982-01-01

    With the publication of NUREG-0586, ''Draft Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities'' in January, 1981 the Nuclear Regulatory Commission staff has put the industry on notice that the termination of operating licenses and the final disposal of physical facilities will require the early consideration of several options and approaches and the preparation of comprehensive engineering and planning documents for the selected option at the end of useful life. This paper opens with a discussion of the options available and the principal aspects of decommissioning. The major emphasis of the composition is the nature of documents, the general approach to be followed, and special considerations to be taken into account when performing the detailed engineering and planning for decommissioning, as the end of life approaches and actual physical disposal is imminent. The author's main point of reference is on-going work by Burns and Roe, with Nuclear Energy Services, under contract to the Department of Energy's Richland Office, to perform the engineering and planning for the decommissioning of the Shippingport Atomic Power Station in Pennsylvania

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

    International Nuclear Information System (INIS)

    Rowden, M.A.; Fowler, S.E.

    1983-01-01

    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) [fr

  2. Decommissioning nuclear and radiation hazardous facilities at the Mining and Chemical Combine: International cooperation in assessment of impact on the environment and population health

    International Nuclear Information System (INIS)

    Lebedev, V.A.; Revenko, Y.A.; Zhidkov, V.V.

    2002-01-01

    The discharge of radionuclides to the Yenisei River has substantially reduced after shutdown of direct cycle reactors at the Mining and Chemical Combine; currently exposure dose rate above water surface and radionuclide concentration in sewage water flows do not exceed the levels set by existing sanitary rules. The results of other protection measures connected with decommissioning of nuclear- and radiation-dangerous facilities and environment restoration activity are considered in the paper. Recently, the workers of the Mining and Chemical Combine, together with specialists from other Russian institutions and with international participation, made significant progress in investigation and monitoring of the radiological impact, primarily in the Yenisei River floodplain and around the 'Severnyi' radwaste disposal site. The inventory of man-made radionuclides in flood-plain deposits of the Yenisei River was assessed and long-term radionuclide transport into the Kara Sea forecasted. New local information on radionuclide pathways to man and environment was the basis for the development of an original dosimetric model. The models of radionuclide migration in the underground liquid radwaste disposal sites have been created and associated human doses predicted. A GIS project has been developed for Yenisei River floodplain contamination. Future work will include development of M and CC ecological geoinformation cadastre and assessments of the impact of radionuclide exposure on the environment, agriculture, fishing, and water quality, as well as identification of necessary rehabilitation measures. (author)

  3. Decommissioning nuclear power plants: a case for external funding

    International Nuclear Information System (INIS)

    Hendren, C.B.

    1987-01-01

    In deciding how to finance the decommissioning of nuclear power plants, there are five basic criteria for choosing between internal and external funding methods: (1) the desire for financial assurance, (2) the cost of the assurance, (3) the degree of equity in the recovery program, (4) the program's ability to respond to changes, and (5) the program's adaptability to different utilities. To fulfill its obligations to protect long-term public interests, the Missouri Public Service Commission decided it had to assure, to the maximum extent possible, that sufficient decommissioning funds were available when needed. For this reason, it chose the external funding method. In an external fund, the money currently collected from ratepayers to cover decommissioning costs is placed in an independent trust fund comprised of low-risk investments. The funds and the interest they accrue are available to the utility only at the time of decommissioning (and only for that purpose), thus assuring a certain amount of money will be on-hand to cover decommissioning costs as they arise. Such a fund may prove critical to the financial well-being of the utility, particularly if one considers that the utility would need additional generating facilities to replace the capacity lost through the retirement of its nuclear plant. 3 references

  4. Full system chemical decontamination used in nuclear decommissioning

    International Nuclear Information System (INIS)

    Elder, George; Rottner, Bernard; Braehler, Georg

    2012-01-01

    The decommissioning of nuclear power stations at the end of the operational period of electricity generation offers technical challenges in the safe dismantling of the facility and the minimization of radioactive waste arising from the decommissioning activities. These challenges have been successfully overcome as demonstrated by decommissioning of the first generation of nuclear power plants. One of the techniques used in decommissioning is that of chemical decontamination which has a number of functions and advantages as given here: 1. Removal of contamination from metal surfaces in the reactors cooling systems. 2. Reduction of radioactive exposure to decommissioning workers 3. Minimization of metal waste by decontamination and recycling of metal components 4. Control of contamination when dismantling reactor and waste systems 5. Reduction in costs due to lower radiation fields, lower contamination levels and minimal metal waste volume for disposal. One such chemical decontamination technology was developed for the Electric Power Research Institute (EPRI) by Bradtec (Bradtec is an ONET Technologies subsidiary) and is known as the EPRI DFD system. This paper gives a description of the EPRI DFD system, and highlights the experience using the system. (orig.)

