Safety problems in decommissioning of nuclear power plants

International Nuclear Information System (INIS)

1975-12-01

The safety problems in decommissioning are presented by the example of light water reactors with an electric power of 1300 MW and 40 years of preceding specified operation. In such a plant the radioactivity in the form of activation and contamination is of the order of 10 7 Ci one year after final shut-down. The fuel elements are not taken into account. During the work at the reactor vessel dose rates of some 10 4 rem/h may occur at the flange level. According to a rough estimation the dose accumulated by the decommissioning personnel during dismantling of the radioactive components amounts to 1200 rem. During the decommissioning work the problems are caused predominantly by the direct radiation from the radioactive components and systems as well as from the release of radioactive particles, aerosols and liquids on cutting them up. In designing new plants the extent of later decommissioning problems can be reduced above all by selection of suitable materials and by decommissioning-minded design and arrangement of the components and parts of the plant. (orig./RW) [de

Safety analysis report for decommissioning of KNPP units 1 and 2

International Nuclear Information System (INIS)

Ivanova, A.; Ovcharova, I.

2008-01-01

At present units 1 and 2 possess a license for operation in mode „E‟ – storage of the spent fuel in the spent fuel pools. According to the order of BNSA, from the beginning of December 2006 the licenses for operation of KNPP units 1 and 2 have been modified; this does not change the current status – operation of the units in mode „E‟ , but allows for dismantling of the systems and equipment, which are not important for safety and do not contain radioactive substances above the free release levels. The next step is obtaining a licence for Stage 1 decommissioning activities – Safe enclosure (SE) and dismantling in Turbine hall. The development of Decommissioning Safety Analysis Report (DSAR) is one of the documents needed for this license. The specific features of the units and decommitioning options are described

Safety in decommissioning of research reactors

International Nuclear Information System (INIS)

1986-01-01

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

Safety of nuclear fuel cycle facilities. Safety requirements

International Nuclear Information System (INIS)

2008-01-01

This publication covers the broad scope of requirements for fuel cycle facilities that, in light of the experience and present state of technology, must be satisfied to ensure safety for the lifetime of the facility. Topics of specific reference include aspects of nuclear fuel generation, storage, reprocessing and disposal. Contents: 1. Introduction; 2. The safety objective, concepts and safety principles; 3. Legal framework and regulatory supervision; 4. The management system and verification of safety; 5. Siting of the facility; 6. Design of the facility; 7. Construction of the facility; 8. Commissioning of the facility; 9. Operation of the facility; 10. Decommissioning of the facility; Appendix I: Requirements specific to uranium fuel fabrication facilities; Appendix II: Requirements specific to mixed oxide fuel fabrication facilities; Appendix III: Requirements specific to conversion facilities and enrichment facilities

Preliminary plan for decommissioning - repository for spent nuclear fuel; Preliminaer plan foer avveckling - slutfoervar foer anvaent kaernbraensle

Energy Technology Data Exchange (ETDEWEB)

Hallberg, Bengt; Tiberg, Liselotte (Studsvik Nuclear AB, Nykoeping (Sweden))

2010-06-15

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

Safety case methodology for decommissioning of research reactors. Assessment of the long term impact of a flooding scenario

International Nuclear Information System (INIS)

Vladescu, G.; Banciu, O.

1999-01-01

The paper contains the assessment methodology of a Safety Case fuel decommissioning of research reactors, taking into account the international approach principles. The paper also includes the assessment of a flooding scenario for a decommissioned research reactor (stage 1 of decommissioning). The scenario presents the flooding of reactor basement, radionuclide migration through environment and long term radiological impact for public. (authors)

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

General principles of nuclear safety management related to research reactor decommissioning

International Nuclear Information System (INIS)

Banciu, Ortenzia; Vladescu, Gabriela

2003-01-01

The paper contents the general principles applicable to the decommissioning of research reactors to ensure a proper nuclear safety management, during both decommissioning activities and post decommissioning period. The main objective of decommissioning is to ensure the protection of workers, population and environment against all radiological and non-radiological hazards that could result after a reactor shutdown and dismantling. In the same time, it is necessary, by some proper provisions, to limit the effect of decommissioning for the future generation, according to the new Romanian, IAEA and EU Norms and Regulations. Assurance of nuclear safety during decommissioning process involves, in the first step, to establish of some safety principles and requirements to be taken into account during whole process. In the same time, it is necessary to perform a series of analyses to ensure that the whole process is conducted in a planned and safe manner. The general principles proposed for a proper management of safety during research reactor decommissioning are as follows: - Set-up of all operations included in a Decommissioning Plan; - Set-up and qualitative evaluation of safety problems, which could appear during normal decommissioning process, both radiological and nonradiological risks for workers and public; - Set-up of accident list related to decommissioning process the events that could appear both due to some abnormal working conditions and to some on-site and off-site events like fires, explosions, flooding, earthquake, etc.); - Development and qualitative/ quantitative evaluation of scenarios for each incidents; - Development (and evaluation) of safety indicator system. The safety indicators are the most important tools used to assess the level of nuclear safety during decommissioning process, to discover the weak points and to establish safety measures. The paper contains also, a safety case evaluation (description of facility according to the decommissioning

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

Cost update: Technology, safety, and costs of decommissioning reference independent spent fuel storage installations

International Nuclear Information System (INIS)

Miles, T.L.

1994-07-01

The cost estimates originally developed in NUREG/CR-2210 for decommissioning five conceptual Independent Spent Fuel Storage Installations (ISFSIs) and their supporting ancillaries (hot cell and transporter) are updated from 1981 to 1993 dollars. The costs for labor and materials increased approximately at the rate of inflation, the cost of energy increased more slowly than the rate of inflation, and the cost of low-level radioactive waste disposal increased much more rapidly than the rate of inflation. A methodology and a formula are presented for estimating the cost of decommissioning the ISFSIs at some future time, based on these current cost estimates. The formula contains essentially the same elements as the formula given in 10 CFR 50.75 for escalating the decommissioning costs for nuclear power reactors to some future time

Review of decommissioning, spent fuel and radwaste management in Slovakia

International Nuclear Information System (INIS)

Jamrich, J.

2000-01-01

Two nuclear power plants with two WWER reactors are currently under operation in Jaslovske Bohunice and NPP A-1 is under decommissioning on the same site. At the second nuclear site in the Slovak Republic in Mochovce third nuclear power plant with two units is in operation. In accordance with the basic Slovak legislation (Act on Peaceful Utilisation of Nuclear Energy) defining the responsibilities, roles and authorities for all organisations involved in the decommissioning of nuclear installations Nuclear Regulatory Authority requires submission of conceptual decommissioning plans by the licensee. The term 'decommissioning' is used to describe the set of actions to be taken at the end of the useful life of a facility, in order to retire the facility from service while, simultaneously, ensuring proper protection of the workers, the general public and the environment. This set of activities is in principle comprised of planning and organisation of decommissioning inclusive strategy development, post-operational activities, implementation of decommissioning (physical and radiological characterisation, decontamination, dismantling and demolition, waste and spent fuel management), radiological, aspects, completion of decommissioning as well as ensuring of funding for these activities. Responsibility for nuclear installations decommissioning, radwaste and spent fuel, management in Slovakia is with a subsidiary of Slovak Electric called Nuclear Installations Decommissioning Radwaste and Spent Fuel Management (acronym SE VYZ), established on January 1, 1996. This paper provides description of an approach to planning of the NPP A-1 and NPPs with WWER reactors decommissioning, realisation of treatment, conditioning and disposal of radwaste, as well as spent fuel management in Slovakia. It takes into account that detail papers on all these issues will follow later during this meeting. (author)

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

Transforming criticality control methods for EBR-II fuel handling during reactor decommissioning

International Nuclear Information System (INIS)

Eberle, C.S.; Dean, E.M.; Angelo, P.L.

1995-01-01

A review of the Department of Energy (DOE) request to decommission the Experimental Breeder Reactor-II (EBR-II) was conducted in order to develop a scope of work and analysis method for performing the safety review of the facility. Evaluation of the current national standards, DOE orders, EBR-II nuclear safeguards and criticality control practices showed that a decommissioning policy for maintaining criticality safety during a long term fuel transfer process did not exist. The purpose of this research was to provide a technical basis for transforming the reactor from an instrumentation and measurement controlled system to a system that provides both physical constraint and administrative controls to prevent criticality accidents. Essentially, this was done by modifying the reactor core configuration, reactor operations procedures and system instrumentation to meet the safety practices of ANS-8.1-1983. Subcritical limits were determined by applying established liquid metal reactor methods for both the experimental and computational validations

Code on the safety of civilian nuclear fuel cycle installations

International Nuclear Information System (INIS)

1996-01-01

The 'Code' was promulgated by the National Nuclear Safety Administration (NSSA) on June 17, 1993, which is applicable to civilian nuclear fuel fabrication, processing, storage and reprocessing installations, not including the safety requirements for the use of nuclear fuel in reactors. The contents of the 'Code' involve siting, design, construction, commissioning, operation and decommissioning of fuel cycle installation. The NNSA shall be responsible for the interpretation of this 'Code'

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 )

Safety culture and organizational issues during transition from operation to decommissioning of NPPs

International Nuclear Information System (INIS)

Slavcheva, K.; Mori, M.; D'Amico, N.; Sollima, C.

2005-01-01

The paper highlights the critical safety issues in a Nuclear Power Plant (NPP) to be managed during the transition period from operation to decommissioning. Pre-shutdown is an important period of a NPP lifetime due to the changes and issues to be faced by the NPP management, which include safety culture issues, organizational issues, plant safety issues and nuclear waste issues. Preservation of staff competence and moral, management and organizational capability, preservation of knowledge and corporate memory, preservation of safety culture, surveillance and permanent control to maintain adequate level of nuclear and radiation safety, development of appropriate solutions for the new incoming issues are the key challenges to be timely faced. The uncertainty regarding the future of the site, the future of the workers and the incoming re-organization originate numerous additional issues including stress for the personnel. It is necessary to take appropriate actions to reduce the uncertainty. The regulatory regime continues with the same rules as during operation. Responsibility for safety remains with the licensee and the regulatory supervision continues and oversees the safe operation and security of the NPP, the safe management and storage of spent nuclear fuel and radioactive waste. Anticipated attention from the Operator and the Regulator to key organizational and safety culture issues during the pre-shutdown phase has shown to be an effective preventive action. The Operator has to aim to preserve staff competence and motivation, preserve corporate memory, safety culture, reinforce monitoring and control on the health risk of workers and population, preserve the technical part of the organization from external disturb and distractions, ensure transparency and develop strategies to solve forthcoming issues. The Regulator has to aim to reorient its supervision, train its personnel and adapt its tools to the new situation, keep adequate presence onsite, keep dialogue

Decommissioning of a mixed oxide fuel fabrication facility

International Nuclear Information System (INIS)

Buck, S.; Colquhoun, A.

1990-01-01

Decommissioning of the coprecipitation plant, which made plutonium/uranium oxide fuel, is a lead project in the BNFL Sellafield decommissioning programme. The overall programme has the objectives of gaining data and experience in a wide range of decommissioning operations and hence in this specific project to pilot the decommissioning of plant heavily contaminated with plutonium and other actinides. Consequently the operations have been used to test improvements in temporary containment, contamination control and decontamination methods and also to develop in situ plutonium assay, plutonium recovery and size-reduction methods. Finally the project is also yielding data on manpower requirements, personnel radiation uptake and waste arisings to help in the planning of future decommissioning projects

Radiation safety for decommissioning projects

International Nuclear Information System (INIS)

Ross, A.C.

1999-01-01

Decommissioning of redundant nuclear facilities is a growth area in the UK at the present time. NUKEM Nuclear Limited is a leading-edge nuclear decommissioning and waste management contractor (with its own in-house health physics and safety department), working for a variety of clients throughout the UK nuclear industry. NUKEM Nuclear is part of the prestigious, international NUKEM group, a world-class organization specializing in nuclear engineering and utilities technologies. NUKEM Nuclear is involved in a number of large, complex decommissioning projects, both in its own right and as part of consortia. This paper explores the challenges presented by such projects and the interfaces of contractor, client and subcontractors from the point of view of a radiation protection adviser. (author)

Development of a harmonized approach to safety assessment of decommissioning: Lessons learned from international experience (DeSa project)

International Nuclear Information System (INIS)

Percival, K.; Nokhamzon, J.-G.; Ferch, R.; Batandjieva, B.

2006-01-01

The number of nuclear facilities being or planned to be shutdown as they reach the end of their design life, due to accidents or other political and social factors has been increasing worldwide. This has led to an increase in the awareness of regulators and operators of the importance of development and implementation of adequate safety requirements and criteria for decommissioning of these facilities. A general requirement at international and national levels, even for new facilities to be commissioned, is the development of a decommissioning plan, which includes evaluation of potential radiological consequences to public and workers during planned and accidental decommissioning activities. Experience has been gained in the safety assessment of decommissioning at various sites with different complexities and hazard potentials. This experience shows that various approaches have been used in conducting safety assessments and that there is a need for harmonisation of these approaches and for transferring the good practice and lessons learned to other countries, in particular developing countries with limited financial and human resources. The IAEA launched an international project on Evaluation and Demonstration of Safety during Decommissioning (DeSa) in 2004 to provide a forum for exchange of lessons learned between site operators, regulators, safety assessors and other specialists in safety assessment of decommissioning of nuclear power plants, research reactors, laboratories, nuclear fuel cycle facilities, etc. This paper presents the lessons learned through the project up to date, i.e.; (i) a common approach to safety assessment is being applied worldwide with the following steps - establishment of assessment framework; description of the facility; definition of decommissioning activities; hazard identification and analysis; calculation of consequences; and analysis of results; (ii) a deterministic approach to safety assessment is most commonly applied; (iii) a

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)

Safety research in nuclear fuel cycle at PNC

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF{sub 6}, uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

Safety research in nuclear fuel cycle at PNC

International Nuclear Information System (INIS)

1998-09-01

This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF 6 , uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

IPR-R1 TRIGA research reactor decommissioning plan

International Nuclear Information System (INIS)

Andrade Grossi, Pablo; Oliveira de Tello, Cledola Cassia; Mesquita, Amir Zacarias

2008-01-01

The International Atomic Energy Agency (IAEA) is concerning to establish or adopt standards of safety for the protection of health, life and property in the development and application of nuclear energy for peaceful purposes. In this way the IAEA recommends that decommissioning planning should be part of all radioactive installation licensing process. There are over 200 research reactors that have either not operated for a considerable period of time and may never return to operation or, are close to permanent shutdown. Many countries do not have a decommissioning policy, and like Brazil not all installations have their decommissioning plan as part of the licensing documentation. Brazil is signatory of Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management, but until now there is no decommissioning policy, and specifically for research reactor there is no decommissioning guidelines in the standards. The Nuclear Technology Development Centre (CDTN/CNEN) has a TRIGA Mark I Research Reactor IPR-R1 in operation for 47 years with 3.6% average fuel burn-up. The original power was 100 k W and it is being licensed for 250 k W, and it needs the decommissioning plan as part of the licensing requirements. In the paper it is presented the basis of decommissioning plan, an overview and the end state / final goal of decommissioning activities for the IPR-R1, and the Brazilian ongoing activities about this subject. (author)

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

Cost update: Technology, safety, and costs of decommissioning a reference uranium fuel fabrication plant

International Nuclear Information System (INIS)

Miles, T.L.; Liu, Y.

1994-06-01

The cost estimates originally developed in NUREG/CR-1266 for commissioning a reference low-enrichment uranium fuel fabrication plant are updated from 1978 to early 1993 dollars. During this time, the costs for labor and materials increased approximately at the rate of inflation, the cost of energy increased more slowly than the rate of inflation, and the cost of low-level radioactive waste disposal increased much more rapidly than the rate of inflation. The results of the analysis indicate that the estimated costs for the immediate dismantlement and decontamination for unrestricted facility release (DECON) of the reference plant have increased from the mid-1978 value of $3.57 million to $8.08 million in 1993 with in-compact low-level radioactive waste disposal at the US Ecoloay facility near Richland, Washington. The cost estimate rises to $19.62 million with out-of-compact radioactive waste disposal at the Chem-Nuclear facility near Barnwell, South Carolina. A methodology and a formula are presented for estimating the cost of decommissioning the reference uranium fuel fabrication plant at some future time, based on these early 1993 cost estimates. The formula contains essentially the same elements as the formula given in 10 CFR 50.75 for escalating the decommissioning costs for nuclear power reactors to some future time

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.

Planning activities for ANPP decommissioning

International Nuclear Information System (INIS)

Ghazaryan, K.G.

2002-01-01

The Armenian NPP consists of two WWER-440, model 270 pressurized water reactors. After an earthquake in northern Armenia in December 1988 both units were shut down for safety reasons: Unit 1 in February 1988, Unit 2 in March 1989, respectively. Unit 2 was restarted in November 1995 after a number of safety upgrades. Unit 1 remains in a long-term shutdown mode. The design lifetime of Unit 2 expires in 2015. Opportunity to shutdown earlier has been discussed in the last years. In particular a statement has been issued by EC asking for an early shutdown of Unit 2 in exchange for the TACIS support in implementing the safety upgrades in a short term. Currently the safety improvement program is being successfully implemented in the framework of US DOE and TACIS assistance. At the moment the date of the permanent plant shutdown is not specified. As with many older reactors throughout the world, a decommissioning plan has not been developed for Armenian NPP at the design stage. After shutdown of ANPP in 1988-1989 the radiological characterization campaign at Unit 1 had been carried out. Recently two studies in the decommissioning area have been performed for ANPP. The first one has been carried out under the US DOE Assistance Program. The purpose of this study was to identify and evaluate feasible decommissioning options for ANPP. Some critical issues related to the waste management had been specified and the near-term activities within this project will be focused on issues of waste characterization and information data base creation as an important prerequisite to manage waste safely. The model used to calculate many of the decommissioning costs was NRC CECP reprogrammed for WWER NPPs. The second study had been carried out in the framework of TACIS project 'Assistance to Energy Strategic Center'. The purpose of the study was to select the best strategy to phase-out and decommission the ANPP and evaluate conditions, implications and consequence of this decision. A

CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 5 - FUEL CHANEL DECOMMISSIONING

Directory of Open Access Journals (Sweden)

Gabi ROSCA FARTAT

2014-05-01

Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of these installations has become one of the 21st century’s great challenges. Each project may be managed differently, depending on the country, development policies, financial considerations, and the availability of qualified engineers or specialized companies to handle such projects. The principle objective of decommissioning is to place a facility into such a condition that there is no unacceptable risk from the decommissioned facility to public health and safety of the environment. In order to ensure that at the end of its life the risk from a facility is within acceptable bounds, action is normally required. The overall decommissioning strategy is to deliver a timely, cost-effective program while maintaining high standards of safety, security and environmental protection. If facilities were not decommissioned, they could degrade and potentially present an environmental radiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is not considered to be an acceptable alternative to decommissioning. The final aim of decommissioning is to recover the geographic site to its original condition.

The decommissioning of Berkeley II

International Nuclear Information System (INIS)

Hannan, A.

2002-01-01

This paper describes the decommissioning progress at the Magnox site at Berkeley in Gloucestershire.Throughout the work at Berkeley the emphasis has been on conducting decommissioning safely. This has been reflected in the progress of decommissioning starting with removal of the fuel from site and thus much greater than 99% of the radioactive inventory. The major radioactive hazard is the Intermediate Level Waste in the form of fuel element debris (graphite struts and extraneous magnox components removed to increase the packing density of fuel elements in flasks going to Sellafield), miscellaneous activated components, sludges and resins. Approximately 1500 m 3 of such material exists and is stored in underground waste vaults on site. Work is underway to recover and encapsulate the waste in cement so rendering it 'passively safe'. All work on site is covered by a nuclear safety case which has a key objective of minimising the radiological exposures that could accrue to workers. Reflecting this an early decision has been taken to leave work on the Reactor Pressure Vessels themselves for several decades. Also important in protection of the workforce has been control of asbestos.Much material has been removed with redundant plant and equipment, but a programme of remediation in line with government legislation has been required to ensure personnel safety throughout the decommissioning period and into Care and Maintenance.In addition to health and safety matters the site approach to environmental issues has been consistent. Formally such standards as ISO 14001 have been adhered to and the appropriate certification maintained. At a working level the principles of reduce, reuse and recycle have been inculcated

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)

Storage of Spent Nuclear Fuel. Specific Safety Guide

International Nuclear Information System (INIS)

2012-01-01

This Safety Guide provides recommendations and guidance on the storage of spent nuclear fuel. It covers all types of storage facilities and all types of spent fuel from nuclear power plants and research reactors. It takes into consideration the longer storage periods that have become necessary owing to delays in the development of disposal facilities and the decrease in reprocessing activities. It also considers developments associated with nuclear fuel, such as higher enrichment, mixed oxide fuels and higher burnup. The Safety Guide is not intended to cover the storage of spent fuel if this is part of the operation of a nuclear power plant or spent fuel reprocessing facility. Guidance is provided on all stages for spent fuel storage facilities, from planning through siting and design to operation and decommissioning, and in particular retrieval of spent fuel. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Roles and responsibilities; 4. Management system; 5. Safety case and safety assessment; 6. General safety considerations for storage of spent fuel. Appendix I: Specific safety considerations for wet or dry storage of spent fuel; Appendix II: Conditions for specific types of fuel and additional considerations; Annex: I: Short term and long term storage; Annex II: Operational and safety considerations for wet and dry spent fuel storage facilities; Annex III: Examples of sections of operating procedures for a spent fuel storage facility; Annex IV: Site conditions, processes and events for consideration in a safety assessment (external human induced phenomena); Annex V: Site conditions, processes and events for consideration in a safety assessment (external natural phenomena); Annex VI: Site conditions, processes and events for consideration in a safety assessment (external human induced phenomena); Annex VII: Postulated initiating events for consideration in a safety assessment (internal phenomena).

Industrial safety in a nuclear decommissioning environment observations and lessons learned

International Nuclear Information System (INIS)

Brevig, D.