  5. Discussion on management of decommissioning funds for nuclear power plants

    International Nuclear Information System (INIS)

    Wang Hailiang

    2013-01-01

    Decommissioning funding is one of the major issues with regard to the policy and management of nuclear power. This paper describes current status of decommissioning of nuclear power plants in some foreign countries and narrates the practices in these countries on the estimation of decommissioning cost, the retrieval and management of decommissioning funds, and the guarantee of fund sufficiency. Based on a brief analysis of the status of decommissioning funding management for nuclear power plants in China, suggestions on tasks or activities needed to be carried out at present in the field of decommissioning funding are proposed. (authors)

  6. Conceptual basic and status of nuclear power plant decommissioning effort in the Russian Federation

    International Nuclear Information System (INIS)

    Glazounov, V.; Khamyanov, L.

    1998-01-01

    Decommissioning of nuclear power plants, although a usual phase in nuclear facility life cycle still has significant peculiarities due to radioactive contamination of NPP equipment and structural elements. This paper deals with the phases in decommissioning process, as follows: NPP shutdown, meaning end of commercial operation; NPP unit mothballing, radiation review of the unit to justify particular concept of decommissioning; extended hold-up, which means maintaining of contaminated equipment in the isolated zone under radiologically safe conditions; unit dismantling and burial. Status of NPP decommissioning effort in Russia is described

  7. Policy and systems analysis for nuclear installation decommissioning

    International Nuclear Information System (INIS)

    Gu Jiande

    1995-01-01

    On the basis of introducing into principal concept for nuclear installation decommissioning, form policy, sciences point of view, the author analyses present problems in the policy, the administrative and programme for decommissioning work in China. According to the physical process of decommissioning, the author studied engineering economics, derived method and formulas to estimate decommissioning cost. It is pointed out that basing on optimization principle for radiation protection and analysing cost-benefit for decommissioning engineering, the corresponding policy decision can be made

  8. Decommissioning of the Risoe Hot Cell facility

    International Nuclear Information System (INIS)

    Carlsen, H.

    1993-02-01

    A concise description of the current status (December 31st, 1992) regarding the decommissioning of the hot cell facility at Risoe National Laboratory is given in this periodic report. During the second half of the year 1992, all remaining fissile material and a large amount of contaminated material were removed, major repair work was carried out on the in-cell crane, the shielded storage facility was decontaminated and sealed, iodine filters in the cell ventilation system were removed, remote cleaning was carried out on three concrete cells to radiation levels acceptable for final cleaning by frogmen, and the remaining work schedule was planned. These processes are briefly described. Some breakdowns of older, but vital equipment (i.e. the in-cell crane and the power manipulator) that was taken into extensive use led to a certain amount of delay. The collective radiation doses during this half-year were no higher than under normal operation of the facility, and amounted to 12 man-mSv ascribed to 14 persons. It was concluded that, when removing old epoxy paint in the cells using paint strippers applied by hand, personnel can wear polythene oversuits, although a technique for remote handling has been developed. Tables illustrate measured radiation levels in cells number 1,4,5 and 6, and a diagram describes the shielded storage facility. (AB)

  9. Regulatory Strategies To Minimize Generation Of Regulated Wastes From Cleanup, Continued Use Or Decommissioning Of Nuclear Facilities Contaminated With Polychlorinated Biphenyls (PCBS) - 11198

    International Nuclear Information System (INIS)

    Lowry, N.

    2010-01-01

    . Allowable options must be evaluated carefully in order to reduce compliance risks, protect personnel, limit potential negative impacts on facility operations, and minimize the generation of wastes subject to TSCA. This paper will identify critical factors in selecting the appropriate TSCA regulatory path in order to minimize the generation of radioactive PCB waste and reduce negative impacts to facilities. The importance of communicating pertinent technical issues with facility staff, regulatory personnel, and subsequently, the public, will be discussed. Key points will be illustrated by examples from five former production reactors at the DOE Savannah River Site. In these reactors a polyurethane sealant was used to seal piping penetrations in the biological shield walls. During the intense neutron bombardment that occurred during reactor operation, the sealant broke down into a thick, viscous material that seeped out of the piping penetrations over adjacent equipment and walls. Some of the walls were painted with a PCB product. PCBs from the paint migrated into the degraded sealant, creating PCB 'spill areas' in some of these facilities. The regulatory cleanup approach selected for each facility was based on its operational status, e.g., active, inactive or undergoing decommissioning. The selected strategies served to greatly minimize the generation of radioactive liquid PCB waste. It is expected that this information would be useful to other DOE sites, DOD facilities, and commercial nuclear facilities constructed prior to the 1979 TSCA ban on most manufacturing and uses of PCBs.