2008-01-01

Decommissioning activities present unusual and unexpected workplace safety challenges that go far beyond the traditional experience of nuclear power plant managers. A blend of state-of-the-art safety program management tools along with new and practical applications are required to ensure high industrial safety performance. The demanding and rigorously applied nuclear safety engineering standards that are accepted as normal and routine in the operation of a nuclear power facility, should transform as an industrial safety standard during the non-operating period of decommissioning. In addition, historical measures of non-nuclear industrial safety injury rates would or should not be acceptable safety behaviors during a nuclear decommissioning project. When complex projects, such as the decommissioning of a nuclear generating facility are undertaken, the workforce brings experience, qualifications, and assumptions to the project. The overall multi-year general schedule is developed, with more schedule details, for example, for the nearest rolling 12-18 months. Methods are established for the selection of contractors to assist in areas that are not normal tasks for the facility workforce, whose normal activity is managing and operating a nuclear generating station. However, it is critical to manage those contractors to the agreed work scope to ensure success is maintained by both parties, e.g. the job gets done, on schedule, on budget, all parties are financially whole when the work is complete, and safely. The purpose of this paper is to provide a perspective of nuclear plant personal safety in the ever changing industrial environment created by the demolition of robust and often radiologically contaminated structures in a nuclear facility decommissioning project. (author)

Industrial safety in a nuclear decommissioning environment observations and lessons learned

Energy Technology Data Exchange (ETDEWEB)

Brevig, D. [Independent Consultant, San Clemente (United States)

2008-07-01

Decommissioning activities present unusual and unexpected workplace safety challenges that go far beyond the traditional experience of nuclear power plant managers. A blend of state-of-the-art safety program management tools along with new and practical applications are required to ensure high industrial safety performance. The demanding and rigorously applied nuclear safety engineering standards that are accepted as normal and routine in the operation of a nuclear power facility, should transform as an industrial safety standard during the non-operating period of decommissioning. In addition, historical measures of non-nuclear industrial safety injury rates would or should not be acceptable safety behaviors during a nuclear decommissioning project. When complex projects, such as the decommissioning of a nuclear generating facility are undertaken, the workforce brings experience, qualifications, and assumptions to the project. The overall multi-year general schedule is developed, with more schedule details, for example, for the nearest rolling 12-18 months. Methods are established for the selection of contractors to assist in areas that are not normal tasks for the facility workforce, whose normal activity is managing and operating a nuclear generating station. However, it is critical to manage those contractors to the agreed work scope to ensure success is maintained by both parties, e.g. the job gets done, on schedule, on budget, all parties are financially whole when the work is complete, and safely. The purpose of this paper is to provide a perspective of nuclear plant personal safety in the ever changing industrial environment created by the demolition of robust and often radiologically contaminated structures in a nuclear facility decommissioning project. (author)

Decommissioning: Regulatory activities and identification of key organizational and human factors safety issues

International Nuclear Information System (INIS)

Durbin, N.E.; Melber, B.D.; Lekberg, A.

2001-12-01

In the late 1990's the Swedish government decided to shut down Unit 1 of the Barsebaeck nuclear power plant. This report documents some of the efforts made by the Swedish Nuclear Power Inspectorate (SKI) to address human factors and organizational issues in nuclear safety during decommissioning of a nuclear facility. This report gives a brief review of the background to the decommissioning of Barsebaeck 1 and points out key safety issues that can arise during decommissioning. The main regulatory activities that were undertaken were requirements that the plant provide special safety reports on decommissioning focusing on first, the operation of both units until closure of Unit 1 and second, the operation of Unit 2 when Unit 1 was closed. In addition, SKI identified areas that might be affected by decommissioning and called these areas out for special attention. With regard to these areas of special attention, SKI required that the plant provide monthly reports on changing and emerging issues as well as self-assessments of the areas to be addressed in the special safety reports. Ten key safety issues were identified and evaluated with regard to different stages of decommissioning and with regard to the actions taken by Barsebaeck. Some key conclusions from SKI's experience in regulating a decommissioning nuclear power plant conclude the report

The decommissioning of the Barnwell nuclear fuel plant

International Nuclear Information System (INIS)

McNeil, J.

1999-01-01

The decommissioning of the Barnwell Nuclear Fuel Plant is nearing completion. The owner's objective is to terminate the plant radioactive material license associated with natural uranium and transuranic contamination at the plant. The property is being released for commercial-industrial uses, with radiation exposure from residual radioactivity not to exceed 0.15 millisieverts per year. Historical site assessments have been performed and the plant characterized for residual radioactivity. The decommissioning of the uranium hexafluoride building was completed in April, 1999. Most challenging from a radiological control standpoint is the laboratory building that contained sixteen labs with a total of 37 glove boxes, many of which had seen transuranics. Other facilities being decommissioned include the separations building and the 300,000-gallon underground high-level waste tanks. This decommissioning in many ways is the most significant project of this type yet undertaken in South Carolina. Many innovations have been made to reduce the time and costs associated with the project. (author)

Long-term safety of the maintenance and decommissioning waste of the encapsulation plant

International Nuclear Information System (INIS)

Nummi, O.; Kylloenen, J.; Eurajoki, T.

2012-12-01

This report, Long-term safety of the maintenance and decommissioning waste of the encapsulation plant, presents the disposal concept for the low and intermediate level waste (L/ILW) that is generated during the operation and decommissioning of the encapsulation plant, and assesses the long-term safety of the disposal of the waste. Radioactive waste originates from the spent nuclear fuel transferred and dried in the encapsulation plant. Radioactive waste accumulates also in the maintenance of the components and systems of the encapsulation plant. The waste is collected, exempted from control if possible and treated for final disposal if necessary. The waste is disposed of in the L/ILW hall which is currently planned to be located at a depth of -180 meters along the access tunnel to the repository for spent fuel. The main engineered barrier in the L/ILW hall is a concrete basin that encases the dried liquid waste. The safety concept of L/ILW disposal is based on the slow release of radioactivity from the L/ILW hall and its limited transport through the bedrock into biosphere. The release and transport of the radioactivity is described by the assessment scenarios, which include expected evolution and unlikely events affecting the long-term safety. The scenarios act as guidelines according to which the conceptual and mathematical models are formed. The long-term safety of the L/ILW hall is assessed using deterministic and probabilistic modeling. Special issues such as human intrusion and radiation effects on other biota are also assessed. The most significant contributor to the dose rates is the short-lived radionuclide 90 Sr followed by long-lived nuclides 129 I and 108 mAg. The annual doses to the public, and release rates of radioactive substances stay below the regulatory constraints in all analyzed scenarios. (orig.)

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.

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.

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

Options for Enhancing Education, Training and Knowledge Management for Decommissioning

International Nuclear Information System (INIS)

Roberts, John

2017-01-01

UK Nuclear Sites: Decommissioning: 26 Magnox Reactors, 2 Fast Reactors; Operational: 14 AGRs, 1 PWR; 9.6 GWe Total Capacity. Nuclear Technology Education Consortium (NTEC) Decommissioning Modules: N04 Decommissioning, Radioactive Waste and Environmental Management; N07 Nuclear Safety Case Development; N08 Particle & Colloid Engineering in the Nuclear Industry; N09 Policy, Regulation & Licensing; N10 Processing, Storage & Disposal of Nuclear Waste; N31 Management of the Decommissioning Process; N01 Reactor Physics, Criticality & Design; N02 Nuclear Fuel Cycle; N03 Radiation & Radiological Protection; N06 Reactor Materials & Lifetime Behaviour; N11 Radiation Shielding; N12 Reactor Thermal Hydraulics; N13 Criticality Safety Management; N23 Environmental Impact Assessment; N32 Experimental Reactor Physics

Technology, safety and costs of decommissioning nuclear reactors at multiple-reactor stations

International Nuclear Information System (INIS)

Wittenbrock, N.G.

1982-01-01

Safety and cost information is developed for the conceptual decommissioning of large (1175-MWe) pressurized water reactors (PWR) and large (1155-MWe) boiling water reactors (BWR) at multiple-reactor stations. Three decommissioning alternatives are studied: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). Safety and costs of decommissioning are estimated by determining the impact of probable features of multiple-reactor-station operation that are considered to be unavailable at a single-reactor station, and applying these estimated impacts to the decommissioning costs and radiation doses estimated in previous PWR and BWR decommissioning studies. The multiple-reactor-station features analyzed are: the use of interim onsite nuclear waste storage with later removal to an offsite waste disposal facility, the use of permanent onsite nuclear waste disposal, the dedication of the site to nuclear power generation, and the provision of centralized services

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)

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

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

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)

New version of NPP Krsko Decommissioning program and LILW and spent fuel management

International Nuclear Information System (INIS)

Zeleznik, N.; Mele, I.; Jenko, T.; Lokner, V.; Levanat, I.; Rapic, A.

2004-01-01

According to the requirements of the bilateral agreement between Republic of Slovenia and Republic of Croatia on the legal and other obligations for Nuclear power plant (NPP) Krsko the Decommissioning program was prepared. The main purpose of the program was to estimate the overall expenses of the future decommissioning, radioactive waste and spent fuel management of the NPP Krsko in order to establish separate fund in Croatia and to correct the rate per kWh collected in the existing decommissioning fund in Slovenia. The program looked at all possible scenarios of dismantling, radioactive waste and spent fuel management and proposed the most plausible two scenarios which are technically possible and financially feasible. (author)

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)

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)

General aspects to be considered in a research reactor decommissioning plan

International Nuclear Information System (INIS)

Grossi, Pablo Andrade; Tello, Cledola Cassia Oliveira de

2009-01-01

There are more than 200 research reactors that have either not operated for a considerable period of time and may never return to operation or, are close to permanent shutdown. Many countries do not have a decommissioning policy, and like Brazil not all installations have their decommissioning plan as part of the licensing documentation. Brazil is signatory of Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, but until now there is no decommissioning policy, and specifically for research reactor there is no decommissioning guidelines in the standards. The Nuclear Technology Development Centre (CDTN/CNEN-MG) has a TRIGA Mark I Research Reactor IPR-R1 in operation for 47 years with 3.6% average fuel burn-up. The original power was 100 kW and it is being licensed for 250 kW, and it needs the decommissioning plan as part of the licensing requirements. In the paper it is presented general aspects and contents of a Research Reactors Decommissioning Plan. As the Brazilian regulatory body so far does not have a decommissioning policy established neither a regulatory framework in this issue, individual efforts are being integrated to establish a National Decommissioning Group (matrix structure) to perform the decommissioning planning and activities. The approach used for IPR-R1 is presented as suggestions to develop the national regulatory standards on this issue and applied to Brazilian Research Reactors and other nuclear facilities. (author)

Topical Session on the Decommissioning and Dismantling Safety Case

International Nuclear Information System (INIS)

2002-01-01

Set up by the Radioactive Waste Management Committee (RWMC), the WPDD brings together senior representatives of national organisations who have a broad overview of Decommissioning and Dismantling (D and D) issues through their work as regulators, implementers, R and D experts or policy makers. These include representatives from regulatory authorities, industrial decommissioners from the NEA Cooperative Programme on Exchange of Scientific and Technical Information on Nuclear Installation Decommissioning Projects (CPD), and cross-representation from the NEA Committee on Nuclear Regulatory Activities, the Committee on Radiation Protection and Public Health, and the RWMC. The EC is a member of the WPDD and the IAEA also participates. This ensures co-ordination amongst activities in these international programmes. Participation from civil society organisations is considered on a case by case basis, and has already taken place through the active involvement of the Group of Municipalities with Nuclear Installations at the first meeting of the WPDD At its second meeting, in Paris, 5-7 December 2001, the WPDD held two topical sessions on the D and D Safety Case and on the Management of Materials from D and D, respectively. This report documents the topical session on the safety case. The topical session was meant to provide an exchange of information and experience on the following issues: What topics should be included in a safety case? Of what should it consist? Is there sufficient and complete guidance nationally and internationally? How do practices differ internationally? Main boundary condition to this session was that it would deal with plants where spent fuel has been removed. Also the topical sessions was kept at a level that makes the most of the varied constituency of the WPDD. Namely, interface issues are important, and issue-identification and discussion was the immediate goal. There was less interest in examining areas where variability amongst national

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

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

Lessons Learned for Decommissioning Planning

International Nuclear Information System (INIS)

Sohn, Wook; Kim, Young-gook; Kim, Hee-keun

2015-01-01

The purpose of this paper is to introduce the U.S. nuclear industrial's some key lessons learned especially for decommissioning planning based on which well informed decommissioning planning can be carried out. For a successful decommissioning, it is crucial to carry out a well-organized decommissioning planning before the decommissioning starts. This paper discussed four key factors which should be decided or considered carefully during the decommissioning planning period with introduction of related decommissioning lessons learned of U.S. nuclear industry. Those factors which have been discussed in this paper include the end state of a site, the overall decommissioning strategy, the management of the spent fuels, and the spent fuel pool island. Among them, the end state of a site should be decided first as it directs the whole decommissioning processes. Then, decisions on the overall decommissioning strategy (DECON vs. SAFSTOR) and the management of the spent fuels (wet vs. dry) should follow. Finally, the spent fuel pool island should be given due consideration because its implementation will result in much cost saving. Hopefully, the results of this paper would provide useful inputs to performing the decommissioning planing for the Kori unit 1

Radioactive waste management decommissioning spent fuel storage. V. 3. Waste transport, handling and disposal spent fuel storage

International Nuclear Information System (INIS)

1985-01-01

As part of the book entitled Radioactive waste management decommissioning spent fuel storage, vol. 3 dealts with waste transport, handling and disposal, spent fuel storage. Twelve articles are presented concerning the industrial aspects of nuclear waste management in France [fr

Decommissioning of the ICI TRIGA Mark I reactor

International Nuclear Information System (INIS)

Parry, D.R.; England, M.R.; Ward, A.; Green, D.

2000-01-01

This paper considers the fuel removal, transportation and subsequent decommissioning of the ICI TRIGA Mark I Reactor at Billingham, UK. BNFL Waste Management and Decommissioning carried out this work on behalf of ICI. The decommissioning methodology was considered in the four stages to be described, namely Preparatory Works, Reactor Defueling, Intermediate Level Waste Removal and Low Level Waste Removal. This paper describes the principal methodologies involved in the defueling of the reactor and subsequent decommissioning operations, highlighting in particular the design and safety case methodologies used in order to achieve a solution which was completed without incident or accident and resulted in a cumulative radiation dose to personnel of only 1.57 mSv. (author)

Decommissioning of NPPs with spent nuclear fuel present - efforts to amend the German regulatory framework to cope with this situation

International Nuclear Information System (INIS)

Brendebach, Boris; Rehs, Bernd

2016-01-01

The authorization to operate an installation for the fission of nuclear fuel for the commercial production of electricity was withdrawn for the seven oldest NPPs and NPP Kruemmel in Germany on August 6, 2011 after the events at Japanese Nuclear Power Plant (NPP) Fukushima Daiichi in March 2011. In the meantime, all these NPPs applied for decommissioning. One aspect reflected in the applications for these NPPs is the possibility that spent nuclear fuel elements or fuel rods will still be present in the cooling ponds at least during the first stage of decommissioning, i.a. due to limited availability of spent fuel casks. Although considerable decommissioning experiences are available in Germany, the approach 'decommissioning with fuel elements present' has been the exceptional case so far. The paper highlights the efforts undertaken to strengthen the regulatory framework with respect to decommissioning in Germany taking into account this changed approach. The paper presents a short introduction to the legal and regulatory requirements for decommissioning in Germany. Afterwards, the updates to the Decommissioning Guide, which includes proposals for an appropriate procedure for the decommissioning, safe enclosure and dismantling of facilities or parts thereof as defined in item 7 of the German Atomic Energy Act in respect of the application of the technical rules for planning and preparation of decommissioning measures as well as for licensing and supervision, are highlighted. In addition, the amendments to the Guidelines for the Decommissioning of Nuclear Facilities of the Nuclear Waste Management Commission (ESK), which is complementary to the Decommissioning Guide in a technical sense, are reported as well. (authors)

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

Energy Technology Data Exchange (ETDEWEB)

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

2000-10-01

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

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

International Nuclear Information System (INIS)

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

2000-10-01

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

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)

Technology, safety, and costs of decommissioning reference light-water reactors following postulated accidents. Appendices

Energy Technology Data Exchange (ETDEWEB)

Murphy, E S; Holter, G M

1982-11-01

Appendices contain information concerning the reference site description; reference PWR facility description; details of reference accident scenarios and resultant contamination levels; generic cleanup and decommissioning information; details of activities and manpower requirements for accident cleanup at a reference PWR; activities and manpower requirements for decommissioning at a reference PWR; costs of decommissioning at a reference PWR; cost estimating bases; safety assessment details; and details of post-accident cleanup and decommissioning at a reference BWR.

Technology, safety and costs of decommissioning a Reference Boiling Water Reactor Power Station. Main report. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWe.

Technology, Safety and Costs of Decommissioning a Reference Uranium Hexafluoride Conversion Plant

Energy Technology Data Exchange (ETDEWEB)

Elder, H. K.

1981-10-01

Safety and cost information is developed for the conceptual decommissioning of a commercial uranium hexafluoride conversion (UF{sub 6}) plant. Two basic decommissioning alternatives are studied to obtain comparisons between cost and safety impacts: DECON, and passive SAFSTOR. A third alternative, DECON of the plant and equipment with stabilization and long-term care of lagoon wastes. is also examined. DECON includes the immediate removal (following plant shutdown) of all radioactivity in excess of unrestricted release levels, with subsequent release of the site for public use. Passive SAFSTOR requires decontamination, preparation, maintenance, and surveillance for a period of time after shutdown, followed by deferred decontamination and unrestricted release. DECON with stabilization and long-term care of lagoon wastes (process wastes generated at the reference plant and stored onsite during plant operation} is also considered as a decommissioning method, although its acceptability has not yet been determined by the NRC. The decommissioning methods assumed for use in each decommissioning alternative are based on state-of-the-art technology. The elapsed time following plant shutdown required to perform the decommissioning work in each alternative is estimated to be: for DECON, 8 months; for passive SAFSTOR, 3 months to prepare the plant for safe storage and 8 months to accomplish deferred decontamination. Planning and preparation for decommissioning prior to plant shutdown is estimated to require about 6 months for either DECON or passive SAFSTOR. Planning and preparation prior to starting deferred decontamination is estimated to require an additional 6 months. OECON with lagoon waste stabilization is estimated to take 6 months for planning and about 8 months to perform the decommissioning work. Decommissioning cost, in 1981 dollars, is estimated to be $5.91 million for OECON. For passive SAFSTOR, preparing the facility for safe storage is estimated to cost $0

Decommissioning the Dresden Unit 1 Spent Fuel Pool

International Nuclear Information System (INIS)

Demmer, R.L.; Bargelt, R.J.; Panozzo, J.B.; Christensen, R.J.

2006-01-01

The Dresden Nuclear Power Station, Unit 1 Spent Fuel Pool (SFP) (Exelon Generation Co.) was decommissioned using a new underwater coating strategy developed in cooperation with the Idaho National Laboratory (INL). This was the first time that a commercial nuclear power plant (NPP) SFP was decommissioned using this underwater coating approach. This approach has advantages in many aspects, particularly in reducing airborne contamination and in safer, more cost effective deactivation. The process was pioneered at the INL and used to decommission three SFPs with a total combined pool volume of over 900,000 gallons. The INL provided engineering support and shared project plans to successfully initiate the Dresden project. This report outlines the steps taken by the INL and Exelon on the pathway for this activity. The rationale used to select the underwater coating option and the advantages and disadvantages are shown. Special circumstances, such as the use of a remotely operated underwater vehicle to map (visually and radiologically) the pool areas that were not readily accessible, are discussed. Several specific areas where special equipment was employed are given and a lessons learned evaluation is included. (authors)

The First Decommissioning of a Fusion Reactor Fueled by Deuterium-Tritium

International Nuclear Information System (INIS)

Gentile, Charles A.; Perry, Erik; Rule, Keith; Williams, Michael; Parsells, Robert; Viola, Michael; Chrzanowski, James

2003-01-01

The Tokamak Fusion Test Reactor (TFTR) at the Plasma Physics Laboratory of Princeton University (PPPL) was the first fusion reactor fueled by a mixture of deuterium and tritium (D-T) to be decommissioned in the world. The decommissioning was performed over a period of three years and was completed safely, on schedule, and under budget. Provided is an overview of the project and detail of various factors which led to the success of the project. Discussion will cover management of the project, engineering planning before the project started and during the field work as it was being performed, training of workers in the field, the novel adaptation of tools from other industry, and the development of an innovative process for the use of diamond wire to segment the activated/contaminated vacuum vessel. The success of the TFTR decommissioning provides a viable model for the decommissioning of D-T burning fusion devices in the future

Final project report: TA-35 Los Alamos Power Reactor Experiment No. II (LAPRE II) decommissioning project

International Nuclear Information System (INIS)

Montoya, G.M.

1993-02-01

This final report addresses the decommissioning of the LAPRE II Reactor, safety enclosure, fuel reservoir tanks, emergency fuel recovery system, primary pump pit, secondary loop, associated piping, and the post-remediation activities. Post-remedial action measurements are also included. The cost of the project including, Phase I assessment and Phase II remediation was approximately $496K. The decommissioning operation produced 533 M 3 of mixed waste

Decommissioning of Medical, Industrial and Research Facilities. Safety Guide

International Nuclear Information System (INIS)

2010-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

Decommissioning of medical, industrial and research facilities. Safety guide

International Nuclear Information System (INIS)

2005-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

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)

National report of the Slovak Republic compiled in terms of the Join on the safety of spent fuel management and on the safety of radwaste management

International Nuclear Information System (INIS)

Jurina, V.; Viktory, D.; Petrik, T.; Sovcik, J.; Suess, J.; Tomek, J.; Lukacovic, J.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Vaclav, J.; Bystricka, S.; Barbaric, M.; Horvath, J.; Betak, J.; Mihaly, B.; Adamovsky, V.; Baloghova, A.; Orihel, M.; Vasina, D.; Balaz, J.; Misovicova, D.; Vrtoch, M.; Mlcuch, J.; Granak, P.; Meleg, J.; Bardy, M.; Gogoliak, J.

2011-08-01

The National safety report of the Slovak Republic on the safety of spent fuel management and on the safety of radwaste management in 2011 is presented. These activities in the safety of spent fuel management and radioactive waste management in the Slovak Republic are reported under the headings: (A) Introduction; B) Concept for spent nuclear fuel management (SNF) and radwaste management (RAW); (C) Scope of application of the convention; (D) Spent fuel management and radioactive waste (RAW) management facilities; (E) Legislation and regulation; (F) General safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste (RAW) management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Disused sealed sources; (K) Planned measures to improve safety; (L) Communication with the public; (M) Annexes. Annexes consists of following parts: I. List of nuclear facilities for spent fuel and RAW management. II. Limits of radioactive material discharges into atmosphere and hydrosphere. III. List of nuclear installations in decommissioning. IV. Inventory of stored spent nuclear fuel. V. Inventory of stored RAW. VI. List of national laws, decrees and guidelines. VII. List of international expert reports (including safety reports). VIII. List of authors.

Technology, safety, and costs of decommissioning reference nuclear research and test reactors: sensitivity of decommissioning radiation exposure and costs to selected parameters

International Nuclear Information System (INIS)

Konzek, G.J.

1983-07-01

Additional analyses of decommissioning at the reference research and test (R and T) reactors and analyses of five recent reactor decommissionings are made that examine some parameters not covered in the initial study report (NUREG/CR-1756). The parameters examined for decommissioning are: (1) the effect on costs and radiation exposure of plant size and/or type; (2) the effects on costs of increasing disposal charges and of unavailability of waste disposal capacity at licensed waste disposal facilities; and (3) the costs of and the available alternatives for the disposal of nuclear R and T reactor fuel assemblies

Human resource development for management of decommissioning

International Nuclear Information System (INIS)

Tanaka, Kenichi

2017-01-01

This paper described the contents of 'Human resource development for the planning and implementation of safe and reasonable nuclear power plant decommissioning' as the nuclear human resource development project by the Ministry of Education, Culture, Sports, Science and Technology. The decommissioning of a nuclear power plant takes 30 to 40 years for its implementation, costing tens of billions of yen. As the period of decommissioning is almost the same as the operation period, it is necessary to provide a systematic and continuous supply of engineers who understand the essence of the decommissioning project. The engineers required here should have project management ability to take charge of preparation, implementation, and termination of decommissioning, and have the ability to perform not only technology, but also factor management, cost management, and the like. As the preconditions of these abilities, it is important to develop human resources who possess qualities that can oversee decommissioning in the future. The contents of human resource education are as follows; (1) desk training (teaching materials: facilities of nuclear power plants, management of nuclear fuels, related laws, decommissioning work, decontamination, dismantling, disposal of waste, etc.), (2) field training (simulators, inspection of power station under decommissioning, etc.), (3) practical training (radiation inventory evaluation, and safety assessment), and (4) inspection of overseas decommissioning, etc. (A.O.)

Safety and dose management during decommissioning of a fire damaged nuclear reactor

International Nuclear Information System (INIS)

Pomfret, D.G.

2000-01-01

Windscale Piles 1 and 2 in Cumbria in the UK were constructed in the early 1950s. They were not intended to produce electricity but were for military purposes only. They were graphite-moderated, air-cooled reactors with horizontal fuel channels fuelled with uranium rods clad in finned aluminium. In October 1957, Windscale Pile 1 suffered a core fire during a planned release of Wigner energy and both Piles were subsequently closed down. Following the fire, Pile 2 was defuelled entirely and as much fuel as was possible was removed from Pile 1. However, it is estimated that up to 15 Te of fuel remains in the core, a large proportion of which is located in the central Fire Affected Zone (FAZ). The condition of the fuel and graphite moderator in the FAZ is not known. It is possible that the moderator could contain voidage, greatly reduced density graphite and fused materials in a disordered matrix. It is probable that there is residual Wigner energy in the graphite. Use of water as part of the attempt to extinguish the fire, together with the possibility that the solidification of molten materials or other local sealing mechanisms could have excluded air mean that uranium hydrides, carbides and other pyrophorics may be present within the core. Pile 1 is now being decommissioned and a considerable amount of preparatory work has already been carried out during Phase 1. Phase 2 decommissioning, which will remove the residual fuel, the moderator and associated steelwork, condition the wastes and place them in a purpose built store is now underway. This work will be carried out for the site licensee, the United Kingdom Energy Authority, by a consortium of British Nuclear Fuels plc, Rolls Royce and NUKEM. This paper will describe the methods to be used to decommission Pile 1 and the systems and procedures which will be used to ensure that it is done safely and with the lowest reasonably practicable environmental impact. It will also describe the methods which will be used to

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

1999-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

2004-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Decommissioning of nuclear power plants and research reactors. Safety guide

International Nuclear Information System (INIS)

2001-01-01

Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of nuclear power plants and research reactors. It is intended to provide guidance to national authorities and operating organizations for the planning and safe management of the decommissioning of such installations. This Safety Guide has been prepared through a series of Consultants and Technical Committee meetings. It supersedes former Safety Series publications Nos 52, 74 and 105

Study of fundamental safety-related aspects in connection with the decommissioning of nuclear installations. Pt. 2. Safety considerations and emissions

International Nuclear Information System (INIS)

John, T.; Thierfeldt, S.

1993-01-01

The procedures used so far for the examination of selected decommissioning projects in expert opinions on safety, in particular of nuclear power plants, were screened, with special emphasis on the examination of safety considerations, i.e. analysis of possible accidents. Generic examinations on safety in connection with the decommissioning of nuclear installations were used to assess safety considerations. Different approaches were taken with regard to the selection of analysed accidents and determination of parameters defining activity release and assumptions in safety opinions. Therefore it seems to be appropriate to establish a scenario to be used for nuclear power plant accident analyses, which covers the range of radiologically relevant accidents during decommissioning activities. Although it might be controversially discussed, because of specific plant designs (test and prototype reactors as well as first power reactors), to establish such a radiologically covering accident scenario for older nuclear power plants, it seems to be no problem for modern light water reactors. The radiologically most relevant possible accident in a decommissioned nuclear power plant is fire in the plant. Parameter values and assumptions are suggested which determine the source term in the event of a fire in the plant. Inspite of a conservative determination of parameter values and assumptions, an environmental dose commitment of less than 50 mSv is to be expected for the resulting source term. (orig.) [de

Environmental restoration and decontamination and decommissioning safety documentation

International Nuclear Information System (INIS)

Hansen, J.L.; Frauenholz, L.H.; Kerr, N.R.

1993-01-01

This document presents recommendations of a working group designated by the Environmental Restoration and Remediation (ER) and Decontamination and Decommissioning (D ampersand D) subcommittees of the Westinghouse M ampersand O (Management and Operation) Nuclear Facility Safety Committee. A commonalty of approach to safety documentation specific to ER and D ampersand D activities was developed and is summarized below. Allowance for interpretative tolerance and documentation flexibility appropriate to the activity, graded for hazard category, duration, and complexity, was a primary consideration in development of this guidance

National report of the Slovak Republic compiled in terms of the join convention on the safety of spent fuel management and on the safety of radwaste management

International Nuclear Information System (INIS)

Jurina, V.; Viktory, D.; Petrik, T.; Sovcik, J.; Suess, J.; Tomek, J.; Lukacovic, J.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Vaclav, J.; Bystricka, S.; Barbaric, M.; Horvath, J.; Betak, J.; Mihaly, B.; Adamovsky, V.; Baloghova, A.; Orihel, M.; Vasina, D.; Balaz, J.; Misovicova, D.; Vrtoch, M.; Mlcuch, J.; Granak, P.; Meleg, J.; Bardy, M.; Gogoliak, J.

2011-08-01

The National safety report of the Slovak Republic on the safety of spent fuel management and on the safety of radwaste management in 2011 is presented. These activities in the safety of spent fuel management and radioactive waste management in the Slovak Republic are reported under the headings: (A) Introduction; B) Concept for spent nuclear fuel management (SNF) and radwaste management (RAW); (C) Scope of application of the convention; (D) Spent fuel management and radioactive waste (RAW) management facilities; (E) Legislation and regulation; (F) General safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste (RAW) management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Disused sealed sources; (K) Planned measures to improve safety; (L) Communication with the public; (M) Annexes. Annexes consists of following parts: I. List of nuclear facilities for spent fuel and RAW management. II. Limits of radioactive material discharges into atmosphere and hydrosphere. III. List of nuclear installations in decommissioning. IV. Inventory of stored spent nuclear fuel. V. Inventory of stored RAW. VI. List of national laws, decrees and guidelines. VII. List of international expert reports (including safety reports). VIII. List of authors.

Safety analysis for the 233-S decontamination and decommissioning project

International Nuclear Information System (INIS)

Thoren, S.

1996-08-01

Decommissioning of the 233-S Plutonium Concentration Facility (REDOX) is a proposed expedited response action that is regulated by the Comprehensive Environmental Response Compensation and Liability Act of 1980 and the Hanford Federal Facility Agreement and Consent Order. Due to progressive physical deterioration of this facility, a decontamination and decommissioning plan is being considered for the immediate future. This safety analysis describes the proposed actions involved in this D ampersand D effort; identifies the radioactive material inventories involved; reviews site specific environmental characteristics and postulates an accident scenario that is evaluated to identify resultant effects

Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

Energy Technology Data Exchange (ETDEWEB)

Haffner, D.R.; Villelgas, A.J. [Pacific Northwest Lab., Richland, WA (United States)

1996-01-01

This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities.

Technology, safety, and costs of decommissioning a reference large irradiator and reference sealed sources

International Nuclear Information System (INIS)

Haffner, D.R.; Villelgas, A.J.

1996-01-01

This report contains the results of a study sponsored by the US Nuclear Regulatory Commission (NRC) to examine the decommissioning of large radioactive irradiators and their respective facilities, and a broad spectrum of sealed radioactive sources and their respective devices. Conceptual decommissioning activities are identified, and the technology, safety, and costs (in early 1993 dollars) associated with decommissioning the reference large irradiator and sealed source facilities are evaluated. The study provides bases and background data for possible future NRC rulemaking regarding decommissioning, for evaluation of the reasonableness of planned decommissioning actions, and for determining if adequate funds are reserved by the licensees for decommissioning of their large irradiator or sealed source facilities. Another purpose of this study is to provide background and information to assist licensees in planning and carrying out the decommissioning of their sealed radioactive sources and respective facilities

The use of managing agencies in decommissioning

International Nuclear Information System (INIS)

Nelson, R.L.

1994-01-01

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

Recovery of decommissioning and spent fuel charges

International Nuclear Information System (INIS)

Bermanis, G.

1982-01-01

The licensing and financial aspects of NPP decommissioning, deactivation and dismantling of radioactive equipment in the USA are considered. Data on the costs of spent fuel transport and conservation are given. The state of the problem development in other countries is briefly described. It is pointed out that the technical aspect of the problem is much better studied than that of license-financial problem. At the same time in contrast to TPP NPP use is connected with considerable expenses after the end of a power plant sevice time

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

International Nuclear Information System (INIS)

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Appendices

Energy Technology Data Exchange (ETDEWEB)

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and EMTOMB (entombment). The study results are presented in two volumes. Volume 2 (Appendices) contains the detailed data that support the results given in Volume 1, including unit-component data.

Decommissioning - The worldwide challenge

International Nuclear Information System (INIS)

McKeown, John

2002-01-01

Full text: Whatever the future may hold for nuclear power, there are closed or ageing nuclear facilities in many countries around the world. While these may be in safe care and maintenance at present, a sustainable long term solution is required. Facilities need to be decommissioned, contaminated land remediated, and wastes conditioned for safe storage or disposal. Practical nuclear site restoration has been demonstrated internationally. This experience has revealed generic challenges in dealing with old, often experimental, facilities. These include: Facilities not designed for ease of decommissioning; Records of plant construction and operation, and of the materials utilised and wastes produced, not to modern standards; Fuels and wastes stored for long periods in less than optimal conditions, leading to deterioration and handling problems; The historic use of experimental fuels and materials, giving rise to unique waste streams requiring unique waste management solutions; The application of modern safety and environmental standards to plant which dates from the 1940s, 50s and 60s, requiring investment before decommissioning can even commence. These problems can be tackled, as examples from UKAEA's own programme will illustrate. But two fundamental issues must be recognised and considered. First, the costs of decommissioning older facilities are very high, and may place a heavy burden on national budgets, despite using best efforts to control them. We can limit these costs by learning from one another's experience and sharing the development of new techniques and technologies. UKAEA has already initiated a programme of international collaboration, and hopes that other IAEA countries will be encouraged to follow suit. But whilst the costs of decommissioning may be high, the process normally meets with public acceptance. This is seldom the case for long term waste storage or disposal. Until waste management routes are available - either nationally or internationally

CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FORTHE DECOMMISSIONING OF THE FUEL CHANNELS IN THECANDU NUCLEAR REACTOR

Directory of Open Access Journals (Sweden)

Gabi ROSCA FARTAT

2013-05-01

Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of theseinstallations has become one of the 21stcentury’s great challenges. Each project may be managed differently,depending on the country, development policies, financial considerations, and the availability of qualifiedengineers or specialized companies to handle such projects. The principle objective of decommissioning is toplace a facility into such a condition that there is no unacceptable risk from the decommissioned facility topublic health and safety of the environment. In order to ensure that at the end of its life the risk from a facility iswithin acceptable bounds, action is normally required. The overall decommissioning strategy is todeliver a timely, cost-effective program while maintaining high standards of safety, security and environmentalprotection. If facilities were not decommissioned, they could degrade and potentially present an environmentalradiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is notconsidered to be an acceptable alternative to decommissioning. The final aim of decommissioning is torecover the geographic site to its original condition.

Decommissioning alternatives for the West Valley, New York, Fuel Reprocessing Plant

Energy Technology Data Exchange (ETDEWEB)

Munson, L F; Nemec, J F; Koochi, A K

1978-06-01

The methodology and numerical values of NUREG-0278 were applied to four decommissioning alternatives for the West Valley Fuel Reprocessing Plant. The cost and impacts of the following four alternatives for the process building, fuel receiving and storage, waste tank farm, and auxiliary facilities were assessed: (1) layaway, (2) protective storage, (3) preparation for alternate nuclear use, and (4) dismantlement. The estimated costs are 5.7, 11, 19, and 31 million dollars, respectively. (DLC)

Decommissioning alternatives for the West Valley, New York, Fuel Reprocessing Plant

International Nuclear Information System (INIS)

Munson, L.F.; Nemec, J.F.; Koochi, A.K.

1978-06-01

The methodology and numerical values of NUREG-0278 were applied to four decommissioning alternatives for the West Valley Fuel Reprocessing Plant. The cost and impacts of the following four alternatives for the process building, fuel receiving and storage, waste tank farm, and auxiliary facilities were assessed: (1) layaway, (2) protective storage, (3) preparation for alternate nuclear use, and (4) dismantlement. The estimated costs are 5.7, 11, 19, and 31 million dollars, respectively

NPP Krsko decommissioning concept

International Nuclear Information System (INIS)

Novsak, M.; Fink, K.; Spiler, J.

1996-01-01

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

NPP Krsko decommissioning concept

International Nuclear Information System (INIS)

Novsak, M.; Fink, K.; Spiler, J.

1996-01-01

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

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.)

Technology, safety, and costs of decommissioning a reference pressurized water reactor power station. Appendices

International Nuclear Information System (INIS)

Smith, R.I.; Konzek, G.J.; Kennedy, W.E. Jr.

1978-05-01

Detailed appendices are presented under the following headings: reference PWR facility description, reference PWR site description, estimates of residual radioactivity, alternative methods for financing decommissioning, radiation dose methodology, generic decommissioning activities, intermediate dismantlement activities, safe storage and deferred dismantlement activities, compilation of unit cost factors, and safety assessment details

Technology, safety, and costs of decommissioning reference nuclear research and test reactors. Main report

International Nuclear Information System (INIS)

Konzek, G.J.; Ludwick, J.D.; Kennedy, W.E. Jr.; Smith, R.I.

1982-03-01

Safety and Cost Information is developed for the conceptual decommissioning of two representative licensed nuclear research and test reactors. Three decommissioning alternatives are studied to obtain comparisons between costs (in 1981 dollars), occupational radiation doses, potential radiation dose to the public, and other safety impacts. The alternatives considered are: DECON (immediate decontamination), SAFSTOR (safe storage followed by deferred decontamination), and ENTOMB (entombment). The study results are presented in two volumes. Volume 1 (Main Report) contains the results in summary form

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

Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities. Specific Safety Guide

International Nuclear Information System (INIS)

2016-01-01

This Safety Guide provides guidance on the predisposal management of all types of radioactive waste (including spent nuclear fuel declared as waste and high level waste) generated at nuclear fuel cycle facilities. These waste management facilities may be located within larger facilities or may be separate, dedicated waste management facilities (including centralized waste management facilities). The Safety Guide covers all stages in the lifetime of these facilities, including their siting, design, construction, commissioning, operation, and shutdown and decommissioning. It covers all steps carried out in the management of radioactive waste following its generation up to (but not including) disposal, including its processing (pretreatment, treatment and conditioning). Radioactive waste generated both during normal operation and in accident conditions is considered

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

Final project report, TA-35 Los Alamos Power Reactor Experiment No. II (LAPRE II) decommissioning project

International Nuclear Information System (INIS)

Montoya, G.M.

1992-01-01

This final report addresses the decommissioning of the LAPRE II Reactor, safety enclosure, fuel reservoir tanks, emergency fuel recovery system, primary pump pit, secondary loop, associated piping, and the post-remediation activities. Post-remedial action measurements are also included. The cost of the project, including Phase I assessment and Phase II remediation was approximately $496K. The decommissioning operation produced 533 m 3 of low-level solid radioactive waste and 5 m 3 of mixed waste

Decommissioning of AECL Whiteshell laboratories - 16311

International Nuclear Information System (INIS)

Koroll, Grant W.; Bilinsky, Dennis M.; Swartz, Randall S.; Harding, Jeff W.; Rhodes, Michael J.; Ridgway, Randall W.

2009-01-01

Whiteshell Laboratories (WL) is a Nuclear Research and Test Establishment near Winnipeg, Canada, operated by AECL since the early 1960's and now under decommissioning. WL occupies approximately 4400 hectares of land and employed more than 1000 staff up to the late-1990's, when the closure decision was made. Nuclear facilities at WL included a research reactor, hot cell facilities and radiochemical laboratories. Programs carried out at the WL site included high level nuclear fuel waste management research, reactor safety research, nuclear materials research, accelerator technology, biophysics, and industrial radiation applications. In preparation for decommissioning, a comprehensive environmental assessment was successfully completed [1] and the Canadian Nuclear Safety Commission issued a six-year decommissioning licence for WL starting in 2003 - the first decommissioning licence issued for a Nuclear Research and Test Establishment in Canada. This paper describes the progress in this first six-year licence period. A significant development in 2006 was the establishment of the Nuclear Legacy Liabilities Program (NLLP), by the Government of Canada, to safely and cost effectively reduce, and eventually eliminate the nuclear legacy liabilities and associated risks, using sound waste management and environmental principles. The NLLP endorsed an accelerated approach to WL Decommissioning, which meant advancing the full decommissioning of buildings and facilities that had originally been planned to be decontaminated and prepared for storage-with-surveillance. As well the NLLP endorsed the construction of enabling facilities - facilities that employ modern waste handling and storage technology on a scale needed for full decommissioning of the large radiochemical laboratories and other nuclear facilities. The decommissioning work and the design and construction of enabling facilities are fully underway. Several redundant non-nuclear buildings have been removed and redundant

Technologies for gas cooled reactor decommissioning, fuel storage and waste disposal. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

1998-09-01

Gas cooled reactors (GCRs) and other graphite moderated reactors have been important part of the world's nuclear programme for the past four decades. The wide diversity in status of this very wide spectrum of plants from initial design to decommissioning was a major consideration of the International Working group on Gas Cooled Reactors which recommended IAEA to convene a Technical Committee Meeting dealing with GCR decommissioning, including spent fuel storage and radiological waste disposal. This Proceedings includes papers 25 papers presented at the Meeting in three sessions entitled: Status of Plant Decommissioning Programmes; Fuels Storage Status and Programmes; waste Disposal and decontamination Practices. Each paper is described here by a separate abstract

International intercomparison and harmonization projects for demonstrating the safety of radioactive waste management, decommissioning and radioactive waste disposal

International Nuclear Information System (INIS)

Metcalf, Phil; O'Donnell, Patricio; Jova Sed, Luis; Batandjieva, Borislava; Rowat, John; Kinker, Monica

2008-01-01

Full text: The Joint Convention on the safety of spent fuel management and the safety of radioactive waste management and the international safety standards on radioactive waste management, decommissioning and radioactive waste disposal call for assessment and demonstration of the safety of facilities and activities; during siting, design and construction prior to operation, periodically during operation and at the end of lifetime or upon closure of a waste disposal facility. In addition, more recent revisions of the international safety standards require the development of a safety case for such facilities and activities, documentation presenting all the arguments supporting the safety of the facilities and activities covering site and engineering features, quantitative safety assessment and management systems. Guidance on meeting these safety requirements also indicates the need for a graded approach to safety assessment, with the extent and complexity of the assessment being proportional to the complexity of the activity or facility, and its propensity for radiation hazard. Safety assessment approaches and methodologies have evolved over several decades and international interest in these developments has been considerable as they can be complex and often subjective, which has led to international projects being established aimed at harmonization. The IAEA has sponsored a number of such initiatives, particularly in the area of disposal facility safety, but more recently in the areas of pre disposal waste management and decommissioning, including projects known as ISAM, ASAM, SADRWMS and DeSa. The projects have a number of common aspects including development of standardized methodological approaches, application on test cases and assessment review; they also have activity and facility specific elements. The paper presents an overview of the projects, the outcomes from the projects to date and their future direction aimed very much at practical application of

New start of nuclear-powered ship 'Mutsu'. 2. On decommissioning works

International Nuclear Information System (INIS)

Matsuo, Ryusuke

1996-01-01

It was decided that 'Mutsu' is decommissioned immediately after the finish of the experimental voyage in the fundamental plan. Therefore, Nuclear-powered Ship Decommissioning Department was organized in Japan Atomic Energy Research Institute in 1992, and the investigation was begun on the measures to abolish the reactor facilities of 'Mutsu'. The fundamental plan was decided to adopt the removal and isolation method for the reactor room including the reactor and shields, to use the ship as the conventional propulsion ocean research ship, and to exhibit the removed reactor chamber under proper control. The required technical assessment and safety examination were carried out based on this fundamental plan. The technical feasibility studies were carried out on the safety of placing 'Mutsu' on a semisubmersible barge, the safety of the cutting works of the hull, the safety of a floating crane, and the safety at the time of accidents. Taking-out of fuel assemblies, the removal works of machinery and equipment in the reactor auxiliary machine room and others, the removal and transport works of the reactor room in a lump, the construction works of the preservation building, and the safety control on the decommissioning works are described. (K.I.)