  10. Cutting techniques for facilities dismantling in decommissioning projects

    International Nuclear Information System (INIS)

    Lainetti, Paulo E.O.

    2011-01-01

    Fuel cycle related activities were accomplished in IPEN-CNEN/SP in laboratory and pilot plant scale and most facilities were built in the 70-80 years. Nevertheless, radical changes of the Brazilian nuclear policy in the beginning of 90's determined the interruption of several fuel cycle activities and facilities shutdown. Some laboratory and pilot plant decommissioning activities have been performed in IPEN in the last years. During the operational activities in the decommissioning of old nuclear fuel cycle facilities, the personnel involved in the task had to face several problems. In old facilities, the need of large components dismantling and material removal use to present some difficulties, such as lack of available and near electricity supply. Besides this, the spread out of the superficial contamination in the form of dust or aerosols and the exposure of workers should be as much as possible avoided. Then, the selection and availability of suitable tools for the task, mainly those employed for cutting and segmentation of different materials is of significant importance. Slight hand tools, mainly those powered by rechargeable batteries, facilitate the work, especially in areas where the access is difficult. Based on the experience in the dismantling of some old nuclear facilities of IPEN-CNEN/SP, some tools that would have facilitated the operations were identified and their availability could have improved the quality and efficiency of different individual tasks. In this paper different cutting problems and techniques, as well as some available commercial hand tools, are presented as suggestion for future activities. (author)

  11. Access to the decision-making process: opportunities for public involvement in the facility decommissioning process of the United States Nuclear Regulatory Commission

    International Nuclear Information System (INIS)

    Cameron, F.X.

    1996-01-01

    This paper discusses recent initiatives taken by the United States Nuclear Regulatory Commission NRC) to effectively involve the public in decommissioning decisions. Initiatives discussed include the Commission's rulemaking to establish the radiological criteria for decommissioning, as well as public involvement methods that have been used on a site-by-site basis. As un example of public involvement, the NRC is currently in the process of developing generic rules on the radiological criteria for the decontamination and decommissioning of NRC-licensed sites. Not only was this proposed rule developed through an extensive and novel approach for public involvement, but it also establishes the basic provisions that will govern public involvement in future NRC decisions on the decommissioning of individual sites. The aim is to provide the public with timely information about all phases of the NRC staff to express concerns and make recommendations. Th NRC recognizes the value and the necessity of effective public involvement in its regulatory activities and has initiated a number of changes to its regulatory program to accomplish this. From the NRC's perspective, it is much easier and less costly to incorporate these mechanisms for public involvement into the regulatory program early in the process, rather than try to add them after considerable public controversy on an action has already been generated. The historical antecedents for initiatives mentioned, as well as 'lessons learned' from prior experience are also discussed. (author)

  12. Nuclear power plant decommissioning: an unresolved problem

    International Nuclear Information System (INIS)

    Pollock, C.

    1987-01-01

    In 1984, the Critical Mass Energy Project asserted that at least 11 US reactors had gone through one-third of their operating lives without collecting any decommissioning funds and that nationwide only $600 million had been collected. This lack of financial planning prompted 10 states to require mandatory periodic deposits into external accounts: California, Colorado, Connecticut, Maine, Massachusetts, Mississippi, New Hampshire, Pennsylvania, Vermont, and Wisconsin. Setting aside decommissioning funds is essential in every country that uses nuclear power. Regardless of a nation's future energy plans, existing plants must eventually be scrapped. Just as today's cities would not be habitable without large fleets of garbage trucks and extensive landfills, the international nuclear industry is not viable without a sound decommissioning strategy. Thirty years after the first nuclear plant started producing electricity, such a strategy has yet to be formulated. More than 500 reactors, including those currently under construction, will have to be decommissioned. Preparing to safely retire these plants requires aggressive, well-funded research and development programs, policy makers willing to tackle unpleasant, long-term problems, and robust retirement accounts funded by today's utility customers

  13. Nuclear fuel cycle facilities, laboratories, irradiators, particle accelerators, under-decommissioning reactors and radioactive waste management facilities safety. Lessons learned from events notified between 2005 and 2008

    International Nuclear Information System (INIS)

    2001-01-01

    Maintaining high levels of safety in nuclear facilities requires constant vigilance by everyone involved, especially by plant operators who are first and foremost responsible for safety in their facilities. Safety can never be taken for granted; constant efforts must be made to improve it, by taking new knowledge and available operating feedback into account. In this respect, a substantial part of operating feedback is made up of lessons learned from analysing events, incidents or accidents occurring in France or in similar facilities abroad. To encourage the diffusion of operating feedback, IRSN has produced a report concerning events notified to the Nuclear Safety Authority (ASN) by operators of LUDD facilities between 2005 and 2008. The main objective is to make general lessons for safety in this type of facility available based on a cross-disciplinary analysis of notified events and noted evolution trends. IRSN has had tools for managing information concerning events occurring in France and abroad for many years. These tools are used to analyse the events in order to take into account the relevant lessons learned in the safety assessments performed on behalf of ASN and also to define study and research programmes to maintain its expertise and expand its knowledge. The report has 4 sections: - the first section (chapters 2 to 4) presents the LUDD facilities so that the facilities themselves, their diversity and the main associated risks can be better understood. It also includes a brief reminder of plant operator obligations in notifying events and describes the database used by the Institute to manage the data relating to the notified events; - the second section (chapter 5) summarises the main changes noted in the events notified to ASN during 2005 to 2008 and provides an overall assessment of the consequences of these events for the environment, the population and the workers; - the third section (chapter 6) describes significant events occurring in France

  14. Decommissioning the UHTREX Reactor Facility at Los Alamos, New Mexico

    International Nuclear Information System (INIS)

    Salazar, M.; Elder, J.

    1992-08-01

    The Ultra-High Temperature Reactor Experiment (UHTREX) facility was constructed in the late 1960s to advance high-temperature and gas-cooled reactor technology. The 3-MW reactor was graphite moderated and helium cooled and used 93% enriched uranium as its fuel. The reactor was run for approximately one year and was shut down in February 1970. The decommissioning of the facility involved removing the reactor and its associated components. This document details planning for the decommissioning operations which included characterizing the facility, estimating the costs of decommissioning, preparing environmental documentation, establishing a system to track costs and work progress, and preplanning to correct health and safety concerns in the facility. Work to decommission the facility began in 1988 and was completed in September 1990 at a cost of $2.9 million. The facility was released to Department of Energy for other uses in its Los Alamos program

  15. Prioritisation process for decommissioning of the Iraq former nuclear complex

    International Nuclear Information System (INIS)

    Jarjies, Adnan; Abbas, Mohammed; Fernandes, Horst M.; Coates, Roger

    2008-01-01

    There are a number of sites in Iraq which have been used for nuclear activities and which contain potentially significant amounts of radioactive waste. The principal nuclear site is Al-Tuwaitha, the former nuclear research centre. Many of these sites suffered substantial physical damage during the Gulf Wars and have been subjected to subsequent looting. All require decommissioning in order to ensure both radiological and non-radiological safety. However, it is not possible to undertake the decommissioning of all sites and facilities at the same time. Therefore, a prioritization methodology has been developed in order to aid the decision-making process. The methodology comprises three principal stages of assessment: 1) a quantitative surrogate risk assessment, 2) a range of sensitivity analyses and 3) the inclusion of qualitative modifying factors. A group of five Tuwaitha facilities presented the highest evaluated risk, followed by a middle ranking grouping of Tuwaitha facilities and some other sites, with a relatively large number of lower risk facilities and sites comprising a third group. This initial risk-based order of priority is changed when modifying factors are taken into account. It is necessary to take account of Iraq's isolation from the international nuclear community over the last two decades and the lack of experienced personnel. Therefore it is appropriate to initiate decommissioning operations on selected low risk facilities at Tuwaitha in order to build capacity/experience and prepare for work to be carried out in more complex and potentially high hazard facilities. In addition it is appropriate to initiate some prudent precautionary actions relating to some of the higher risk facilities. (author)

  16. Decommissioning of the nuclear facilities-radio-isotope thermo-electrical generators in the Republic of Tajikistan

    International Nuclear Information System (INIS)

    Mirsaidov, U.; Kamalov, D.