Plan for fully decontaminating and decommissioning of the Westinghouse Advanced Reactors Division Fuel Laboratories at Cheswick, Revision 3

International Nuclear Information System (INIS)

1982-01-01

The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of all bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. This volume contains the following 3 attachments: (1) Plan for Fully Decontamination and Decommissioning of the Westinghouse Advanced Reactors Division Fuel Laboratories at Cheswick; (2) Environmental Assessment for Decontamination and Decommissioning the Westinghouse Advanced Reactors Division Plutonium Fuel Laboratories, Cheswick, PA; and (3) WARD-386, Quality Assurance Program Description for Decontamination and Decommissioning Activities

Decommissioning of units 1 - 4 at Kozloduy nuclear power plant in Bulgaria

International Nuclear Information System (INIS)

Dishkova, Denitsa

2014-01-01

Nuclear safety and security are absolute priorities for the European Union countries and this applies not only to nuclear power plants in operation but also to decommissioning. In terms of my technical background and my working experience in the field of licensing and environmental impact assessment during the decommissioning of Units 1 to 4 at Kozloduy Nuclear Power Plant (KNPP) in Bulgaria, I decided to present the strategy for decommissioning of Units 1 to 4 at KNPP which was selected and followed to achieve safe and effective decommissioning process. The selected strategy in each case must meet the legislative framework, to ensure safe management of spent fuel and radioactive waste, to provide adequate funding and to lead to positive socio-economic impact. The activities during the decommissioning generate large volume of waste. In order to minimize their costs and environmental impact it should be given a serious consideration to the choice, the development and the implementation of the most adequate process for treatment and the most appropriate measurement techniques. The licensing process of the decommissioning activities is extremely important and need to cope with all safety concerns and ensure optimal waste management. (authors)

Liabilities identification and long-term management decommissioning of nuclear installations in Slovak Republic

International Nuclear Information System (INIS)

Burclova, Jana; Konecny, Ladislav

2003-01-01

The decommissioning is defined as the safe removal of nuclear facilities from service and reduction of residual radioactivity and/or risk to a level enabling their use for the purpose of another nuclear facility or unrestricted use (site release) and termination of license. The Legal Basis for Decommissioning and Waste Management are described in 4 acts: - 1. Act 130/98 Coll. on peaceful use of nuclear energy (Atomic Act); - 2. The act No 127/1994 Coll. on environmental impact assessment (amended 2000); - 3. The act No 254/1994 Coll. on creation of state found for NPP decommissioning, spent fuel management and disposal investment (amended 2000, 2001); 4. The act No 272/1994 Coll. on protection of public health (amended 1996,2000). The licensing process for radioactive waste management installations as for all nuclear installations is running in following principal steps. The permits for siting, construction, operation including commissioning, individual steps of decommissioning and site release are issued by municipal environmental office on the basis of the Act No 50/1976 Coll. on territorial planning and construction rules and the decisions of the Nuclear regulatory Authority (UJD SR) based on the Atomic Act. The safety documentation shall be prepared by applicant and it is subject of the regulatory bodies approval, for nuclear safety is responsible UJD SR, for radiation protection Ministry of Health, for fire protection Ministry of Interior and for general safety Ministry of Labour, Social Policy and Family. UJD SR issues the permit for each decommissioning phase based on review and approval of safety documentation. Decommissioning Strategy of Slovak Republic was strongly influenced by the changes of Waste Management Strategy. During the last time UJD SR dedicated the great effort to principal improvement of legislation, to cooperation with Ministry of Economy with the aim to create rules for financial sources for decommissioning activities and to enforcement of

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

Transuranium contamination in BWRs after fuel accidents and its impact on decommissioning exposures and costs

Energy Technology Data Exchange (ETDEWEB)

Lundgren, K.

1996-12-01

The theme of the present study is to quantify the amount of transuranium activity in different parts of the plant after various fuel accidents, and which impact such contamination has on radiation exposure and costs for decommissioning the plant. The consequences of four different accident degrees have been treated: Common fuel failures, e.g. in line with recent experiences from Swedish BWRs; Fuel channel obstruction resulting in partial melting of one fuel assembly; Total loss of electric power resulting in partial meltdown of the core, but with primary circuit intact preventing a massive contamination of the containment; A LOCA followed by a core meltdown and melting and penetration of the reactor pressure vessel. The amount of transuranium activity distributed, the form of this activity and the plant contamination are evaluated for these accidents. The costs and exposures have been split up on cleanup activities after the accident and decommissioning. 75 refs.

Transuranium contamination in BWRs after fuel accidents and its impact on decommissioning exposures and costs

International Nuclear Information System (INIS)

Lundgren, K.

1996-12-01

The theme of the present study is to quantify the amount of transuranium activity in different parts of the plant after various fuel accidents, and which impact such contamination has on radiation exposure and costs for decommissioning the plant. The consequences of four different accident degrees have been treated: Common fuel failures, e.g. in line with recent experiences from Swedish BWRs; Fuel channel obstruction resulting in partial melting of one fuel assembly; Total loss of electric power resulting in partial meltdown of the core, but with primary circuit intact preventing a massive contamination of the containment; A LOCA followed by a core meltdown and melting and penetration of the reactor pressure vessel. The amount of transuranium activity distributed, the form of this activity and the plant contamination are evaluated for these accidents. The costs and exposures have been split up on cleanup activities after the accident and decommissioning. 75 refs

Fuel and canister process report for the safety assessment SR-Can

International Nuclear Information System (INIS)

Werme, Lars

2006-10-01

This report documents fuel and canister processes identified as relevant to the long-term safety of a KBS-3 repository. It forms an important part of the reporting of the safety assessment SR-Can. The detailed assessment methodology, including the role of the process report in the assessment, is described in the SR-Can Main report. The report is written by, and for, experts in the relevant scientific fields. It should though be possible for a generalist in the area of long-term safety assessments of geologic nuclear waste repositories to comprehend the contents of the report. The report is an important part of the documentation of the SR-Can project and an essential reference within the project, providing a scientifically motivated plan for the handling of geosphere processes. It is, furthermore, foreseen that the report will be essential for reviewers scrutinising the handling of geosphere issues in the SR-Can assessment. Several types of fuel will be emplaced in the repository. For the reference case with 40 years of reactor operation, the fuel quantity from boiling water reactors, BWR fuel, is estimated at 7,000 tonnes, while the quantity from pressurized water reactors, PWR fuel, is estimated at about 2,300 tonnes. In addition, 23 tonnes of mixed-oxide fuel (MOX) fuel of German origin from BWR and PWR reactors and 20 tonnes of fuel from the decommissioned heavy water reactor in Aagesta will be disposed of. To allow for future changes in the Swedish nuclear programme, the safety assessment assumes a total of 6,000 canister corresponding to 12,000 tonnes of fuel

Fuel and canister process report for the safety assessment SR-Can

Energy Technology Data Exchange (ETDEWEB)

Werme, Lars (ed.)

2006-10-15

This report documents fuel and canister processes identified as relevant to the long-term safety of a KBS-3 repository. It forms an important part of the reporting of the safety assessment SR-Can. The detailed assessment methodology, including the role of the process report in the assessment, is described in the SR-Can Main report. The report is written by, and for, experts in the relevant scientific fields. It should though be possible for a generalist in the area of long-term safety assessments of geologic nuclear waste repositories to comprehend the contents of the report. The report is an important part of the documentation of the SR-Can project and an essential reference within the project, providing a scientifically motivated plan for the handling of geosphere processes. It is, furthermore, foreseen that the report will be essential for reviewers scrutinising the handling of geosphere issues in the SR-Can assessment. Several types of fuel will be emplaced in the repository. For the reference case with 40 years of reactor operation, the fuel quantity from boiling water reactors, BWR fuel, is estimated at 7,000 tonnes, while the quantity from pressurized water reactors, PWR fuel, is estimated at about 2,300 tonnes. In addition, 23 tonnes of mixed-oxide fuel (MOX) fuel of German origin from BWR and PWR reactors and 20 tonnes of fuel from the decommissioned heavy water reactor in Aagesta will be disposed of. To allow for future changes in the Swedish nuclear programme, the safety assessment assumes a total of 6,000 canister corresponding to 12,000 tonnes of fuel.

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)

Apollo decommissioning project, Apollo, Pennsylvania. Final technical report

International Nuclear Information System (INIS)

1997-01-01

In November, 1991 Babcock and Wilcox (B and W) received a grant to partially fund the decommissioning of the former Apollo Nuclear Fuel Facility. The decommissioning was performed in accordance with a Nuclear Regulatory Commission (NRC) approved decommissioning plan. This report summarizes the decommissioning of the Apollo Nuclear Fuel Facility and the radiological surveying of the site to demonstrate that these decommissioning activities were effective in reducing residual activity well below NRC's criteria for release for unrestricted use. The Apollo Nuclear Fuel Facility was utilized by the Nuclear Materials and Equipment Corporation (NUMEC) and B and W for nuclear research and production under Atomic Energy Commission and Department of Energy (DOE) contracts during 20 plus years of nuclear fuel manufacturing operations

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

Decommissioning Handbook

International Nuclear Information System (INIS)

Cusack, J.G.; Dalfonso, P.H.; Lenyk, R.G.

1994-01-01

The Decommissioning Handbook provides technical guidance on conducting decommissioning projects. Information presented ranges from planning logic, regulations affecting decommissioning, technology discussion, health and safety requirements, an developing a cost estimate. The major focus of the handbook are the technologies -- decontamination technologies, waste treatment, dismantling/segmenting/demolition, and remote operations. Over 90 technologies are discussed in the handbook providing descriptions, applications, and advantages/disadvantages. The handbook was prepared to provide a compendium of available or potentially available technologies in order to aid the planner in meeting the specific needs of each decommissioning project. Other subjects presented in the Decommissioning Handbook include the decommissioning plan, characterization, final project configuration based planning, environmental protection, and packaging/transportation. These discussions are presented to complement the technologies presented in the handbook

Roadmap and performance carried out during Ciemat site decommissioning

International Nuclear Information System (INIS)

Quinones, Javier; Diaz Diaz, Jose Luis

2005-01-01

Ciemat (Research Centre for Energy, Environment and Technology) located in the heart of the Ciudad Universitaria of Madrid, occupies a property of 20 Ha. Since its creation in 1951 as JEN, and in 1986 renowned as Ciemat, it has involved on R and D projects in the field of Energy and Environment, i.e., Nuclear Fission, Nuclear Fusion, Fossils Fuels, Renewable Energy. As a consequence of the R and D projects developed between 1951 - 1986 on Nuclear Fission field (fuel design, fabrication, characterization on irradiated fuels, safety studies, etc) and to the diversification of the goals as well, it is necessary to Decommissioning and Dismantling (D and D) from nuclear facilities (nuclear reactor, Hot Cells, Irradiation facility), buildings and soils. Preparations for D and D included a staged shutdown of operations, planning documentation and licensing for decommissioning. As a prerequisite to Ciemat application for a decommissioning license and nuclear environmental assessment was carried out according to Spanish Nuclear Council (CSN) and approval of the site decommissioning project was obtained in 2000 and valid until December 31, 2006. Since 2001 - 2003 is underway and focussed on the radiological characterization of the site (divided in pieces of ground), when each piece of ground is characterized a planning for D and D is presented to CSN in order to obtain a license for actuation. Nowadays several pieces of ground are decontaminated and modifications have been done in order to achieve a safe state of storage-with-surveillance. Later phases have planned waste management improvements for selected wastes already on temporally storage, eventually followed by final decommissioning of facilities and buildings and cleaning of contaminants from soils and removal of waste from the site. This paper describes the planning, nuclear and environment assessment and descriptions of decommissioning activities currently underway at Ciemat. (Author)

Planning of the BN-350 reactor decommissioning

International Nuclear Information System (INIS)

Klepikov, A.Kh.; Tazhibayeva, I.L.; Zhantikin, T.M.; Baldov, A.N.; Nazarenko, P.I.; Koltyshev, S.M.; Wells, P.B.

2002-01-01

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

AREVA decommissioning strategy and programme

International Nuclear Information System (INIS)

Gay, A.

2008-01-01

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

Decommissioning licensing procedure

International Nuclear Information System (INIS)

Perello, M.

1979-01-01

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

Decommissioning and dismantling of nuclear and fuel cycle facilitites in Spain

International Nuclear Information System (INIS)

Gravalos, J.M.; Alamo, S.

1992-01-01

In the recent past, and as a consequence of a fire in the turbine island of the Vandellos I Graphite Gas type Nuclear Plant, which damaged the facility to a point that recovery was not judged economically feasible, the authorities decided on the final shutdown of the plant. Several studies were performed in order to select the dismantling strategy to be adopted. In spite of Valdellos I being the first commercial reactor to be decommissioned in Spain, several research reactors and fuel cycle facilities, which have reached the end of their commercial lives, are at present at different stages of their dismantling and decommissioning process as is described further. The development of an exemption policy for below regulatory concern wastes is considered a very significant issue regarding decommissioning as it has a large impact on radioactive waste volumes, and thus on costs. Aware of this problem ENRESA together with Spanish regulatory authorities are working in close cooperation with CEC research programs to complete the development of criteria and methodologies for the application of exemption practices in Spain

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Appendices. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01

Appendices are presented concerning the evaluations of decommissioning financing alternatives; reference site description; reference BWR facility description; radiation dose rate and concrete surface contamination data; radionuclide inventories; public radiation dose models and calculated maximum annual doses; decommissioning methods; generic decommissioning information; immediate dismantlement details; passive safe storage, continuing care, and deferred dismantlement details; entombment details; demolition and site restoration details; cost estimating bases; public radiological safety assessment details; and details of alternate study bases.

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)

CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 4 - FUEL CHANNEL ASSEMBLY

Directory of Open Access Journals (Sweden)

Gabi ROSCA FARTAT

2014-05-01

Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of these installations has become one of the 21st century’s great challenges. Each project may be managed differently, depending on the country, development policies, financial considerations, and the availability of qualified engineers or specialized companies to handle such projects. The principle objective of decommissioning is to place a facility into such a condition that there is no unacceptable risk from the decommissioned facility to public health and safety of the environment. In order to ensure that at the end of its life the risk from a facility is within acceptable bounds, action is normally required. The overall decommissioning strategy is to deliver a timely, costeffective program while maintaining high standards of safety, security and environmental protection. If facilities were not decommissioned, they could degrade and potentially present an environmental radiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is not considered to be an acceptable alternative to decommissioning. The final aim of decommissioning is to recover the geographic site to its original condition.

CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 2 - FUEL CHANNEL PRESENTATION

Directory of Open Access Journals (Sweden)

Gabi ROSCA FARTAT

2014-05-01

Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of these installations has become one of the 21st century’s great challenges. Each project may be managed differently, depending on the country, development policies, financial considerations, and the availability of qualified engineers or specialized companies to handle such projects. The principle objective of decommissioning is to place a facility into such a condition that there is no unacceptable risk from the decommissioned facility to public health and safety of the environment. In order to ensure that at the end of its life the risk from a facility is within acceptable bounds, action is normally required. The overall decommissioning strategy is to deliver a timely, costeffective program while maintaining high standards of safety, security and environmental protection. If facilities were not decommissioned, they could degrade and potentially present an environmental radiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is not considered to be an acceptable alternative to decommissioning.The final aim of decommissioning is to recover the geographic site to its original condition.

CONSIDERATIONS FOR THE DEVELOPMENT OF A DEVICE FOR THE DECOMMISSIONING OF THE HORIZONTAL FUEL CHANNELS IN THE CANDU 6 NUCLEAR REACTOR PART 3 - FUEL CHANNEL REFERENCES

Directory of Open Access Journals (Sweden)

Gabi ROSCA FARTAT

2014-05-01

Full Text Available As many nuclear power plants are reaching their end of lifecycle, the decommissioning of these installations has become one of the 21st century’s great challenges. Each project may be managed differently, depending on the country, development policies, financial considerations, and the availability of qualified engineers or specialized companies to handle such projects. The principle objective of decommissioning is to place a facility into such a condition that there is no unacceptable risk from the decommissioned facility to public health and safety of the environment. In order to ensure that at the end of its life the risk from a facility is within acceptable bounds, action is normally required. The overall decommissioning strategy is to deliver a timely, cost-effective program while maintaining high standards of safety, security and environmental protection. If facilities were not decommissioned, they could degrade and potentially present an environmental radiological hazard in the future. Simply abandoning or leaving a facility after ceasing operations is not considered to be an acceptable alternative to decommissioning. The final aim of decommissioning is to recover the geographic site to its original condition.

Principles of record keeping for decommissioning purposes

International Nuclear Information System (INIS)

Laraia, M.

2003-01-01

At the siting and conceptual design stage of a nuclear facility the first records pertaining to that facility are produced and stored. Subsequent phases in the facility's life cycle (detailed design, construction, commissioning, operation and shutdown) will include the production and retention of a large variety of records. Design, as-built drawings and operational records are essential for safe and efficient operation of any nuclear facility. This set of records is constantly updated and augmented during operation. Records from all phases of a nuclear facility are important for planning its decommissioning. Although not all of these records need to be included explicitly in the decommissioning plan itself, the process of initial, ongoing and final planning utilizes pertinent records for, and ultimately achieves, safe and cost effective decommissioning. When a nuclear facility is shutdown for decommissioning, current operating experience may be lost. Therefore, one important element of planning is to identify, secure and store appropriate operational records to support decommissioning. This process is preferably initiated during the design and construction phase and continues throughout operation including shutdown. Part of the records inventory from operation will become records for decommissioning and it is cost effective to identify these records before final facility shutdown. Experience shows that lack of attention to record keeping may result in an undue waste of time, other resources and additional costs. The newly established Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management recognizes the importance of keeping decommissioning-related records. In addition, the systematic management of records is an essential part of quality assurance and is often a licence condition. A good comprehensive decommissioning records management system (RMS) is one specific application of the broader concepts of 'Protection

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

Safe decommissioning of the Romanian VVR-S research reactor

International Nuclear Information System (INIS)

Garlea, C.; Garlea, I.; Kelerman, C.; Rodna, A.

2002-01-01

The VVR-S Romania research reactor was operated between 1957-1997, at 2 MW nominal power, for research and radioisotopical production. The detailed decommissioning plan was developed between 1995-1998, in the frame of the International Atomic Energy Agency Technical assistance project ROM/9/017. The proposed strategy agreed by the counterpart as well as international experts was stage 1. In 1997, an independent analysis performed by European Commission experts, in the frame of PHARE project PH04.1/1994 was dedicated to the 'Study of Soviet Design Research Reactors', had consolidated the development of the project emphasizing technical options of safe management for radioactive wastes and VVR-S spent fuel. The paper presents the main technical aspects as well as those of social impact, which lead to the establishment of strategy for safe management of decommissioning. Technical analysis of the VVR-S reactor and associated radwaste facilities (Radioactive Waste Treatment Plant - Magurele and National Repository Baita-Bihor) proved the possibility of the classical method utilization for dismantling of the facility and treatment-conditioning-disposal of the arrised wastes in safe conditions. The decommissioning plan at stage 2 has been developed based on radiological safety assessment, evaluation of radwaste inventory (removed as well as preserved on site), cost analysis and environmental impact. Technical data were provided by the R and D programme including neutron calculations and experiments, radiological characterizing (for facility and its influence area), seismic analysis and environmental balance during the operation and after shut down of the reactor. A special chapter is dedicated to regulatory issues concerning the development of decommissioning under nuclear safety. Based on the Fundamental Norms of Radiological Safety, the Regulatory Body defined the clearance levels and safety criteria for the process. The development of National Norms for the

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

Waste management, decommissioning and environmental restoration for Canada's nuclear activities. Proceedings

International Nuclear Information System (INIS)

2011-01-01

The Canadian Nuclear Society conference on Waste Management, Decommissioning and Environmental Restoration for Canada's Nuclear Activities was held in Toronto, Ontario, Canada on September 11-14, 2011. The conference provided a forum for discussion of the status and proposed future directions of technical, regularly, environmental, social and economic aspects of radioactive waste management, nuclear facility decommissioning, and environmental restoration activities for Canadian nuclear facilities. The conference included both plenary sessions and sessions devoted to more detailed technical issues. The plenary sessions were focussed on three broad themes: the overall Canadian program; low and intermediate waste; and, international perspectives. Topics of the technical sessions included: OPG's deep geologic repository for low and intermediate level waste; stakeholder interactions; decommissioning projects; uranium mine waste management; used fuel repository - design and safety assessment; federal policies, programs and oversight; regulatory considerations; aboriginal traditional knowledge; geological disposal - CRL site classification; geological disposal - modelling and engineered barriers; Port Hope Area Initiative; waste characterization; LILWM - treatment and processing; decommissioning projects and information management; international experience; environmental remediation; fuel cycles and waste processing.

Guidelines of Decommissioning Schedule Establishment

Energy Technology Data Exchange (ETDEWEB)

Oh, Jae Yong; Yun, Taesik; Kim, Younggook; Kim, Hee-Geun [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

Decommissioning has recently become an issue highlighted in Korea due to the Permanent Shutdown (PS) of Kori-1 plant. Since Korea Hydro and Nuclear Power (KHNP) Company decided the PS of Kori-1 instead of further continued operation, Kori-1 will be the first decommissioning plant of the commercial reactors in Korea. Korean regulatory authority demands Initial Decommissioning Plan (IDP) for all the plants in operation and under construction. In addition, decommissioning should be considered for the completion of the life cycle of NPPs. To date, Korea has no experience regarding decommissioning of the commercial reactor and a lot of uncertainties will be expected due to its site-specific factors. However, optimized decommissioning process schedule must be indispensable in the safety and economic efficiency of the project. Differed from USA, Korea has no experience and know-hows of the operation and site management for decommissioning. Hence, in Korea, establishment of decommissioning schedule has to give more weight to safety than precedent cases. More economical and rational schedule will be composed by collecting and analyzing the experience data and site-specific data and information as the decommissioning progresses. In a long-range outlook, KHNP having capability of NPP decommissioning will try to decommissioning business in Korea and foreign countries.

New safety experiments in decommissioned superheated steam reactor at Karlstein

International Nuclear Information System (INIS)

Koerting, K.

1986-01-01

This article gives a concise summary of the Status Report of the Superheated Steam Reactor Safety Program (PHDR) Project, held at KfK on Dec. 5, 1985. The results discussed dealt with fire experiments, shock tests simulating airplane crashes, temperature shocks in the reactor pressure vessel, studies of crack detection in pressure vessels and blasting experiments associated with nuclear plant decommissioning

Training for decommissioning

International Nuclear Information System (INIS)

Dietzold, A.