    2010-01-01

    One of peaceful uses of the nuclear energy is the production of electrical energy by using the phenomenon of fission of radioactive strontium in the radio-isotope thermo-electrical generators (RITEGs) to supply with energy lighthouses, radio-lighthouses and radio meteorological stations. They are installed in the remote territories far from the people’s dwellings and do not require presence of the personnel to maintain them. Republic of Tajikistan as other republics of the ex-Soviet Union used the radio isotope thermo- electrical generators (RITEGs) as sources for autonomous hydro- and meteorological navigational equipment, which was placed in the hard-to-reach mountainous regions. In the ex-Soviet Union, the RITEGs were under constant surveillance. But, after the breakup of the Soviet Union, hundreds of these small devices equipped with powerful sources of radiation remained out of control. Radioactive substance contained in them may be easily used as a source of radiation dispersion. By applying Strontium-90 as a material for a bomb one can disperse this radioactive substance after exploding the bomb. Having exploded one of such “dirty bombs” a terrorist may contaminate several cities by the radioactive materials. It was determined that there are around 1 000 RITEGs on the territory of the Russian Federation and approximately 30- on the territory of other states. It is presumed that approximately 1500 RITEGs were manufactured in the USSR. The exploitation period of all the RITEGs is around 10 years. At present, all the RITEGs which were in circulation have finalized their functionality period and should be withdrawn from the utilization. In Tajikistan, Tajikhydromet is the user of the RITEGs. The manufacturer of the RITEGs, according to the documentation, was the All-Russian Institute of Technological Physics and Automation in Moscow. The documents were sent to the plant-producer. According to the unofficial sources, during the times of the Soviet Union 15

  17. Procedure of uranium mine and mill facilities decommissioning work

    International Nuclear Information System (INIS)

    Li Renjie

    1995-01-01

    The procedure of decommissioning work of uranium mine and mill facilities includes three stages: preparation, on-the-spot construction and acceptance after being completed. The first stage, preparation, is discussed in detail, and it is presented to take the measures of strengthening leadership and improving leading body to conduct the decommissioning work best

  18. Decommissioning and disposal of foreign uranium mine and mill facilities

    International Nuclear Information System (INIS)

    Pan Yingjie; Xue Jianxin; Yuan Baixiang; Xu Lechang

    2012-01-01

    Disposal techniques in decommissioning of foreign uranium mine and mill facilities are systematically discussed, including covering of uranium tailing impoundment, drainaging and consolidation of uranium tailing, and treatment of mining waste water and polluted groundwater, and the costs associated with disposal are analyzed. The necessity of strengthening the decommissioning disposal technology research and international exchanges and cooperation is emphasized. (authors)

  19. Draft principles, policy, and acceptance criteria for decommissioning of U.S. Department of Energy contaminated surplus facilities and summary of international decommissioning programs

    International Nuclear Information System (INIS)

    Singh, B.K.

    1994-12-01

    Decommissioning activities enable the DOE to reuse all or part of a facility for future activities and reduce hazards to the general public and any future work force. The DOE Office of Environment, Health and Safety has prepared this document, which consists of decommissioning principles and acceptance criteria, in an attempt to establish a policy that is in agreement with the NRC policy. The purpose of this document is to assist individuals involved with decommissioning activities in determining their specific responsibilities as identified in Draft DOE Order 5820.DDD, ''Decommissioning of US Department of Energy Contaminated Surplus Facilities'' (Appendix A). This document is not intended to provide specific decommissioning methodology. The policies and principles of several international decommissioning programs are also summarized. These programs are from the IAEA, the NRC, and several foreign countries expecting to decommission nuclear facilities. They are included here to demonstrate the different policies that are to be followed throughout the world and to allow the reader to become familiar with the state of the art for environment, safety, and health (ES and H) aspects of nuclear decommissioning

  20. Implementation of decommissioning criteria in the conceptual design of the MRS facility

    International Nuclear Information System (INIS)

    Gross, D.L.; Wilcox, A.D.; Huang, S.

    1986-01-01

    The US Department of Energy (DOE) selected the Ralph M. Parsons Company (RMP) to prepare the conceptual design of the Monitored Retrievable Storage (MRS) Facility. The purpose of this facility is to consolidate and temporarily store spent fuel from civilian nuclear power plants. In addition, it will overpack, handle, and store high-level radioactive waste from non-defense related sources. The Functional Design Criteria (FDC) prepared by Pacific Northwest Laboratories, as well as 10 CFR 72, requires the facility to be designed for decommissioning, with provisions to facilitate decontamination of structures and equipment to minimize the volume of radioactive wastes and contaminated equipment at the time of decommissioning. Many problems associated with decommissioning a nuclear facility have been identified in recent years and the design for the MRS Facility presents a unique opportunity for RMP to implement decommissioning criteria into the conceptual design of a major nuclear facility. The provisions made in the design to facilitate decommissioning include good housekeeping during operations, controlled personnel access, access for equipment removal, equipment design, installed radiation monitors, adequate work space, installed decontamination systems and areas, control of all effluents, and operational documentation. These topics will be the major points of discussion for this paper

  1. Lessons learned from decontaminating and decommissioning fuel cycle facilities in France

    International Nuclear Information System (INIS)

    Bordier, Jean-Claude; Dalcorso, J. P.; Nokhamzon, Jean-Guy

    2000-01-01

    This paper draws on 20 years of experience and lessons learned by COGEMA and the CEA during the decontamination and decommissioning (DandD) of its nuclear fuel cycle facilities. COGEMA and the CEA have developed a wealth of knowledge on issues such as assessing decommissioning alternatives, selecting appropriate technical procedures on the basis of thorough site characterization, and developing waste management and disposal procedures. (author)

  2. Testing and Performance Validation of a Sensitive Gamma Ray Camera Designed for Radiation Detection and Decommissioning Measurements in Nuclear Facilities-13044

    Energy Technology Data Exchange (ETDEWEB)

    Mason, John A.; Looman, Marc R.; Poundall, Adam J.; Towner, Antony C.N. [ANTECH, A. N. Technology Ltd., Unit 6, Thames Park, Wallingford, Oxfordshire, OX10 9TA (United Kingdom); Creed, Richard; Pancake, Daniel [Argonne National Laboratory, 9700 South Cass Avenue, Lemont, IL 60439 (United States)

    2013-07-01

    This paper describes the measurements, testing and performance validation of a sensitive gamma ray camera designed for radiation detection and quantification in the environment and decommissioning and hold-up measurements in nuclear facilities. The instrument, which is known as RadSearch, combines a sensitive and highly collimated LaBr{sub 3} scintillation detector with an optical (video) camera with controllable zoom and focus and a laser range finder in one detector head. The LaBr{sub 3} detector has a typical energy resolution of between 2.5% and 3% at the 662 keV energy of Cs-137 compared to that of NaI detectors with a resolution of typically 7% to 8% at the same energy. At this energy the tungsten shielding of the detector provides a shielding ratio of greater than 900:1 in the forward direction and 100:1 on the sides and from the rear. The detector head is mounted on a pan/tile mechanism with a range of motion of ±180 degrees (pan) and ±90 degrees (tilt) equivalent to 4 π steradians. The detector head with pan/tilt is normally mounted on a tripod or wheeled cart. It can also be mounted on vehicles or a mobile robot for access to high dose-rate areas and areas with high levels of contamination. Ethernet connects RadSearch to a ruggedized notebook computer from which it is operated and controlled. Power can be supplied either as 24-volts DC from a battery or as 50 volts DC supplied by a small mains (110 or 230 VAC) power supply unit that is co-located with the controlling notebook computer. In this latter case both power and Ethernet are supplied through a single cable that can be up to 80 metres in length. If a local battery supplies power, the unit can be controlled through wireless Ethernet. Both manual operation and automatic scanning of surfaces and objects is available through the software interface on the notebook computer. For each scan element making up a part of an overall scanned area, the unit measures a gamma ray spectrum. Multiple

  3. Testing and Performance Validation of a Sensitive Gamma Ray Camera Designed for Radiation Detection and Decommissioning Measurements in Nuclear Facilities-13044

    International Nuclear Information System (INIS)

    Mason, John A.; Looman, Marc R.; Poundall, Adam J.; Towner, Antony C.N.; Creed, Richard; Pancake, Daniel

    2013-01-01

    This paper describes the measurements, testing and performance validation of a sensitive gamma ray camera designed for radiation detection and quantification in the environment and decommissioning and hold-up measurements in nuclear facilities. The instrument, which is known as RadSearch, combines a sensitive and highly collimated LaBr 3 scintillation detector with an optical (video) camera with controllable zoom and focus and a laser range finder in one detector head. The LaBr 3 detector has a typical energy resolution of between 2.5% and 3% at the 662 keV energy of Cs-137 compared to that of NaI detectors with a resolution of typically 7% to 8% at the same energy. At this energy the tungsten shielding of the detector provides a shielding ratio of greater than 900:1 in the forward direction and 100:1 on the sides and from the rear. The detector head is mounted on a pan/tile mechanism with a range of motion of ±180 degrees (pan) and ±90 degrees (tilt) equivalent to 4 π steradians. The detector head with pan/tilt is normally mounted on a tripod or wheeled cart. It can also be mounted on vehicles or a mobile robot for access to high dose-rate areas and areas with high levels of contamination. Ethernet connects RadSearch to a ruggedized notebook computer from which it is operated and controlled. Power can be supplied either as 24-volts DC from a battery or as 50 volts DC supplied by a small mains (110 or 230 VAC) power supply unit that is co-located with the controlling notebook computer. In this latter case both power and Ethernet are supplied through a single cable that can be up to 80 metres in length. If a local battery supplies power, the unit can be controlled through wireless Ethernet. Both manual operation and automatic scanning of surfaces and objects is available through the software interface on the notebook computer. For each scan element making up a part of an overall scanned area, the unit measures a gamma ray spectrum. Multiple radionuclides may be

  4. BNFL nuclear decommissioning liabilities management program

    International Nuclear Information System (INIS)

    Colquhoun, A.P.