2009-01-01

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

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

International Nuclear Information System (INIS)

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

Energy Technology Data Exchange (ETDEWEB)

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices.

On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden

Energy Technology Data Exchange (ETDEWEB)

Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter; Kristofova, Kristina; Tatransky, Peter; Zachar, Matej [DECOM Slovakia, spol. s.r.o., J. Bottu 2, SK-917 01 Trnava (Slovakia); Lindskog, Staffan [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

2007-03-15

The presented report is focused on tentative calculations of basic decommissioning parameters such as costs, manpower and exposure of personnel for activities of older nuclear facility decommissioning in Sweden represented by Intermediate storage facility for spent fuel in Studsvik, by means of calculation code OMEGA. This report continuously follows up two previous projects, which described methodology of cost estimates of decommissioning with an emphasis to derive cost functions for alpha contaminated material and implementation of the advanced decommissioning costing methodology for Intermediate Storage facility for Spent Fuel in Studsvik. The main purpose of the presented study is to demonstrate the trial application of the advanced costing methodology using OMEGA code for Intermediate Storage Facility for Spent Fuel in Studsvik. Basic work packages presented in report are as follows: 1. Analysis and validation input data on Intermediate Storage Facility for Spent Fuel and assemble a database suitable for standardised decommissioning cost calculations including radiological parameters, 2. Proposal of range of decommissioning calculations and define an extent of decommissioning activities, 3. Defining waste management scenarios for particular material waste streams from Intermediate Storage Facility for Spent Fuel, 4. Developing standardised cost calculation structure applied for Intermediate Storage Facility for Spent Fuel decommissioning calculation and 5. Performing tentative decommissioning calculations for Intermediate Storage Facility for Spent Fuel by OMEGA code. Calculated parameters of decommissioning are presented in structure according to Proposed Standardized List of Items for Costing Purposes. All parameters are documented and summed up in both table and graphic forms in text and Annexes. The presented report documents availability and applicability of methodology for evaluation of costs and other parameters of decommissioning in a form implemented

On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden

International Nuclear Information System (INIS)

Vasko, Marek; Daniska, Vladimir; Ondra, Frantisek; Bezak, Peter; Kristofova, Kristina; Tatransky, Peter; Zachar, Matej; Lindskog, Staffan

2007-03-01

The presented report is focused on tentative calculations of basic decommissioning parameters such as costs, manpower and exposure of personnel for activities of older nuclear facility decommissioning in Sweden represented by Intermediate storage facility for spent fuel in Studsvik, by means of calculation code OMEGA. This report continuously follows up two previous projects, which described methodology of cost estimates of decommissioning with an emphasis to derive cost functions for alpha contaminated material and implementation of the advanced decommissioning costing methodology for Intermediate Storage facility for Spent Fuel in Studsvik. The main purpose of the presented study is to demonstrate the trial application of the advanced costing methodology using OMEGA code for Intermediate Storage Facility for Spent Fuel in Studsvik. Basic work packages presented in report are as follows: 1. Analysis and validation input data on Intermediate Storage Facility for Spent Fuel and assemble a database suitable for standardised decommissioning cost calculations including radiological parameters, 2. Proposal of range of decommissioning calculations and define an extent of decommissioning activities, 3. Defining waste management scenarios for particular material waste streams from Intermediate Storage Facility for Spent Fuel, 4. Developing standardised cost calculation structure applied for Intermediate Storage Facility for Spent Fuel decommissioning calculation and 5. Performing tentative decommissioning calculations for Intermediate Storage Facility for Spent Fuel by OMEGA code. Calculated parameters of decommissioning are presented in structure according to Proposed Standardized List of Items for Costing Purposes. All parameters are documented and summed up in both table and graphic forms in text and Annexes. The presented report documents availability and applicability of methodology for evaluation of costs and other parameters of decommissioning in a form implemented

Enhanced productivity in reactor decommissioning and waste management

International Nuclear Information System (INIS)

Wasinger, Karl

2014-01-01

As for any industrial facility, the service live of nuclear power plants, fuel cycle facilities, research and test reactors ends. Decision for decommissioning such facilities may be motivated by technical, economical or political reasons or a combination of it. As of today, a considerable number of research reactors, fuel cycle facilities and power reactors have been completely decommissioned. However, the end point of such facilities' lifetime is achieved, when the facility is finally removed from regulatory control and the site becomes available for further economical utilization. This process is commonly known as decommissioning and involves detailed planning of all related activities, radiological characterization, dismantling, decontamination, clean-up of the site including treatment and packaging of radioactive and/or contaminated material not released for unrestricted recycling or industrial disposal. Decommissioning requires adequate funding and suitable measures to ensure safety while addressing stakeholders' requirements on occupational health, environment, economy, human resources management and the socioeconomic effects to the community and the region. One important aspect in successful management of decommissioning projects and dismantling operation relates to the economical impact of the endeavor, primarily depending on the selected strategy and, as from commencement of dismantling, on total duration until the end point is achieved. Experience gained by Areva in executing numerous decommissioning projects during past 2 decades shows that time injury free execution and optimum productivity turns out crucial to project cost. Areva develops and implements specific 'performance improvement plans' for each of its projects which follow the philosophy of operational excellence based on Lean Manufacturing principles. Means and methods applied in implementation of these plans and improvements achieved are described and examples are given on the way Areva

Enhanced productivity in reactor decommissioning and waste management

Energy Technology Data Exchange (ETDEWEB)

Wasinger, Karl [Areva GmbH, Offenbach (Germany)

2014-04-15

As for any industrial facility, the service live of nuclear power plants, fuel cycle facilities, research and test reactors ends. Decision for decommissioning such facilities may be motivated by technical, economical or political reasons or a combination of it. As of today, a considerable number of research reactors, fuel cycle facilities and power reactors have been completely decommissioned. However, the end point of such facilities' lifetime is achieved, when the facility is finally removed from regulatory control and the site becomes available for further economical utilization. This process is commonly known as decommissioning and involves detailed planning of all related activities, radiological characterization, dismantling, decontamination, clean-up of the site including treatment and packaging of radioactive and/or contaminated material not released for unrestricted recycling or industrial disposal. Decommissioning requires adequate funding and suitable measures to ensure safety while addressing stakeholders' requirements on occupational health, environment, economy, human resources management and the socioeconomic effects to the community and the region. One important aspect in successful management of decommissioning projects and dismantling operation relates to the economical impact of the endeavor, primarily depending on the selected strategy and, as from commencement of dismantling, on total duration until the end point is achieved. Experience gained by Areva in executing numerous decommissioning projects during past 2 decades shows that time injury free execution and optimum productivity turns out crucial to project cost. Areva develops and implements specific 'performance improvement plans' for each of its projects which follow the philosophy of operational excellence based on Lean Manufacturing principles. Means and methods applied in implementation of these plans and improvements achieved are described and examples are given on

IAEA Global Support of Decommissioning Implementation with a Focus on Advanced Technologies

International Nuclear Information System (INIS)

Michal, Vladimir; )

2017-01-01

Recently there are about 140 power reactors in decommissioning phase worldwide excluding 17+ that might be considered as decommissioned. In addition, more than 400 other nuclear facilities, such as research reactors or nuclear fuel cycle facilities, have been shutdown for decommissioning, have been undergoing active decommissioning or have already been fully dismantled. The IAEA provides various kind of support for Member States including publication of safety and technical reports providing guidance, recommendations, experiences, good practices and lessons learned covering the preparatory and implementation decommissioning phases. Many training courses, workshops, seminars etc. were organized to support sharing of good practices among specialists and organizations involved. In line with the non-technical aspects, such as decommissioning planning, costing, managerial approaches etc., there are also presented and discussed technical solutions often with a focus on the advanced technologies to be considered. Several completed and ongoing IAEA initiatives partially or fully address the advanced approaches and techniques to support safe and effective implementation of decommissioning projects. The presentation will provide an overview of relevant activities organized so far and perspectives of the IAEA on advanced technologies for decommissioning. (author)

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979

International Nuclear Information System (INIS)

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 1. Main report. Technical report, September 1977-October 1979

Energy Technology Data Exchange (ETDEWEB)

Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

1980-06-01

Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE.

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)

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

Planning the Decommissioning of Research Reactors

Energy Technology Data Exchange (ETDEWEB)

Podlaha, J., E-mail: pod@ujv.cz [Nuclear Research Institute Rez, 25068 Rez (Czech Republic)

2013-08-15

In the Czech Republic, three research nuclear reactors are in operation. According to the valid legislation, preliminary decommissioning plans have been prepared for all research reactors in the Czech Republic. The decommissioning plans shall be updated at least every 5 years. Decommissioning funds have been established and financial resources are regularly deposited. Current situation in planning of decommissioning of research reactors in the Czech Republic, especially planning of decommissioning of the LVR-15 research reactor is described in this paper. There appeared new circumstances having wide impact on the decommissioning planning of the LVR-15 research reactor: (1) Shipment of spent fuel to the Russian Federation for reprocessing and (2) preparation of processing of radioactive waste from reconstruction of the VVR-S research reactor (now LVR-15 research reactor). The experience from spent fuel shipment to the Russian Federation and from the process of radiological characterization and processing of radioactive waste from reconstruction of the VVR-S research reactor (now the LVR-15 research reactor) and the impact on the decommissioning planning is described in this paper. (author)

In-core power sharing and fuel requirement study for a decommissioning Boiling Water Reactor using the linear reactivity model

International Nuclear Information System (INIS)

Chen, Chung-Yuan; Tung, Wu-Hsiung; Yaur, Shung-Jung; Kuo, Weng-Sheng

2014-01-01

Highlights: • Linear reactivity model (LRM) was modified and applied to Boiling Water Reactor. • The power sharing and fuel requirement study of the last cycle and two cycles before decommissioning was implemented. • The loading pattern design concept for the cycles before decommissioning is carried out. - Abstract: A study of in-core power sharing and fuel requirement for a decommissioning BWR (Boiling Water Reactor) was carried out using the linear reactivity model (LRM). The power sharing of each fuel batch was taken as an independent variable, and the related parameters were set and modified to simulate actual cases. Optimizations of the last cycle and two cycles before decommissioning were both implemented; in the last-one-cycle optimization, a single cycle optimization was carried out with different upper limits of fuel batch power, whereas, in the two-cycle optimization, two cycles were optimized with different cycle lengths, along with two different optimization approaches which are the simultaneous optimization of two cycles (MO) and two successive single-cycle optimizations (SO). The results of the last-one-cycle optimization show that it is better to increase the fresh fuel power and decrease the thrice-burnt fuel power as much as possible. It also shows that relaxing the power limit is good to the fresh fuel requirement which will be reduced under lower power limit. On the other hand, the results of the last-two-cycle (cycle N-1 and N) optimization show that the MO is better than SO, and the power of fresh fuel batch should be decreased in cycle N-1 to save its energy for the next cycle. The results of the single-cycle optimization are found to be the same as that in cycle N of the multi-cycle optimization. Besides that, under the same total energy requirement of two cycles, a long-short distribution of cycle length design can save more fresh fuel

Study on the Operating Strategy of HVAC Systems for Nuclear Decommissioning Plant

Energy Technology Data Exchange (ETDEWEB)

Kim, Sung-hwan; Han, Sung-heum; Lee, Jae-gon [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

According as Kori nuclear power plant unit 1 was determined to be defueled in 2017, various studies on nuclear plant decommissioning have been performed. In nuclear decommissioning plant, HVAC systems with large fan and electric coil have to be operated for long periods of time to support various types of work from defueled phase to final dismantling phase. So, in view of safety and utility costs, their overall operating strategy need to be established prior to defueled phase. This study presents HVAC system operating strategy at each decommissioning phase, that is, defueled plant operating phase, SSCs(systems, structures, components) decontamination and dismantling phases. In defueled plant operating phase, all fuel assemblies in reactor vessel are transferred to spent fuel pool(SFP) permanently. In defueled plant operation phase, reduction of the operating system trains is more practicable than the introduction of new HVAC components with reduced capacity. And, based on the result of the accident analyses for this phase, HVAC design bases such as MCR habitability requirement can be mitigated. According to these results, associated SSCs also can be downgraded. In similar approach, at each phase of plant decommissioning, proper inside design conditions and operating strategies should be re-established.

Nuclear fission energy: new build, operation, fuel cycle and decommissioning in the international perspective

Energy Technology Data Exchange (ETDEWEB)

Niessen, Stefan [AREVA GmbH, Erlangen (Germany)

2015-07-01

Over 60 nuclear power reactors are in construction today and over 400 are connected to the grid. The presentation will show where. A nuclear new build project involves a team of several thousand people. Some pictures from ongoing new build projects will illustrate this. Using concrete examples from the AREVA group, the nuclear fuel cycle from uranium mines in Niger, Kazakhstan or Canada to chemical conversion, enrichment and fuel manufacturing will be explained. Also the recycling of used fuel and the fabrication of MOX fuel is addressed. The presentation closes with an overview on decommissioning and final storage projects.

Technology development for nuclear fuel cycle waste treatment - Decontamination, decommissioning and environmental restoration (1)

International Nuclear Information System (INIS)

Lee, Byung Jik; Won, Hui Jun; Yoon, Ji Sup and others

1997-12-01

Through the project of D econtamination, decommissioning and environmental restoration technology development , the following were studied. 1. Development of decontamination and repair technology for nuclear fuel cycle facilities 2. Development of dismantling technology 3. Environmental remediation technology development. (author). 95 refs., 45 tabs., 163 figs

Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Motta, E.S.; Sousa, A.L.B. de; Paiva, R.L.C. de; Mezrahi, A.

2013-01-01

The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

Importance of the licensing process on the safety culture in the Brazilian nuclear fuel cycle facilities

Energy Technology Data Exchange (ETDEWEB)

Motta, E.S.; Sousa, A.L.B. de; Paiva, R.L.C. de; Mezrahi, A., E-mail: emotta@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2013-07-01

The main objective of the Nuclear Fuel Cycle Facilities licensing processes is to ensure the safety of these installations in their entire life cycle (in the installation site selection, designing, construction, pre-operational tests, operational and decommissioning phases). The Brazilian licensing process requires from the operator, among others, before the operating license: (I) a Site Report and a Final Safety Analysis Report, ensuring that all safety related issues are adequately analyzed and understood; (II) a formal structured Management System focused on the installation safety; and (III) dissemination of safety related information to all involved operator employees and subcontractors. Therefore, these requirements reflect in an adequate operator actions and practices, ensuring a working environment with a high level of safety culture. (author)

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

Status of the Fort St. Vrain decommissioning

International Nuclear Information System (INIS)

Fisher, M.J.

1990-01-01

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

Decommissioning situation and research and development for the decommissioning of the commercial nuclear power station in Japan

International Nuclear Information System (INIS)

Yamamoto, Tatsumi.

1996-01-01

There are 48 commercial nuclear power stations in operation in Japan as of January 1, 1995, which supplies about 28% (2.2 x 10 8 MWh) of total annual electricity generation in FY 1992. Accordingly, as the nuclear power contributes so much in electricity generation, there is a growing concern in the public toward the safety on decommissioning nuclear power station. It is gravely important to secure the safety throughout the decommissioning. This paper discusses: the decommissioning situation in Japan; the Japanese national policy for decommissioning of commercial nuclear power stations; R and D for decommissioning of commercial nuclear power stations in Japan; and the present conditions of low-level radioactive wastes disposal in Japan

Government Assigns New Supervisory Task. Safe Decommissioning

International Nuclear Information System (INIS)

Lekberg, Anna

2003-01-01

When the Government decided to shutdown one of the two Barsebaeck reactors in February of 1998, it presented SKI with a task that came much earlier than expected; the supervision of the decommissioning of a reactor. As a result of proposals presented in Parliament, SKI began the formulation of a long-term strategy in 1997 for the inspection of a nuclear plant during the decommissioning process. As a preliminary task, SKI started a research programme dealing with the potential risks associated with the transition from normal operations through shutdown to final deconstruction of the power plant. Emphasis was laid on safety culture issues and on questions of organization, as opposed to an earlier stress on the purely technical aspects of decommissioning. After a long period of uncertainty, following much discussion, in July 1998 a Government decision was finally reached to shutdown the first reactor at Barsebaeck. This was carried out in November 1999. It is still uncertain as to when the other reactor will be decommissioned; a decision is expected at the earliest in 2004. This uncertainty, resulting from the prolonged decision making process, could be detrimental to the safety culture on the site; motivation could diminish, and key personnel could be lost. Decommissioning is a new phase in the life cycle of a plant, giving rise to new inspection issues of supervision. During the period of uncertainty, while awaiting SKI has identified ten key areas, dealing with the safety culture of the organization, in connection with the decommissioning of Barsebaeck 1. 1. Obtaining and retaining staff competence during decommissioning; 2. Sustaining organizational memory; 3. Identifying key organizational functions and management skills that are critical during the transition from operations to decommissioning. 4. Sustaining organizational viability and accountability for decommissioning; 5. Sustaining motivation and trust in management of dismantlement; 6. Overseeing

U.S. experience with organizational issues during decommissioning

International Nuclear Information System (INIS)

Durbin, N.E.; Harty, R.

1998-01-01

The report provides information from a variety of sources, including interviews with US NRC management and staff, interviews and discussions with former employees of a decommissioned plant, discussions with subject matter experts, and relevant published documents. The NRC has modified its rule regarding decommissioning requirements. Two key reasons for these modifications are that plants have been decommissioning early and for economic reasons instead of at the end of their license period and, a desire for a more efficient rule that would more effectively use NRC staff. NRC management and staff expressed the opinion that resource requirements for the regulatory have been higher than anticipated. Key observations about decommissioning included that: The regulator faces new challenges to regulatory authority and performance during decommissioning. The public concern over decommissioning activities can be very high. There are changes in the types of safety concerns during decommissioning. It is important to balance planning and the review of plans with verification of activities. There are important changes in the organizational context at the plant during decommissioning. Retention of key staff is important. In particular, the organizational memory about the plant that is in the staff should not be lost. Six key areas of risk during decommissioning are fuel storage, potential accidents that could cause an offsite release, inappropriate release of contaminated material, radiation protection of workers, industrial accidents, and shipment of hazardous materials. Deconstruction of one unit while a co-located unit is still operating could create risks with regard to shared systems, specific risks of dismantling activities and coordination and management. Experience with co-located units at one site in the US was that there was a lack of attention to the decommissioning plant

U.S. experience with organizational issues during decommissioning

Energy Technology Data Exchange (ETDEWEB)

Durbin, N.E. [MPD Consulting, Kirkland, WA (United States); Harty, R. [Battelle Pacific Northwest National Laboratory, Richland, WA (United States)

1998-01-01

The report provides information from a variety of sources, including interviews with US NRC management and staff, interviews and discussions with former employees of a decommissioned plant, discussions with subject matter experts, and relevant published documents. The NRC has modified its rule regarding decommissioning requirements. Two key reasons for these modifications are that plants have been decommissioning early and for economic reasons instead of at the end of their license period and, a desire for a more efficient rule that would more effectively use NRC staff. NRC management and staff expressed the opinion that resource requirements for the regulatory have been higher than anticipated. Key observations about decommissioning included that: The regulator faces new challenges to regulatory authority and performance during decommissioning. The public concern over decommissioning activities can be very high. There are changes in the types of safety concerns during decommissioning. It is important to balance planning and the review of plans with verification of activities. There are important changes in the organizational context at the plant during decommissioning. Retention of key staff is important. In particular, the organizational memory about the plant that is in the staff should not be lost. Six key areas of risk during decommissioning are fuel storage, potential accidents that could cause an offsite release, inappropriate release of contaminated material, radiation protection of workers, industrial accidents, and shipment of hazardous materials. Deconstruction of one unit while a co-located unit is still operating could create risks with regard to shared systems, specific risks of dismantling activities and coordination and management. Experience with co-located units at one site in the US was that there was a lack of attention to the decommissioning plant.

Decommissioning of NPP A1 - HWGCR type

International Nuclear Information System (INIS)

Burclova, J.

1998-01-01

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

Problems and concerns in radiation safety management related with decommissioning of tritium facility

International Nuclear Information System (INIS)

Kawano, Takao

2005-01-01

The tritium facility at the National Institute for Fusion Science has been closed in 2002 after decommissioning procedure. A number of works have been completed including technical measures and administrative documentations to be reported to the Ministry of Education, Culture, Sport, Science and Technology. All the operations were carried out in three successive terms; 1) survey and preparations, 2) actual decommissioning works, and 3) report of all procedures to the Minister. A valuable experience we had during this project has been summarized, and some problems have also been pointed out from a viewpoint of radiation safety management. (author)

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)

Decommissioning of IFEC

International Nuclear Information System (INIS)

Ceccotti, G.; Sberze, L.

1995-05-01

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

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)

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

Experience relevant to safety obtained from reactor decommissioning operations in the French Atomic Energy Commission

International Nuclear Information System (INIS)

Giraudel, B.; Langlois, G.

1979-01-01

From among the nuclear facilities constructed in France the authors cite eight large reactors, ranging from critical assemblies to power reactors, that have been finally shut-down since 1965. A brief account is given of the way in which the various operations were carried out after the final control rod drop, a distinction being drawn between the shut-down proper and the containment and dismantling work. A description is also given, from the technical and regulatory standpoint, of the final stage attained, and mention is made of French safety arrangements and of the part played by the safety services during decommissioning operations. Among the lessons derived from French experience, the authors mention the completion of operations without any serious safety problems, and with guarantees for the protection of personnel and the population as a whole, by conventional techniques; the advantage of planning decommissioning operations from the very beginning of construction of the facilities; and the importance of filing descriptive documents. In view of the experience gained, the French Atomic Energy Commission has devised internal procedures for facilitating the application of regulations governing the shut-down and decommissioning phases, which are aimed at preserving surveillance procedures similar to those in force during normal operation. (author)

Vandellos 1 decommissioning project. Safety before, during and after

International Nuclear Information System (INIS)

Rodriguez, A.