    1995-01-01

    The objective of this paper is to describe BNFL's policy and strategy for decommissioning and also to summarize the overall scope of nuclear liabilities in the wider field of waste retrieval and storage, as well as the dismantling and demolition aspects of decommissioning. BNFL's recently established organisational arrangements for discharging all types of these liabilities are explained, together with a review of practical progress in dealing with them. Organisational changes in recent years have amalgamated decommissioning work with operations covering waste storage and retrieval operations. A strategy of minimising residual activity in shutdown plants is pursued, followed by dismantling and demolition on appropriate time scales to minimise risk and cost. Since April 1995, a new BNFL subsidiary, Nuclear Liabilities Management Company Limited has taken responsibility for discharge of BNFL's Waste Retrieval and Decommissioning liabilities on all BNFL sites. NLM has the objectives of optimal and lowest cost management of liabilities and much clearer segregation of physical operations from project specification and planning. The Ministry of Defense (MoD) policy, strategy, work programmes and progress for the Atomic Weapons Establishment (AWE) are also outlined. MoD/AEA has established an equivalent strategy for dealing with its liabilities. (J.S.). 5 refs., 2 figs., 4 appends

  5. UK safety and standards for radioactive waste management and decommissioning on nuclear licensed sites

    International Nuclear Information System (INIS)

    Mason, D.J.

    2001-01-01

    This paper discusses the regulation of radioactive waste and decommissioning in the United Kingdom and identifies the factors considered by HM Nuclear Installations Inspectorate in examining the adequacy arrangements for their management on nuclear licensed sites. The principal requirements are for decommissioning to be undertaken as soon as reasonably practicable and that radioactive wastes should be minimised, disposed of or contained and controlled by storage in a passively safe form. However, these requirements have to be considered in the context of major organisational changes in the UK nuclear industry and the non-availability of disposal routes for some decommissioning wastes. The legislative framework used to regulate decommissioning of nuclear facilities in the UK is described. Reference is made to radioactive waste and decommissioning strategies, quinquennial reviews criteria for delicensing and the forthcoming Environmental Impact Assessment Regulations. (author)

  6. KONTEC 2013. 11{sup th} international symposium on 'Conditioning of radioactive operational and decommissioning waste' and 11{sup th} BMBF status report on 'Decommissioning and demolition of nuclear facilities'; KONTEC 2013. 11. internationales Symposium 'Konditionierung radioaktiver Betriebs- und Stilllegungsabfaelle' einschliesslich 11. Statusbericht des BMBF 'Stilllegung und Rueckbau kerntechnischer Anlagen'. Veranstaltungsbericht

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2013-06-15

    KONTEC 2013 was held in Dresden on 13 to 15 March 2013. The 11{sup th} event organized under this heading dealt with the subjects of 'Conditioning of Radioactive Operational and Decommissioning Waste' and 'Decommissioning and Demolition of Nuclear Facilities' including the R and D Status Report by the Federal Ministry of Education and Research (BMBF) on the same subject. The conference was attended by an international audience from 19 countries. The program included plenary sessions on these 4 key topics: - Disposal of Radioactive Residues from Nuclear Facilities' Operation and Decommissioning. - Decommissioning and Dismantling of Nuclear Facilities. - Facilities and Systems for the Conditioning of Operational and Decommissioning Wastes. - Transport, Interim and Final Storage of Non-heat Generating Wastes (i.e. Konrad). These sessions were accompanied by poster sessions and short presentations under the heading of 'Kontec Direct.' The best presentations of the categories Plenary Session Presentation, Poster Presentation and Kontec-Direct have been awarded. In detail, 'Dismantling of Russian nuclear powered submarines' by Detlef Mietann, 'Requalification of 'Old Packages' for the Konrad Repository Described for the Model Case of Packages from Storage Annex A and Repackaging of Containers Holding Compacts in Hall 2 of the GNS Plant' by Martina Koessler, Sebastian Schwall and Pascal Budriks, and 'Electrochemical process development for cleaning organic, C-14-labelled waste solutions' by Hans-Juergen Friedrich. (orig.)

  7. Shutdown, dismantling and decommissioning of nuclear facilities in France - Guide no. 6 - Update of 30/08/2016

    International Nuclear Information System (INIS)

    2016-01-01

    After a recall of the regulatory context and references, this guide addresses the strategy for an immediate dismantling of an installation, the dismantling planning, the different phases of the end of life of nuclear base installations, the authorization of definitive stop and dismantling, the preliminary phase preparing the definitive stop (regulatory context, technical aspects), the dismantling phase (regulatory context, technical aspects for the concerned operations, the security functions, hardware important for security, taking ageing into account), and the final status of installations (downgrading, constraints)

  8. Practical decommissioning experience with nuclear installations in the European Community

    International Nuclear Information System (INIS)

    Skupinski, E.