2002-01-01

The Nuclear Power Plant of Vandellos 1, a gas-graphite reactor (GCR), started operation in the 70's after 17 years running the decommissioning process began in 1998, and is expected to finish at the end of 2002 with the level 2 of decommissioning with a practically total scope reached, except the concrete reactor vessel and its internals that will remain for another 25 years in surveillance state (dormancy) until their total dismantling. During the last four years the activities related to decontamination and disassembly of the power plant system as well as the management of all this material have been carried out. One of the last phases of the project that will be performed this year, without doubt, one of the most representative of the operative difficulty of the task is the disassembly of some buildings which are more than 80 meters high and with some structures weighing more than 3.000 t, an operation, which is spectacular in terms of volume and mass involved. However one has to keep in mind that it has been preceded by the of clearance process of all these structures to be disassembled this summer. Hundred of thousands of radiological measures will confirm with guarantee that the destination of the dismantled materials is the correct one, assuring the protection of people and the environment. This is a process which has to integrate the principles of radiological safety and industrial safety. First, it has to be guaranteed that structures and components are below the values authorised by authorities for their free release, and, secondly, that the planned sequence of the process and manoeuvres in the disassembly of these colossal structures assures safety. (author)

ORNL decontamination and decommissioning program

International Nuclear Information System (INIS)

Bell, J.P.

1980-01-01

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

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).

Uranium hexafluoride production plant decommissioning

International Nuclear Information System (INIS)

Santos, Ivan

2008-01-01

The Institute of Energetic and Nuclear Research - IPEN is a research and development institution, located in a densely populated area, in the city of Sao Paulo. The nuclear fuel cycle was developed from the Yellow Cake to the enrichment and reconversion at IPEN. After this phase, all the technology was transferred to private enterprises and to the Brazilian Navy (CTM/SP). Some plants of the fuel cycle were at semi-industrial level, with a production over 20 kg/h. As a research institute, IPEN accomplished its function of the fuel cycle, developing and transferring technology. With the necessity of space for the implementation of new projects, the uranium hexafluoride (UF 6 ) production plant was chosen, since it had been idle for many years and presented potential leaking risks, which could cause environmental aggression and serious accidents. This plant decommission required accurate planning, as this work had not been carried out in Brazil before, for this type of facility, and there were major risks involving gaseous hydrogen fluoride aqueous solution of hydrofluoric acid (HF) both highly corrosive. Evaluations were performed and special equipment was developed, aiming to prevent leaking and avoid accidents. During the decommissioning work, the CNEN safety standards were obeyed for the whole operation. The environmental impact was calculated, showing to be not relevant.The radiation doses, after the work, were within the limits for the public and the area was released for new projects. (author)

Decommissioning and demolition of the Greifswald nuclear power station

International Nuclear Information System (INIS)

Sterner, H.; Leushacke, D.; Rittscher, D.

1995-01-01

The unexpected decision to decommission the plants in Greifswald makes the management and disposal of fuels and plant waste a major issue to be solved as a precondition for decommissioning and dismantling. The decisive point in waste management is the existence of an interim store or repository of sufficient capacity to accept both the nuclear fuel and the plant waste and the considerable volumes of radioactive residues arising in dismantling. Current major activities include planning for decommissioning and demolition, and drafting of the licensing documents; removal of the fuel elements from the reactor units; construction of the northern interim store for fuel elements and residues. (orig./HP)

The Role of Stakeholders in the Decommissioning of Salaspils Research Reactor

International Nuclear Information System (INIS)

Abramenkovs, A.

2009-01-01

The paper describes the role of different stakeholders in the decommissioning of the Salaspils Research Reactor. Decommissioning was a large challenge for the Latvia, since the country in this moment had no decommissioning experience and necessary technologies for the implementation of the defined goals by the Government. In this case for facilitation of the decommissioning of Salaspils Research Reactor (SRR), the significant role plays the local and international stakeholders. The paper deals with information on the basic stages of decommissioning of SRR and the role of the wide spectrum of stakeholders in preparation, upgrade and implementation of the decommissioning plan. The role of governmental institutions in the decommissioning of Salaspils research reactor is discussed. It was shown, that local municipalities are very important stakeholders, which significantly influence the decommissioning of SRR. The Salaspils municipalities positive impact on the decommissioning processes are discussed. Basic problems with the Baldone municipality in context of radioactive wastes management are indicated. The role of international stakeholders in decommissioning of Salaspils research reactor is discussed. It was shown, that the support from International Atomic Energy Agency significantly promotes the decommissioning of SRR. The main issues were expert support for solution of different technical problems in radioactive wastes management, area monitoring, and verification of decommissioning plans, training of staff and technical expertise during whole process of decommissioning. It was shown, that technical and economical support from DOE, USA provides the possibility to solve the fuel problem during decommissioning of SRR, as well as, to increase the physical safety of SRR and repository 'Radons'. It was shown, that a proper coordination of all activities and using the services from stakeholders can significantly reduce the total project expenses. The cooperation between

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)

Safety culture and organisational issues specific to the transitional phase from operation to decommissioning of the Ignalina Nuclear Power Plant

International Nuclear Information System (INIS)

Medeliene, D.

2005-01-01

The PHARE project Support to State Nuclear Power Safety Inspectorate for safety culture and organisational issues specific to the pre-shutdown phase of Ignalina Nuclear Power Plant was aimed at providing assistance to VATESI in their task to oversee that the Ignalina Nuclear Power Plant's management and staff are able to provide an acceptable level of reactor safety taking into account possible safety culture related problems that may occur due to the decision of an early closure of both units. Safety culture is used as a concept to characterise the attitudes, behaviour and perceptions of people that are important in ensuring the safety of nuclear power facility. Since the Chernobyl accident, the International Atomic Energy Agency (IAEA) has been active in creating guidance for ensuring that an adequate safety culture can be created and maintained. The transition from operation to decommissioning introduces uncertainty for both the organisation and individuals. This creates new challenges that need to be dealt with. Although safety culture and organisational issues have to be addressed during the entire life cycle of a nuclear power plant, owing to these special challenges, it should be especially highlighted during the transitional period from operation to decommissioning. Nuclear safety experts from Sweden, Finland, Italy, the UK and Germany, as well as Lithuanian specialists, participated in the project, and it proved to be a most effective way to share experience. The aim of this brochure is to provide information about: the importance of safety culture issues during the transitional phase from operation to decommissioning of Ignalina Nuclear Power Plant; the purpose, activities and results of this PHARE project; recommendations that are provided by western experts concerning the management of safety culture issues specific to the pre-decommissioning phase of Ignalina Nuclear Power Plant. (author)

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)

DASAO: software tool for the management of safeguards, waste and decommissioning

International Nuclear Information System (INIS)

Noynaert, Luc; Verwaest, Isi; Libon, Henri; Cuchet, Jean-Marie

2013-01-01

Decommissioning of nuclear facilities is a complex process involving operations such as detailed surveys, decontamination and dismantling of equipment's, demolition of buildings and management of resulting waste and nuclear materials if any. This process takes place in a well-developed legal framework and is controlled and followed-up by stakeholders like the Safety Authority, the Radwaste management Agency and the Safeguards Organism. In the framework of its nuclear waste and decommissioning program and more specifically the decommissioning of the BR3 reactor, SCK-CEN has developed different software tools to secure the waste and material traceability, to support the sound management of the decommissioning project and to facilitate the control and the follow-up by the stakeholders. In the case of Belgium, it concerns the Federal Agency for Nuclear Control, the National Agency for radioactive waste management and fissile material and EURATOM and IAEA. In 2005, Belgonucleaire decided to shutdown her Dessel MOX fuel fabrication plant and the production stopped in 2006. According to the final decommissioning plan ('PDF') approved by NIRAS, the decommissioning works should start in 2008 at the earliest. In 2006, the management of Belgonucleaire identified the need for an integrated database and decided to entrust SCK-CEN with its development, because SCK-CEN relies on previous experience in comparable applications namely already approved by authorities such as NIRAS, FANC and EURATOM. The main objectives of this integrated software tool are: - simplified and updated safeguards; - waste and material traceability; - computerized documentation; - support to project management; - periodic and final reporting to waste and safety authorities. The software called DASAO (Database for Safeguards, Waste and Decommissioning) was successfully commissioned in 2008 and extensively used from 2009 to the satisfaction of Belgonucleaire and the stakeholders. SCK-CEN is

Feedback from the decommissioning of two accelerators

International Nuclear Information System (INIS)

Aubert, M-C; Damoy, F.; Joly, J-M

2003-01-01

Saclay Linear Accelerator (ALS) and Saturne synchrotron, both well known as international research instruments, have definitively stopped operating in 1990 and 1997 respectively. The French Atomic Energy Commission (CEA) has decided proceeding with the appropriate actions in order to dismantle these two nuclear installations (NIs) known as INB 43 (ALS) and INB 48 (Saturne). The SDA (Accelerator Decommissioning Division) was created to be in charge of the dismantling procedure of the above NIs under the following conditions: - to maintain within the team a few employees from the previous exploitation of two NIs, in order not to loose the details and history of accelerator operation; - to import the necessary skills for a good management of dismantling operation such as waste management, ANDRA rules, project AMEC34omelt.com. Learn more about GeoMelt ats-gssr410nuclear safety, radiation protection, ALARA concepts, etc. Presently the dismantling operations are well under way at INB 43 and nearly finished at INB 48. The project organisation established by SDA has allowed meeting both the schedule and cost requirements of the decommissioning. At the beginning, major decommissioning safety characteristics of large research instruments will be presented and dismantling aspects in particular. Afterwards, the organization of both projects will be detailed, emphasizing their statutory aspects (e.g., safety documents, zoning, traceability, etc.) and technical difficulties. Waste characterisation as well as the choice of evacuation paths for each category of the waste will then be described in detail for both accelerators. A number of difficulties met during these procedures will be analysed and proposals will be made in order to improve the statutory framework in particular, both on technical and nuclear safety aspects. The application of the above experience to the dismantling of two fuel cycle installations, namely the research nuclear reactors, is presently under study

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

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.

International Atomic Energy Agency activities in decommissioning

International Nuclear Information System (INIS)

Reisenweaver, D W.; )

2005-01-01

Full text: The International Atomic Energy Agency (IAEA) has been addressing the safety and technical issues of decommissioning for over 20 years, but their focus has been primarily on planning. Up to know, the activities have been on an ad hoc basis and sometimes, important issues have been missed. A new Action Plan on the Decommissioning of Nuclear Facilities has recently been approved by the Agency's board of Governors which will focus the Agency's efforts and ensure that our Member States' concerns are addressed. The new initiatives associated with this Action Plan will help ensure that decommissioning activities in the future are performed in a safe and coherent manner. The International Atomic Energy Agency (IAEA) has been preparing safety and technical documents concerning decommissioning since the mid-1980's. There have been over 30 documents prepared that provide safety requirements, guidance and supporting technical information. Many of these documents are over 10 years old and need updating. The main focus in the past has been on planning for decommissioning. During the past five years, a set of Safety Standards have been prepared and issued to provide safety requirements and guidance to Member States. However, decommissioning was never a real priority with the Agency, but was something that had to be addressed. To illustrate this point, the first requirements documents on decommissioning were issued as part of a Safety Requirements [1] on pre-disposal management of radioactive waste. It was felt that decommissioning did not deserve its own document because it was just part of the normal waste management process. The focus was mostly on waste management. The Agency has assisted Member States with the planning process for decommissioning. Most of these activities have been focused on nuclear power plants and research reactors. Now, support for the decommissioning of other types of facilities is being requested. The Agency is currently providing technical

NPP Decommissioning: the concept; state of activities

International Nuclear Information System (INIS)

Nemytov, S.; Zimin, V.

2001-01-01

The main principles of NPP decommissioning concept in Russia are given. The conditions with fulfillment of works on NPP unit pre-decommissioning and decommissioning including: development of the normative documentation, creation of special fund for financing NPP decommissioning activities, deriving the Gosatomnadzor license for decommissioning of shut down NPP units, development of the equipment and technologies for waste and spent fuel management are presented. The decommissioning cost and labour intensity of one WWER-440 unit are shown. The practical works, executed on shut down units at Beloyarsk NPP (Unit1 and 2) and Novo Voronezh NPP (Unit 1 and 2) are outlined

Radioactive waste management and decommissioning at the NEA

International Nuclear Information System (INIS)

2010-11-01

The OECD Nuclear Energy Agency (NEA) seeks to assist its member countries in developing safe, sustainable and societally acceptable strategies for the management of all types of radioactive materials, with particular emphasis on the management of long-lived waste and spent fuel and on decommissioning of disused nuclear facilities. The programme of work in these areas is carried out for the most part by the Radioactive Waste Management Committee (RWMC) assisted by three working parties: - The Forum on Stakeholder Confidence (FSC). - The Integration Group for the Safety Case (IGSC). - The Working Party on Decommissioning and Dismantling (WPDD). Other NEA Committees also have interests in this field: the Committee on Radiation Protection and Public Health (CRPPH) and the Nuclear Development Committee (NDC). The OECD/NEA is at the forefront in addressing both the technical and societal requirements for durable and sustainable waste management and decommissioning solutions. Through the RWMC it provides a neutral forum where policy makers, regulators and implementing organisations can discuss issues of common interest and develop solutions that meet the diverse needs of its member countries

SE-VYZ - Decommissioning of Nuclear Installations, Radioactive Waste and Spent Fuel Management

International Nuclear Information System (INIS)

Anon

2004-01-01

In this presentations processes of radioactive waste treatment in the Bohunice Radioactive Waste Processing Center (SE-VYZ), Jaslovske Bohunice are presented. Decommissioning of the A-1 NPP is also presented. Disposal of conditioned radioactive waste in fibre concrete containers (FCC) are transported to Mochovce from Jaslovske Bohunice by the transport truck where are reposited in the National radioactive waste repository Mochovce. The Interim spent fuel storage facility (ISFSF) is included into this presentation

DETAILS OF OPERATIONS PERFORMED BY THE REMOTE CONTROL ROBOT (CONCEPT TO THE HORIZONTAL FUEL CHANNEL DURING DECOMMISSIONING PHASE OF NUCLEAR REACTOR CALANDRIA STRUCTURE. PART II: INSIDE OPERATIONS

Directory of Open Access Journals (Sweden)

Constantin POPESCU

2017-05-01

Full Text Available The authors contribution to this paper is to present a concept solution of a remote control robot (RCR used for decommissioning of the horizontal fuel channels pressure tube in the CANDU nuclear reactor. In this paper the authors highlight few details of geometry, operations, constraints by kinematics and dynamics of the robot movement inside of the reactor fuel channel. Inside operations performed has as the main steps of dismantling process the followings: unblock and extract the channel closure plug (from End Fitting - EF, unblock and extract the channel shield plug (from Lattice Tube - LT, cut the ends of the pressure tube, extract the pressure tube and cut it in small parts, sorting and storage extracted items in the safe robot container. All steps are performed in automatic mode. The remote control robot (RCR represents a safety system controlled by sensors and has the capability to analyze any error registered and decide next activities or abort the inside decommissioning procedure in case of any risk rise in order to ensure the environmental and workers protection.

JPDR decommissioning program

International Nuclear Information System (INIS)

Anon.

1983-01-01

As approved by the Japan Nuclear Safety Commission, the preparatory work for dismantling the Japan Power Demonstration Reactor of Japan Atomic Energy Research Institute has begun. As decided in the long term nuclear energy development and utilization program in June, 1982, by the Japan Atomic Energy Commission, the dismantling of the JPDR through its entire phase is the model case for the development of the dismantling technology and for the establishment of safety standard in the dismantling of shut-off nuclear power plants and their removal. The schedule of the JPDR dismantling is divided into two phases. In Phase 1, the development of dismantling techniques is made by the end of fiscal 1985, and in Phase 2, the full scale dismantling work is carried out by the end of fiscal 1989. The removal of the related facilities and the rearrangement of the evacuated land also are scheduled to be completed. During the first 10 days of April, 1983, the JPDR will be in the sealed up condition for the purpose of developing the dismantling techniques, and the nuclear fuel has been transferred to the spent fuel pool. The national policy on reactor decommissioning and the program for the technology development are reported. (Kako, I.)

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)

Fuel safety research 1999

Energy Technology Data Exchange (ETDEWEB)

Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2000-07-01

In April 1999, the Fuel Safety Research Laboratory was newly established as a result of reorganization of the Nuclear Safety Research Center, JAERI. The laboratory was organized by combining three laboratories, the Reactivity Accident Laboratory, the Fuel Reliability Laboratory, and a part of the Sever Accident Research Laboratory. Consequently, the Fuel Safety Research Laboratory is now in charge of all the fuel safety research in JAERI. Various types of experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of five research groups corresponding to each research fields. They are; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). This report summarizes the outline of research activities and major outcomes of the research executed in 1999 in the Fuel Safety Research Laboratory. (author)

Development of decommissioning system engineering technology

International Nuclear Information System (INIS)

Lee, K. W.; Kim, S. K.; Seo, B. K.

2012-02-01

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

Advanced fuels safety comparisons

International Nuclear Information System (INIS)

Grolmes, M.A.

1977-01-01

The safety considerations of advanced fuels are described relative to the present understanding of the safety of oxide fueled Liquid Metal Fast Breeder Reactors (LMFBR). Safety considerations important for the successful implementation of advanced fueled reactors must early on focus on the accident energetics issues of fuel coolant interactions and recriticality associated with core disruptive accidents. It is in these areas where the thermal physical property differences of the advanced fuel have the greatest significance

Experience Of Using Metal-and-Concrete Cask TUK-108/1 For Storage And Transportation Of Spent Nuclear Fuel Of Decommissioned NPS

Energy Technology Data Exchange (ETDEWEB)

Barnes, E.; Dyer, R. [Environmental Protection Agency, Ronald Reagan Bldg. 3rd Floor 1200 Pennsylvania Av., NW Washington, D.C. 20024 (United States); Snipes, R. [Oak Ridge National Laboratories, VA (United States); Dolbenkov, V.G.; Guskov, V.D.; Korotkov, G.V. [Joint Stock Company ' KBSM' , 64 Lesnoy Av., St.Petersburg 194100 (Russian Federation); Makarchuk, T.F. [Joint Stock Company ' Atomstroyexport' , Potapovskiy str. 5, bld. 4, Moscow, 101990 (Russian Federation); Zakharchev, A.A. [State Corporation ' Rosatom' , 24-26 Ordinka St., Moscow, 100000 (Russian Federation)

2009-06-15

In past 10 years in Russia an intensive development of a new technology of management of spent nuclear fuel (SNF) has taken place. This technology is based on the concept of using a shielded cask which provides safety of its content (SNF) and meeting all other safety requirements to storage and transportation of SNF. Radiation protection against emission and non-propagation of activity outside the cask is ensured by the physical barriers such as all-metal or composite body, face work, inner structures to accommodate spent fuel assemblies (SFA), lids with sealing systems. Residual heat buildup is off-taken to the environment by natural way: emission and convection of surrounding air. The necessity in development of the cask technology of SNF management was conditioned by the situation at hand with defueling of Russian decommissioned nuclear-powered submarines (NPS) as the existed transport infrastructure and enterprises involved in fuel processing could not meet the demand for transportation and processing of SNF neither from reactors of all dismantled NPS, nor from reactors of NPS waiting for decommissioning. The US and Norway actively participated in the trilateral joint project with the Russian Federation aimed at creation of a cask prototype for interim storage and transportation of SNF of dismantled NPS. The 1.1 Project is a part of the Arctic Military Environmental Cooperation (AMEC) Program. In December 2000 the project was successfully completed by issuance of the certificate-permit for design and transportation of NP Submarine SNF. It was a first certified dual-purpose TUK from the MMC family. In these years 106 TUK-108/1 casks have been manufactured and supplied to PO Mayak, JSC CS Zvezda, JSC CS Zvezdochka and FSUE DalRAO. The storage pads for interim storage of TUK-108/1 have been built and currently are in operation on sites of SNF unloading from submarine reactors and SNF cask-loading such as JSC CS Zvezda, JSC CS Zvezdochka and FSUE DalRAO. In

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

Cost Estimation for Research Reactor Decommissioning

International Nuclear Information System (INIS)

2013-01-01

One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world'. One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property.' The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia, and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. The purpose of this publication is to develop a costing methodology and a software tool in order to support cost estimation for research reactor decommissioning. The costing methodology is intended for the preliminary cost estimation stages for research reactor decommissioning with limited inventory data and other input data available. Existing experience in decommissioning costing is considered. As the basis for the cost calculation structure, the costing model uses the International Structure for Decommissioning Costing (ISDC) that is recommended by the IAEA, the Organisation for

Proceedings of the Topical Meeting on the safety of nuclear fuel cycle intermediate storage facilities

International Nuclear Information System (INIS)

1998-01-01

reprocessing plant (Thorp). Description, safety design criteria and cold commissioning of the storage facility for HLW and MLW in Belgium. Burn-up assessment of spent PWR fuel assemblies by analysis of the neutron emission; Comparison of measured and calculated data. Study on burnup credit evaluation method at JAERI towards securing criticality safety rationale for management of spent fuel. Handling and storage of decommissioning wastes at BNFL Sellafield - A criticality perspective. Uncertainties of radiation source terms for the shielding safety analysis of high burnup fuels

Chernobyl NPP decommissioning efforts - Past, Present and Future. Decommissioning Efforts on Chernobyl NPP site - Past, Present

International Nuclear Information System (INIS)

Kuchinskiy, V.

2017-01-01

Two unique large-scale projects are underway at the moment within the Chernobyl - Exclusion zone - Shelter object transformation into ecologically safe system and the decommissioning of 3 Chernobyl NPP Units. As a result of beyond design accident in 1986 the entire territory of the industrial site and facilities located on it was heavily contaminated. Priority measures were carried out at the damaged Unit under very difficult conditions to reduce the accident consequences and works to ensure nuclear and radiation safety are continuous, and the Unit four in 1986 was transformed into the Shelter object. Currently, works at the Shelter object are in progress. Under assistance of the International Community new protective construction was built above the existing Shelter object - New Safe Confinement, which will ensure the SO Safety for the long term - within up to 100 years. The second major project is the simultaneous decommissioning of Chernobyl NPP Units 1, 2 and 3. Currently existing Chernobyl NPP decommissioning Strategy has been continuously improved starting from the Concept of 1992. Over the years the following was analyzed and taken into account: the results of numerous research and development works, international experience in decommissioning, IAEA recommendations, comments and suggestions from the governmental and regulatory bodies in the fields of nuclear energy use and radioactive waste management. In 2008 the final decommissioning strategy option for Chernobyl NPP was approved, that was deferred gradual dismantling (SAFSTOR). In accordance with this strategy, decommissioning will be carried out in 3 stages (Final Shutdown and Preservation, Safe Enclosure, Dismantling). The SAFSTOR strategy stipulates: -) the preservation of the reactor, the primary circuit and the reactor compartment equipment; -) the dismantling of the equipment external in relation to the reactor; -) the safe enclosure (under the supervision); -) the gradual dismantling of the primary

Cleanup and decommissioning of a nuclear reactor after a severe accident

International Nuclear Information System (INIS)

1992-01-01

Although the development of commercial nuclear power plants has in general been associated with an excellent record of nuclear safety, the possibility of a severe accident resulting in major fuel and core damage cannot be excluded and such accidents have in fact already occurred. For over a decade, IAEA publications have provided technical guidance and recommendations for post-accident planning to be considered by appropriate authorities. Guidance and recommendations have recently been published on the management of damaged nuclear fuel, sealing of the reactor building and related safety and performance assessment aspects. The present technical report on the cleanup and decommissioning of reactors which have undergone a severe accident represents a further publication in the series. Refs, figs and tabs.

Generations of decay: the political geography of decommissioning

International Nuclear Information System (INIS)

Blowers, A.

1990-01-01

Energy is politics. We rarely find it where we need it, it imposes upon other areas when we move it, and the less control we have over its development and use, the more politically insecure we feel. Nuclear power appears to avoid the traditional politics of energy supply by geographically internalizing much of the fuel cycle. But the problem of waste disposal, including decommissioning, is a major source of political conflict and uncertainty affecting the whole future of the nuclear industry. One of the most politically motivated decisions of the decommissioning era will be in choosing whether the process will be immediate or deferred. Deferred decommissioning is the most likely strategy, and that geographical inertia is the likely outcome. Such inertia is a feature of industrial decline, with each industrial epoch leaving the detritus of past decisions for future generations to discover and deal with. The political basis of the nuclear fuel cycle is its links with considerations of wastes, hazards, longevity, and equity, all matters of public interest and concern. As part of the nuclear fuel cycle, decommissioning will include these considerations too, and it is for this reason that, wherever decommissioning takes place, political questions arise. (author)

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)

Towards a safety case for the use of laser cutting in nuclear decommissioning

International Nuclear Information System (INIS)

Hilton, P.A.

2014-01-01

Some of the requirements in nuclear decommissioning include size reduction of contaminated containers, pipework and other structures manufactured from stainless and other steels. Size reduction is generally performed using mechanical saws or shears, with drawbacks of quick wear, significant applied force, difficult remote operation and addition to contaminated waste mass. The use of lasers for cutting within the context of nuclear decommissioning has been recently demonstrated by TWI and others. In this paper, aspects of drawing together a safety case for using laser beams for cutting in a nuclear decommissioning cell are discussed, via analysis of relevant purpose designed experimental data. Data presented includes assessment of the use of different focal length lenses and the power densities anticipated at distances of up to 3 m from the focal point, as well as beam effects on material behind the cutting zone. An assessment of anticipated material damage from stray beams or unintended exposure to laser light of surrounding items is also presented. Finally materials for effective screening against stray beams during the cutting process have been tested for effectiveness. (authors)

Fuel safety research 2000

Energy Technology Data Exchange (ETDEWEB)

Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-03-01

In April 1999, the Fuel Safety Research Laboratory was newly established as a part of reorganization of the Nuclear Safety Research Center, JAERI. The new laboratory was organized by combining three pre-existing laboratories, Reactivity Accident Laboratory, Fuel Reliability Laboratory, and a part of Severe Accident Research Laboratory. The Fuel Safety Research Laboratory becomes to be in charge of all fuel safety research in JAERI. Various experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of following five research groups corresponding to each research fields; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). The research activities in year 2000 produced many important data and information. They are, for example, failure of high burnup BWR fuel rod under RIA conditions, data on the behavior of hydrided Zircaloy cladding under LOCA conditions and FP release data from VEGA experiments at very high temperature/pressure condition. This report summarizes the outline of research activities and major outcomes of the research executed in 2000 in the Fuel Safety Research Laboratory. (author)

Assessment methodology applicable to safe decommissioning of Romanian VVR-S research reactor

International Nuclear Information System (INIS)

Baniu, O.; Vladescu, G.; Vidican, D.; Penescu, M.

2002-01-01

The paper contains the results of research activity performed by CITON specialists regarding the assessment methodology intended to be applied to safe decommissioning of the research reactors, developed taking into account specific conditions of the Romanian VVR-S Research Reactor. The Romanian VVR-S Research Reactor is an old reactor (1957) and its Decommissioning Plan is under study. The main topics of paper are as follows: Safety approach of nuclear facilities decommissioning. Applicable safety principles; Main steps of the proposed assessment methodology; Generic content of Decommissioning Plan. Main decommissioning activities. Discussion about the proposed Decommissioning Plan for Romanian Research Reactor; Safety risks which may occur during decommissioning activities. Normal decommissioning operations. Fault conditions. Internal and external hazards; Typical development of a scenario. Features, Events and Processes List. Exposure pathways. Calculation methodology. (author)

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.

Strategy for decommissioning of the glove-boxes in the Belgonucleaire Dessel MOX fuel fabrication plant

International Nuclear Information System (INIS)

Vandergheynst, Alain; Cuchet, Jean-Marie

2007-01-01

Available in abstract form only. Full text of publication follows: BELGONUCLEAIRE has been operating the Dessel plant from the mid-80's at industrial scale. In this period, over 35 metric tons of plutonium (HM) was processed into almost 100 reloads of MOX fuel for commercial West-European Light Water Reactors. In late 2005, the decision was made to stop the production because of the shortage of MOX fuel market remaining accessible to BELGONUCLEAIRE after the successive capacity increases of the MELOX plant (France) and the commissioning of the SMP plant (UK). As a significant part of the decommissioning project of this Dessel plant, about 170 medium-sized glove-boxes are planned for dismantling. In this paper, after having reviewed the different specifications of ±-contaminated waste in Belgium, the authors introduce the different options considered for cleaning, size reduction and packaging of the glove-boxes, and the main decision criteria (process, α-containment, mechanization and radiation protection, safety aspects, generation of secondary waste, etc) are analyzed. The selected strategy consists in using cold cutting techniques and manual operation in shielded disposable glove-tents, and packaging α-waste in 200-liter drums for off-site conditioning and intermediate disposal. (authors)

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.

Management of the decommissioning of the Thetis reactor

Energy Technology Data Exchange (ETDEWEB)

Ooms, Luc; Maris, Patrick; Noynaert, Luc [SCK-CEN, Mol (Belgium)

2013-07-01

The Thetis research reactor on the site of the Nuclear Sciences Institute of the Ghent University has been in operation from 1967 until December 2003. This light-water moderated graphite-reflected low-enriched uranium pool-type reactor has been used for various purposes e.g. the production of radioisotopes and activation analyses. During the first years its core power was 15 kW. In the early '70, a core enlargement allowed for operation at typically 150 kW, while the maximum was allowed to be 250 kW In September 2007, Ghent University entrusted to SCK-CEN the management of the back-end of the spent fuel and the decommissioning of the reactor. In 2010, the spent fuel was removed from the reactor and transported to Belgoprocess for cementation in 400 l drums and interim storage awaiting final disposal. This activity allows tackling the decommissioning of the reactor. The objective is to complete its decommissioning by the end of 2014. In the framework of the decommissioning of the Thetis reactor, SCK-CEN set-up the final decommissioning plan and the decommissioning licensing file. These documents include among others a radiological inventory of the reactor. The graphite moderator blocks, the control and the safety pates, the liner of the pool were modeled to assess the activation products (isotopic vector and intensity). At the end of the unloading of the reactor in 2010 a brief mapping of the equipment's and internals of the reactor pool was performed. In 2012, we realized a more detailed mapping. These results confirmed those performed earlier and allowed to confirm the assumptions made in the final decommissioning plan. We set-up the terms of reference for the first decommissioning phase of the reactor namely the dismantling of the reactor i.e. reactor pool, circuits and rabbit system, equipment's and ventilation ducts. The removal of asbestos is also included into this phase. We conducted the selection process and the awarding of this

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

Sizewell B nuclear power station: the basis for the decision by the Health and Safety Executive to grant consent to load fuel into the reactor

International Nuclear Information System (INIS)

1994-01-01

The licensing and consent process and the basis for granting a consent for Nuclear Electric to load fuel into the Sizewell B reactor in the United Kingdom are explained. Consent was granted by the UK Nuclear Installations Inspectorate on behalf of the Health and Safety Executive on satisfactory completion of construction and those commissioning stages needed to proceed safely, and the production of a satisfactory safety case. A summary of the assessment of the safety case is appended. It covers the reactor core, coolant system structural integrity, engineered safety features, main and essential electrical system, control and instrumentation, radioactive waste management, radiological protection, fuel storage and handling, civil works and structures, fault analysis, human factors, hazard analysis, quality assurance, and decommissioning. (UK)

Project No. 8 - Final decommissioning plan

International Nuclear Information System (INIS)

2000-01-01

Ignalina NPP should prepare the final Ignalina NPP unit 1 decommissioning plan by march 31, 2002. This plan should include the following : description of Ignalina NPP and the Ignalina NPP boundary that could be influenced by decommissioning process; decommissioning strategy selected and a logical substantiation for this selection; description of the decommissioning actions suggested and a time schedule for the actions to be performed; conceptual safety and environmental impact assessment covering ionizing radiation and other man and environment impact; description of the environmental monitoring program proposed during decommissioning process; description of the waste management proposed; assessment of decommissioning expenses including waste management, accumulated funds and other sources. Estimated project cost - 0.75 M EURO

Fuel safety research 2001

Energy Technology Data Exchange (ETDEWEB)

Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2002-11-01

The Fuel Safety Research Laboratory is in charge of research activity which covers almost research items related to fuel safety of water reactor in JAERI. Various types of experimental and analytical researches are being conducted by using some unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and the Reactor Fuel Examination Facility (RFEF) of JAERI. The research to confirm the safety of high burn-up fuel and MOX fuel under accident conditions is the most important item among them. The laboratory consists of following five research groups corresponding to each research fields; Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). Research group of fuel behavior analysis (FEMAXI group). Research group of radionuclides release and transport behavior from irradiated fuel under severe accident conditions (VEGA group). The research conducted in the year 2001 produced many important data and information. They are, for example, the fuel behavior data under BWR power oscillation conditions in the NSRR, the data on failure-bearing capability of hydrided cladding under LOCA conditions and the FP release data at very high temperature in steam which simulate the reactor core condition during severe accidents. This report summarizes the outline of research activities and major outcomes of the research executed in 2001 in the Fuel Safety Research Laboratory. (author)

Trends in fuel reprocessing safety research

International Nuclear Information System (INIS)

Tsujino, Takeshi

1981-01-01

With the operation of a fuel reprocessing plant in the Power Reactor and Nuclear Fuel Development Corporation (PNC) and the plan for a second fuel reprocessing plant, the research on fuel reprocessing safety, along with the reprocessing technology itself, has become increasingly important. As compared with the case of LWR power plants, the safety research in this field still lags behind. In the safety of fuel reprocessing, there are the aspects of keeping radiation exposure as low as possible in both personnel and local people, the high reliability of the plant operation and the securing of public safety in accidents. Safety research is then required to establish the safety standards and to raise the rate of plant operation associated with safety. The following matters are described: basic ideas for the safety design, safety features in fuel reprocessing, safety guideline and standards, and safety research for fuel reprocessing. (J.P.N.)

Nuclear power plant decommissioning. The nature of problems

Energy Technology Data Exchange (ETDEWEB)

Yunus, Yaziz

1986-04-01

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.

Answers to questions on National Report of the Slovak Republic. Compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. October 2003

International Nuclear Information System (INIS)

2003-10-01

Slovakia is pleased to present to the State Parties of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management the Answers to questions received on the National Report of the Slovak Republic compiled according to the terms of the Joint Convention (April 2003). Slovakia is ready to provide additional explanations to these Answers during the 1 st Review Meeting. In the Annexes the 254/1994 Coll. LL. Act of the National Council of the Slovak Republic of 25 August 1994 on State Fund of Decommissioning of Nuclear Installations and Handling of Spent Nuclear Fuels and Nuclear Wastes is included

Technology, safety, and costs of decommissioning a reference pressurized water reactor power station

International Nuclear Information System (INIS)

Smith, R.I.; Konzek, G.J.; Kennedy, W.E. Jr.

1978-05-01

Safety and cost information was developed for the conceptual decommissioning of a large [1175 MW(e)] pressurized water reactor (PWR) power station. Two approaches to decommissioning, Immediate Dismantlement and Safe Storage with Deferred Dismantlement, were studied to obtain comparisons between costs, occupational radiation doses, potential radiation dose to the public, and other safety impacts. Immediate Dismantlement was estimated to require about six years to complete, including two years of planning and preparation prior to final reactor shutdown, at a cost of $42 million, and accumulated occupational radiation dose, excluding transport operations, of about 1200 man-rem. Preparations for Safe Storage were estimated to require about three years to complete, including 1 1 / 2 years for planning and preparation prior to final reactor shutdown, at a cost of $13 million and an accumulated occupational radiation dose of about 420 man-rem. The cost of continuing care during the Safe Storage period was estimated to be about $80 thousand annually. Accumulated occupational radiation dose during the Safe Storage period was estimated to range from about 10 man-rem for the first 10 years to about 14 man-rem after 30 years or more. The cost of decommissioning by Safe Storage with Deferred Dismantlement was estimated to be slightly higher than Immediate Dismantlement. Cost reductions resulting from reduced volumes of radioactive material for disposal, due to the decay of the radioactive containments during the deferment period, are offset by the accumulated costs of surveillance and maintenance during the Safe Storage period

Safety of fuel cycle facilities. Topical issues paper no. 3

International Nuclear Information System (INIS)

Ranguelova, V.; Niehaus, F.; Delattre, D.

2001-01-01

that the relative hazards vary from facility to facility depending upon the processes employed. However, all installations should be designed and operated so as to keep all sources of radiation exposure under strict technical and administrative control. The design management should ensure that the structures, systems and components important to safety have the appropriate characteristics, specifications and material composition to perform the required safety functions. Emphasis should be placed on the use of proven engineered safety features in the implementation of the defence in depth concept in the facility design and operation. The development of nuclear safety standards is one of the tasks given by the Statute of the IAEA. Over a number of years, the IAEA has developed a comprehensive set of publications which address, in a structured manner, the safety of nuclear installations. The Safety Fundamentals publication entitled 'The Safety of Nuclear Installations' presents an international consensus on the basic concepts underlying the principles for the regulation, design and operation of nuclear installations, including fuel cycle facilities. Detailed requirements and guides for activities relating to siting, design, construction, operation, decommissioning and regulation of nuclear installations are addressed by lower hierarchy safety standards, which cover nuclear power plants (NPPs) and research reactors. Although some of the IAEA NPP standards can be adapted and applied to fuel cycle facilities and some standards on criticality safety are published by the International Organization for Standardization (ISO), in general there is a lack of international safety standards to cover the safety of such facilities. With a view to establishing a plan for the development of safety standards for fuel cycle facilities, the IAEA began to compile information on the status of national regulations and safety issues concerning such facilities. It also held a Technical Committee

Nuclear power performance and safety. V.5. Nuclear fuel cycle

International Nuclear Information System (INIS)

1988-01-01

The International Conference on Nuclear Power Performance and Safety, organized by the International Atomic Energy Agency, was held at the Austria Centre Vienna (ACV) in Vienna, Austria, from 28 September to 2 October 1987. The objective of the Conference was to promote an exchange of worldwide information on the current trends in the performance and safety of nuclear power and its fuel cycle, and to take a forward look at the expectations and objectives for the 1990s. Policy decisions for waste management have already been taken in many countries and the 1990s should be a period of demonstration and implementation of these policies. As ilustrated by data presented from a number of countries, many years of experience in radioactive waste management have been achieved and the technology exists to implement the national plans and policies that have been developed. The establishment of criteria, the development of safety performance methodology and site investigation work are key activities essential to the successful selection, characterization and construction of geological repositories for the final disposal of radioactive waste. Considerable work has been done in these areas over the last ten years and will continue into the 1990s. However, countries that are considering geological disposal for high level waste now recognize the need for relating the technical aspects to public understanding and acceptance of the concept and decision making activities. The real challenge for the 1990s in waste disposal will be successfully to integrate technological activities within a process which responds to institutional and public concern. Volume 5 of the Proceedings comprehends the contributions on waste management in the 1990s. Decontamination and decommissioning, waste management, treatment and disposal, nuclear fuel cycle - present and future. Enrichment services and advanced reactor fuels, improvements in reactor fuel utilization and performance, spent fuel management

The new revision of NPP Krsko decommissioning, radioactive waste and spent fuel management program: analyses and results

International Nuclear Information System (INIS)

Zeleznik, Nadja; Kralj, Metka; Lokner, Vladimir; Levanat, Ivica; Rapic, Andrea; Mele, Irena

2010-01-01

The preparation of the new revision of the Decommissioning and Spent Fuel (SF) and Low and Intermediate level Waste (LILW) Disposal Program for the NPP Krsko (Program) started in September 2008 after the acceptance of the Term of Reference for the work by Intergovernmental Committee responsible for implementation of the Agreement between the governments of Slovenia and Croatia on the status and other legal issues related to investment, exploitation, and decommissioning of the Nuclear power plant Krsko. The responsible organizations, APO and ARAO together with NEK prepared all new technical and financial data and relevant inputs for the new revision in which several scenarios based on the accepted boundary conditions were investigated. The strategy of immediate dismantling was analyzed for planned and extended NPP life time together with linked radioactive waste and spent fuel management to calculate yearly annuity to be paid by the owners into the decommissioning funds in Slovenia and Croatia. The new Program incorporated among others new data on the LILW repository including the costs for siting, construction and operation of silos at the location Vrbina in Krsko municipality, the site specific Preliminary Decommissioning Plan for NPP Krsko which included besides dismantling and decontamination approaches also site specific activated and contaminated radioactive waste, and results from the referenced scenario for spent fuel disposal but at very early stage. Important inputs for calculations presented also new amounts of compensations to the local communities for different nuclear facilities which were taken from the supplemented Slovenian regulation and updated fiscal parameters (inflation, interest, discount factors) used in the financial model based on the current development in economical environment. From the obtained data the nominal and discounted costs for the whole nuclear program related to NPP Krsko which is jointly owned by Slovenia and Croatia have

Technology, safety and costs of decommissioning a reference boiling water reactor power station: Comparison of two decommissioning cost estimates developed for the same commercial nuclear reactor power station

International Nuclear Information System (INIS)

Konzek, G.J.; Smith, R.I.

1990-12-01

This study presents the results of a comparison of a previous decommissioning cost study by Pacific Northwest Laboratory (PNL) and a recent decommissioning cost study of TLG Engineering, Inc., for the same commercial nuclear power reactor station. The purpose of this comparative analysis on the same plant is to determine the reasons why subsequent estimates for similar plants by others were significantly higher in cost and external occupational radiation exposure (ORE) than the PNL study. The primary purpose of the original study by PNL (NUREG/CR-0672) was to provide information on the available technology, the safety considerations, and the probable costs and ORE for the decommissioning of a large boiling water reactor (BWR) power station at the end of its operating life. This information was intended for use as background data and bases in the modification of existing regulations and in the development of new regulations pertaining to decommissioning activities. It was also intended for use by utilities in planning for the decommissioning of their nuclear power stations. The TLG study, initiated in 1987 and completed in 1989, was for the same plant, Washington Public Supply System's Unit 2 (WNP-2), that PNL used as its reference plant in its 1980 decommissioning study. Areas of agreement and disagreement are identified, and reasons for the areas of disagreement are discussed. 31 refs., 3 figs., 22 tabs

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

Challenges of Ignalina NPP Decommissioning - View of Lithuanian Operator

International Nuclear Information System (INIS)

Aksionov, P.

2017-01-01

The state enterprise Ignalina Nuclear Power Plant (INPP) operates 2 similar design units of RBMK-1500 water-cooled graphite-moderated channel-type power reactors (1500 MW electrical power). INPP is carrying out the decommissioning project of the 2 reactors which includes: -) the retrieval of the spent nuclear fuel from the power units and its transportation into the Interim Spent Fuel Storage Facility; -) equipment and building decontamination and dismantling; -) radioactive waste treatment and storage; and -) the operation of key systems to ensure nuclear, radiation and fire protection. Ignalina NPP decommissioning project is planned to be completed by 2038. The presentation will be focused on the ongoing decommissioning activities at Ignalina NPP. The overview of main aspects and challenges of INPP decommissioning will be provided

Guideline to Estimate Decommissioning Costs

Energy Technology Data Exchange (ETDEWEB)

Yun, Taesik; Kim, Younggook; Oh, Jaeyoung [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

The primary objective of this work is to provide guidelines to estimate the decommissioning cost as well as the stakeholders with plausible information to understand the decommissioning activities in a reasonable manner, which eventually contribute to acquiring the public acceptance for the nuclear power industry. Although several cases of the decommissioning cost estimate have been made for a few commercial nuclear power plants, the different technical, site-specific and economic assumptions used make it difficult to interpret those cost estimates and compare them with that of a relevant plant. Trustworthy cost estimates are crucial to plan a safe and economic decommissioning project. The typical approach is to break down the decommissioning project into a series of discrete and measurable work activities. Although plant specific differences derived from the economic and technical assumptions make a licensee difficult to estimate reliable decommissioning costs, estimating decommissioning costs is the most crucial processes since it encompasses all the spectrum of activities from the planning to the final evaluation on whether a decommissioning project has successfully been preceded from the perspective of safety and economic points. Hence, it is clear that tenacious efforts should be needed to successfully perform the decommissioning project.

Decommissioning experience in the U.K

International Nuclear Information System (INIS)

Johnson, A.

1992-01-01

The decommissioning of nuclear power plants and fuel cycle centers in the United Kingdom has become an emotive subject and has, along with waste management, been blamed for the apparent demise of the nuclear power industry. During the early eighties, in the United Kingdom, it was becoming obvious that some of the older defence facilities could not be left in their existing condition for much longer. A program was drawn up and discussions held with the responsible authorities. At about the same time, consideration was also being given to the dismantling of the nuclear facilities that were or had been used as part of the programme of nuclear fuel cycle services to the civil nuclear programme in United Kingdom. As a consequence of these activities, a comprehensive decommissioning policy and programme for the defence related and fuel cycle centers had been drawn up. In addition to this, the Atomic Energy Authority began planning a decommissioning programme on the Windscale Advanced Gas Cooled Reactor after its shut down in 1981. 4 refs

New iteration of decommissioning program for NPP Krsko

International Nuclear Information System (INIS)

Lokner, V.; Levanat, I.; Rapic, A.; Zeleznik, N.; Mele, I.; Jenko, T.