    1993-01-01

    Initiated by the Commission of the European Communities (CEC), this seminar was jointly organized by Kernkraftwerke RWE Bayernwerk GmbH (KRB) and the CEC at Gundremmingen-Guenzburg (D), where the former KRB-A BWR is presently being dismantled. The meeting aimed at gathering a limited number of European experts for the presentation and discussion of operations, the results and conclusions on techniques and procedures presently applied in the dismantling of large-scale nuclear installations in the European Community. Besides the four pilot dismantling projects of the presently running third R and D programme (1989-93) of the European Community on decommissioning of nuclear installations (WAGR, BR-3 PWR, KRB-A BWR and AT-1 FBR fuel reprocessing), the organizers selected the presentation of topics on the following facilities which have a significant scale and/or representative features and are presently being dismantled: the Magnox reprocessing pilot plant at Sellafield, the HWGCR EL4 at Monts d'Arree, the operation of an on-site melting furnace for G2/G3 GCR dismantling waste at Marcoule, an EdF confinement conception of shut-down LWRs for deferred dismantling, and the technical aspects of the Greifswald WWER type NPPs decommissioning. This was completed by a presentation on the decommissioning of material testing reactors in the United Kingdom and by an overview on the conception and implementation of two EC databases on tools, costs and job doses. The seminar concluded with a guided visit of the KRB-A dismantling site. This meeting was attended by managers concerned by the decommissioning of nuclear installations within the European Community, either by practical dismantling work or by decision-making functions. Thereby, the organizers expect to have contributed to the achievement of decommissioning tasks under optimal conditions - with respect to safety and economics - by making available a complete and updated insight into on-going dismantling projects and by

  9. Nuclear Energy Agency task group on Radiological Characterisation for Decommissioning of Nuclear Installations

    International Nuclear Information System (INIS)

    Larsson, Arne; Weber, Inge

    2016-01-01

    Radiological characterisation plays a significant role in the process of decommissioning of shut-down nuclear facilities in order to ensure the protection of the environment and radiation safety. At all stages of a decommissioning programme or project, adequate radiological characterisation is of crucial importance, not least from a material and waste perspective. The radiological characterisation is a key element for planning, controlling and optimising decommissioning and dismantling activities. Experience has shown that data and information from the operation of a facility can - supplemented by recently collected and analysed data and information - be of crucial importance for decisions on waste management and for characterisation of radioactive waste. Once the dismantling has been done, some information may be hard, costly or even impossible to obtain later in the waste management process. This was the reason why the Working Party on Decommissioning and Dismantling (WPDD) of the OECD Nuclear Energy Agency (NEA) decided in late 2013 to extend the mandate of the Task Group on Radiological Characterisation and Decommissioning (TGRCD) for a second phase focusing on nuclear facility characterisation from a waste and material end-state perspective whereas the first phase focused on overall strategies of radiological characterisation. This paper gives an overview of the activities and findings within both phases up to now. (authors)

  10. Remediation and decommissioning of radioactive waste facilities in Estonia

    International Nuclear Information System (INIS)

    Putnik, H.; Realo, E.

    2001-01-01

    Full text: The nuclear training facility at Paldiski was constructed in the early 1960's by the former USSR Navy. The hull sections of Delta and Echo class submarines each housing a full-sized ship reactor were installed in the main building of the site for training of navy personnel in safe operation of the submarine nuclear reactor systems. The first reactor was commissioned in 1968 and the second in 1982, while both was shut down in 1989. After Estonia's reproclamation of independence in 1991 the responsibility for the clean up and decommissioning of the Paldiski site became a subject of negotiations between Russia and Estonia. As the result Estonia took the ownership and control of the site in September 1995. Before the take over the Russian authorities defuelled the reactors and transported the spent fuel to Russia, dismantled the hull sections not related with reactor systems, seal-welded the hull sections housing the reactor vessels with their primary circuitry and enclosed those in reinforced concrete sarcophagi. The auxiliary facilities and radioactive waste were left intact. Main goals of the Conceptual Decommissioning Plan for the Paldiski facilities, developed under the auspices of the Paldiski International Expert Reference Group (Pier, a group established at the request of the Estonian government to advise local authorities to maintain the decommissioning and waste management at Paldiski) were defined as following: Establishing the waste management system and a long term monitored