2004-01-01

As required by the paragraph 10 of the Agreement between the governments of Slovenia and Croatia on status and other legal issues related to investment, exploitation, and decommissioning of Nuclear power plant Krsko, Decommissioning program for Krsko NPP including LILW and spent fuel management was drafted. The Intergovernmental body required that the Program should be extensive revision of existing program as one of several iterations to be prepared before the final version. The purpose of the Program is to estimate the expenses of the future decommissioning, radioactive waste and spent fuel management for Krsko NPP. Costing estimation would be the basis for establishment of a special fund in Croatia and for adjustment of the annual rates for the existing decommissioning fund in Slovenia. The Program development was entrusted to specialized organizations both in Croatia and Slovenia, which formed the Project team as the operative body. Consulting firms from Croatia and Slovenia were involved as well as experts from the International Atomic Energy Agency (through short visits to Zagreb and Ljubljana) for specialized fields (e.g. economic aspects of decommissioning, pre-feasibility study for spent fuel repository in crystalline rock, etc.). The analysis was performed in several steps. The first step was to develop rational and feasible integral scenarios (strategies) of decommissioning and LILW and spent fuel management on the basis of detailed technical analysis and within defined boundary conditions. Based on technological data, every scenario was attributed with time distribution of expenses for all main activities. In the second step, financial analysis of the scenarios was undertaken aiming at estimation of total discounted expense and the related annuity (19 installments to the single fund, empty in 2003) for each of the scenarios. The third step involves additional analysis of the chosen scenarios aiming at their (technical or financial) improvements even at

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

Nuclear Safety. Technical progress journal, April--June 1996: Volume 37, No. 2

Energy Technology Data Exchange (ETDEWEB)

Muhlheim, M D [ed.

1996-01-01

This journal covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities.

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

International Nuclear Information System (INIS)

Lessard, Leo; Kay, Jim; Lefrancois, Donald; Furr, Richard; Lucas, Matthieu; Schauer, Konrad

2016-01-01

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

Brief Assessment of Krsko NPP Decommissioning Costs

International Nuclear Information System (INIS)

Skanata, D.; Medakovic, S.; Debrecin, N.

2000-01-01

The first part of the paper gives a brief description of decommissioning scenarios and models of financing the decommissioning of NPPs. The second part contains a review of decommissioning costs for certain PWR plants with a brief description of methods used for that purpose. The third part of the paper the authors dedicated to the assessment of decommissioning costs for Krsko NPP. It does not deal with ownership relations and obligations ensuing from them. It starts from the simple point that decommissioning is an structure of the decommissioning fund is composed of three basic cost items of which the first refers to radioactive waste management, the second to storage and disposal of the spent nuclear fuel and the third to decommissioning itself. The assessment belongs to the category of preliminary activities and as such has a limited scope and meaning. Nevertheless, the authors believe that it offers a useful insight into the basic costs that will burden the decommissioning fund of Krsko NPP. (author)

Fort St. Vrain defueling ampersand decommissioning considerations

International Nuclear Information System (INIS)

Warembourg, D.

1994-01-01

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

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)

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.

Sipping fuel and saving lives: increasing fuel economy withoutsacrificing safety

Energy Technology Data Exchange (ETDEWEB)

Gordon, Deborah; Greene, David L.; Ross, Marc H.; Wenzel, Tom P.

2007-06-11

The public, automakers, and policymakers have long worried about trade-offs between increased fuel economy in motor vehicles and reduced safety. The conclusion of a broad group of experts on safety and fuel economy in the auto sector is that no trade-off is required. There are a wide variety of technologies and approaches available to advance vehicle fuel economy that have no effect on vehicle safety. Conversely, there are many technologies and approaches available to advance vehicle safety that are not detrimental to vehicle fuel economy. Congress is considering new policies to increase the fuel economy of new automobiles in order to reduce oil dependence and reduce greenhouse gas emissions. The findings reported here offer reassurance on an important dimension of that work: It is possible to significantly increase the fuel economy of motor vehicles without compromising their safety. Automobiles on the road today demonstrate that higher fuel economy and greater safety can co-exist. Some of the safest vehicles have higher fuel economy, while some of the least safe vehicles driven today--heavy, large trucks and SUVs--have the lowest fuel economy. At an October 3, 2006 workshop, leading researchers from national laboratories, academia, auto manufacturers, insurance research industry, consumer and environmental groups, material supply industries, and the federal government agreed that vehicles could be designed to simultaneously improve safety and fuel economy. The real question is not whether we can realize this goal, but the best path to get there. The experts' studies reveal important new conclusions about fuel economy and safety, including: (1) Vehicle fuel economy can be increased without affecting safety, and vice versa; (2) Reducing the weight and height of the heaviest SUVs and pickup trucks will simultaneously increase both their fuel economy and overall safety; and (3) Advanced materials can decouple size from mass, creating important new possibilities

The curious accountancy of decommissioning

International Nuclear Information System (INIS)

Anon.

1990-01-01

Financial provision for the decommissioning and waste management of the United Kingdom Magnox and AGR reactor is discussed. In the last set of accounts prior to privatisation a decommissioning provision of Pound 8.34 bn was indicated whereas previous figures had only shown Pound 2.88. It is suggested that the increase was only achieved on paper, without real financial provision. Estimates of decommissioning costs for the Magnox stations have increased greatly. Cost estimates for AGR decommissioning have still to be released but it is expected that the post-privatisation owners of the nuclear power industry, Nuclear Electric, will have to find Pound 6-7 bn to dismantle its own reactors. Much of this it hopes to put off for over 100 years. The South of Scotland Electicity Board has made much more realistic provision for its own Magnox and two AGR stations. Reprocessing costs for AGR reactor fuel is uncertain and high reprocessing and decommissioning costs will mean increases in the price of nuclear electricity. (UK)

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

A Decommissioning Information Management System

Energy Technology Data Exchange (ETDEWEB)

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

2007-07-01

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

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

Financial aspects of decommissioning

International Nuclear Information System (INIS)

Chirica, T.; Havris, A.

2003-01-01

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

Alternate form and placement of short lived reactor waste and associated fuel hardware for decommissioning of EBR-II

Energy Technology Data Exchange (ETDEWEB)

Planchon, H.P.; Singleterry, R.C. Jr.

1995-12-01

Upon the termination of EBR-II operation in 1994, the mission has progressed to decommissioning and waste cleanup of the facility. The simplest method to achieve this goal is to bury the raw fuel and activated steel in an approved burial ground or deep geologic repository. While this might be simple, it could be very expensive, consume much needed burial space for other materials, and leave large amounts of fissile easily available to future generations. Also, as with any operation, an associated risk to personnel and the public from the buried waste exists. To try and reduce these costs and risks, alternatives to burial are sought. One alternative explored here for EBR-II is to condition the fuel and store the fission products and steel either permanently or temporarily in the sealed primary boundary of the decommissioned reactor. The first problem is to identify which subassemblies are going to be conditioned and their current composition and decay time. The next problem is to identify the conditioning process and determine the composition and form of the waste streams. The volume, mass, heat, and curie load of the waste streams needs to be determined so a waste-assembly can be designed. The reactor vessel and internals need to be analyzed to determine if they can handle these loads. If permanent storage is the goal, then mechanisms for placing the waste-assembly in the reactor vessel and sealing the vessel are needed. If temporary storage is the goal, then mechanisms for waste-assembly placement and retrieval are needed. This paper answers the technical questions of volume, mass, heat, and curie loads while just addressing the other questions found in a safety analysis. The final conclusion will compare estimated risks from the burial option and this option.

Nuclear Safety. Technical progress journal, January--March 1994: Volume 35, No. 1

Energy Technology Data Exchange (ETDEWEB)

Silver, E G [ed.

1994-01-01

This is a journal that covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities.

Safety Analysis of Spent Nuclear Fuel and Radwaste Facilities

International Nuclear Information System (INIS)

Poskas, P.; Ragaisis, V.

2001-01-01

The overview of the activities in the Laboratory of Heat Transfer in Nuclear Reactors related with the assessment of thermal, neutronic and radiation characteristics in spent nuclear fuel and radwaste facilities are performed. Activities related with decommissioning of Ignalina NPP are also reviewed. (author)

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.)

Nuclear safety. Technical progress journal, January--March 1996: Volume 37, No. 1

Energy Technology Data Exchange (ETDEWEB)

Muhlheim, M D [ed.

1996-01-01

Nuclear Safety is a journal that covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but is also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. Individual articles are indexed separately for the data base.

Shippingport station decommissioning project technology transfer program

International Nuclear Information System (INIS)

McKernan, M.L.

1988-01-01

US Department of Energy (DOE) Shippingport Station Decommissioning Project (SSDP) decommissioned, decontaminated, and dismantled the world's first, nuclear fueled, commercial size, electric power plant. SSDP programmatic goal direction for technology transfer is documentation of project management and operations experience. Objective is to provide future nuclear facility decommissioning projects with pertinent SSDP performance data for project assessment, planning, and operational implementation. This paper presents a working definition for technology transfer. Direction is provided for access and availability for SSDP technology acquisition

International regulatory issues and approaches in the transition phase from operation to decommissioning

International Nuclear Information System (INIS)

Pyy, P.; Hrehor, M.; ); Murley, T.; Ranieri, R.; Laaksonen, J.

2005-01-01

Full text: The paper summarizes the work performed by an international group of senior nuclear safety regulators which was convened by the Committee on Nuclear Regulatory Activities (CNRA) of the OECD/Nuclear Energy Agency. The fundamental objective of this work was to identify the safety, environmental, organizational, human factors and public policy issues arising from decommissioning that will produce new challenges for the regulator. The study begins by recognizing that decommissioning is not simply an extension of operation and thus it is important for both the management of the facility and the regulator to understand the fundamental nature of the change taking place. Major regulatory policy issues discussed during this study include assurance of adequate funds, waste storage and disposal sites, material release criteria and site release criteria. Some of the important regulatory challenges relate to organizational and human factors, to safety and security requirements and to waste disposal and license termination. The importance of regular communication with both the corporate and site management and with public is recognized in the study as one of the key factors. When a nuclear facility ceases operation and enters into the decommissioning phase, both the operator and the regulator face a new set of challenges very different from those of an operating facility. The operator should have in place a strategic plan for decommissioning, prepared well in advance and reviewed by the regulatory body, to guide the facility managers and personnel through the changed circumstances. An essential part of the strategic plan should be the operator's plan for securing adequate funds to complete the decommissioning activities. In fact, the regulator should ensure that the operator sets aside funds, perhaps in a trust fund, while the facility is still operating and generating revenues. Both the operator and the regulator should expect a heightened public interest and concern

Lessons learned from the decommissioning process affected by an accident during operation. The case of A1 NPP in Slovakia

International Nuclear Information System (INIS)

Daniska, Vladimir; Timulak, Jan; Pekar, Anton; Niznansky, Vojtech; Konecny, Ladislav

2007-01-01

Decommissioning of NPP's with standard shutdown is currently well known process. The A1 NPP in Slovakia was shutdown in 1977 after the accident in the core which caused the damage of the fuel and contamination of systems. Long period from 1977 to 2008 was needed to manage issues resulting from affecting the systems and structures of A1 NPP and the environment by the accident. Management of the damaged spent fuel, decontamination of the primary circuit and other processes generated large amounts of alpha bearing waste, mostly liquid, having sludge phases with specific physical-chemical and radiological properties. Up to 1994, the approach for eliminating the consequences of the accident was based on safety priorities. The systematic approach, which includes also the rehabilitation of the affected environment, was implemented in the period 1994-2008. The process includes also establishing of the decommissioning infrastructure, legislative and funding system with the aim to implement the standard decommissioning procedures after 2008. However, the specific aspects, especially the level and radio-nuclide composition of contamination of systems and structures will remain. For final decommissioning 2008-2033, the approach was selected which foresees four licensed phases. This approach enables proper planning and performing of individual decommissioning phases. (authors)

Decommissioning: Strategies and programmes at the International Atomic Energy Agency (IAEA)

International Nuclear Information System (INIS)

Laraia, M.

2003-01-01

The International Atomic Energy Agency (IAEA) has included decommissioning in its regular programmes since 1985. Until a few years ago, attention was focused on the decommissioning of nuclear power plants, and to a lesser extent, research reactors. Some countries, however, are now devoting greater attention to the decommissioning of non-reactor facilities, with implementation of these programmes being seen as a high priority. This demanded equal attention in IAEA's programmes. In recent years, the IAEA has expanded its programmes to include guidance on decommissioning of small medical, industrial and research facilities which are prevailing in most of its over 130 Member States. By 2010-2020, a significant number of nuclear power plants, research reactors, fuel cycle and non-reactor facilities will have exceeded their normal design lifetimes. Many of these facilities are already shutdown and are awaiting decommissioning. In 1996, the IAEA organized the decommissioning programme along two directions. A first direction focuses on the safety of management of radioactive waste including decommissioning. A second direction focuses on the technology and strategies to support waste management and decommissioning activities. This split of activities was instituted in order to keep the regulatory aspects separated from the strategic and technology-related activities. The focus of this paper will be on current and foreseen activities related to strategies and technologies of decommissioning, but other activities will be touched upon as well. All technical divisions of the IAEA provide technical support for Technical Co-operation (TC) projects with developing countries. TC projects in the field of decommissioning are given separate coverage in this paper. The IAEA documents on decommissioning strategies and technologies are presented in Section 2. Technical Co-operation Programme concerning Decommissioning is discussed focusing the objectives, the specific projects and the

Design, construction and commissioning of an interim spent fuel store for the decommissioning of Ignalina NPP, Lithuania

International Nuclear Information System (INIS)

Rainer Goehring; Martin Beverungen; Phil Smith

2006-01-01

The contract for the design, construction and commissioning (turn-key) of an interim spent fuel store facility (ISFSF) has been awarded to a Consortium of GNS Gesellschaft fuer Nuklear Service and RWE NUKEM GmbH under the lead of RWE NUKEM. The contract was signed on the 12.01.2005. The Interim Spent Fuel Storage Facility (ISFSF) is financed by the Ignalina Decommissioning Support Fund which is managed by EBRD. All spent fuel assemblies, currently stored in the spent fuel pits at the reactors plus future arising (about 18000 in total) will be loaded in the CONSTOR R RBMK1500/M2 containers, which are stored in the new facility. The initial contract has been awarded for 3500 spent fuel assemblies. (authors)

The study of the installation of spent fuel interim storage facility from safety aspect point of view

International Nuclear Information System (INIS)

Djunaidi, Prayogo S.

1999-01-01

The installation of the ISFSF of the RSG-GAS has been come a cureneed, since the RSG-GAS has been operating for more than 10 years. The spent fuel stored in the reactor storage pool in creasing from time to time and therefore a long time storage is needed until the decommissioning of the reactor. The safety aspect related to the installation of the ISFSF has been studied, but the most important aspect are prevention of criticality of the spen fuel in the storage. The radiation dose must be less than that has been recommended by ICRP and the release of the radioactive material must be avoided . In this paper one of the safety aspects i.e. the radiological aspect is described, while the other aspects are referenced to safety analysis report of the facility. From the calculation it can be seen that in accident condition the total radiation dose received by the handling operator is 1.06 mSv and 1.6 mSv resulted from Kr-85 and 1-131. This is lower than the limitation recommended by the ICRP No. 60.1990. Verification for other safety aspect of the facility in still needed

Decommissioning and cutting methods in the nuclear field

Energy Technology Data Exchange (ETDEWEB)

Bensoussan, E. [Protem SAS, 26 - Etoile sur Rhone (France)

2008-07-01

A few states started in the early forties/fifties the first development of nuclear technologies. Some of them now own a great amount of nuclear installations which entirely fulfill their assignment. In some cases, the life time of the nuclear power plants which were scheduled for approximately 30 years have been extended by more than 50%, the other ones as well as fuel production and enrichment plants, experimental or research reactors, will have to be dismantled in the near future. The decommissioning of those installations is definitely one of the twenty first century challenge. It is differently managed depending on the countries and their energetic and development policies, their financial consideration, the availability of qualified engineers or specialized companies to handle such projects. The final aim of decommissioning is to recover the geographic site in its original condition. A real cooperation is existing in between the people involved in different countries through different types of conferences and meetings during which the main subjects are: - The safety of the operators during all the phases of decommissioning operations. - Restrictions and dimensioning of the required equipment - Storage and waste management - Elaboration of procedures for recording all different steps and processes. Some of the techniques are described in this paper without being exhaustive. (author)

Decommissioning and cutting methods in the nuclear field

International Nuclear Information System (INIS)

Bensoussan, E.

2008-01-01

A few states started in the early forties/fifties the first development of nuclear technologies. Some of them now own a great amount of nuclear installations which entirely fulfill their assignment. In some cases, the life time of the nuclear power plants which were scheduled for approximately 30 years have been extended by more than 50%, the other ones as well as fuel production and enrichment plants, experimental or research reactors, will have to be dismantled in the near future. The decommissioning of those installations is definitely one of the twenty first century challenge. It is differently managed depending on the countries and their energetic and development policies, their financial consideration, the availability of qualified engineers or specialized companies to handle such projects. The final aim of decommissioning is to recover the geographic site in its original condition. A real cooperation is existing in between the people involved in different countries through different types of conferences and meetings during which the main subjects are: - The safety of the operators during all the phases of decommissioning operations. - Restrictions and dimensioning of the required equipment - Storage and waste management - Elaboration of procedures for recording all different steps and processes. Some of the techniques are described in this paper without being exhaustive. (author)

Review of Impact Factors on Decommissioning Strategies

Energy Technology Data Exchange (ETDEWEB)

Yun, Taesik; Jung, Hyejin; Kim, Younggook [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

This article is prepared to factor out decommissioning strategies mostly appropriate to the decommissioning Kori-1 nuclear power plant. Terms used to delineate the lifetime of an authorized facility and of the associated licensing process consists of six core stages such as siting, design, construction, commissioning, operation and decommissioning. The term decommissioning implies the administrative and technical actions taken to allow the removal of some or all of the regulatory controls from a facility except for the part of a disposal facility in which the radioactive waste is emplaced. Whole range of each process of decommissioning should be considered throughout the other five stages. The decommissioning process is typically composed of its planning, conducting actions and terminating the authorization. In order to achieve the successful decommissioning, the impact factor on the strategy should be analyzed and evaluated to optimally apply to Kori-1 project. From my perspective, among eight factor, stakeholder’s consideration and spent fuel management are considered the key elements we have to concentrate on to smoothly go ahead for successful decommissioning of Kori-1.

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)

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

Spent fuel storage criticality safety

Energy Technology Data Exchange (ETDEWEB)

Amin, E M; Elmessiry, A M [National center of nuclear safety and radiation control atomic energy authority, (Egypt)

1995-10-01

The safety aspects of the spent fuel storage pool of the Egyptian test and research reactor one (ET-R R-1) has to be assessed as part of a general overall safety evaluation to be included in a safety analysis report (SAR) for this reactor. The present work treats the criticality safety of the spent fuel storage pool. Conservative calculations based on using fresh fuel has been performed, as well as less conservative using burned fuel. The calculations include cross library generation for burned and fresh fuel for the ET-R R-1 fuel type. The WIMS-D 4 code has been used in library generation and burn up calculation the critically calculations are performed using the one dimensional transport code (ANISN) and the two dimensional diffusion code (DIXY2). The possibility of increasing the storage efficiency either by insertion of absorber sheets of soluble boron salts or by reduction of fuel rod separation has been studied. 8 figs., 2 tabs.

Spent fuel storage criticality safety

International Nuclear Information System (INIS)

Amin, E.M.; Elmessiry, A.M.

1995-01-01

The safety aspects of the spent fuel storage pool of the Egyptian test and research reactor one (ET-R R-1) has to be assessed as part of a general overall safety evaluation to be included in a safety analysis report (SAR) for this reactor. The present work treats the criticality safety of the spent fuel storage pool. Conservative calculations based on using fresh fuel has been performed, as well as less conservative using burned fuel. The calculations include cross library generation for burned and fresh fuel for the ET-R R-1 fuel type. The WIMS-D 4 code has been used in library generation and burn up calculation the critically calculations are performed using the one dimensional transport code (ANISN) and the two dimensional diffusion code (DIXY2). The possibility of increasing the storage efficiency either by insertion of absorber sheets of soluble boron salts or by reduction of fuel rod separation has been studied. 8 figs., 2 tabs

Platform decommissioning costs

International Nuclear Information System (INIS)

Rodger, David

1998-01-01

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

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

The management and regulation of decommissioning wastes

International Nuclear Information System (INIS)

Berkhout, F.

1990-01-01

Radioactive waste management is an inevitable consequence of nuclear technology. In the past it was often regarded as a peripheral matter, easily dealt with, and having little impact on the economics of the fuel cycle. Gradually, over the last two decades, waste management has asserted itself as one of nuclear power's most intractable problems. First, it is a problem of trying to understand through science the effects of discharging and disposing of man-made radioactivity to the general environment. Second, technologies for treating and disposing of the wastes, as well as techniques to verify their safety, must be developed. Third, and most problematically, a wide spread of public trust in the techniques of management must be nurtured. Disputes over each of these dimensions of the question exist in nearly all countries with nuclear programmes. Some of them may be near resolution, but many others are far from closure. Decommissioning, because it comes last in the nuclear life-cycle, is also the last important aspect of the technology to be considered seriously. In Britain, wastes arising from decommissioning, whether it is done slowly or quickly, are projected to have an important impact on the scale of radioactive waste management programmes, beginning in the mid-1990s. It follows that decommissioning, contentious in itself, is likely to exacerbate the difficulties of waste management. (author)

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

International Nuclear Information System (INIS)

Konzek, G.J.; Smith, R.I.

1988-07-01

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

Technology, safety and costs of decommissioning a refernce boiling water reactor power station: Technical support for decommissioning matters related to preparation of the final decommissioning rule

International Nuclear Information System (INIS)

Konzek, G.J.; Smith, R.I.

1988-07-01

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

Decommissioning project feedback experience in the Japan Atomic Energy Research Institut

International Nuclear Information System (INIS)

Yanagihara, S.; Tachibana, M.; Miyajima, K.

2003-01-01

and to implement a decommissioning project in safe and economical manner. The Japan Power Demonstration Reactor (JPDR) decommissioning project was completed by March, 1996, accumulating various data, experience and know-how on dismantling activities. The data and project experience were analyzed for future decommissioning of commercial and research nuclear facilities, in which the lessons learnt are categorized into three groups: safety case, waste management and work efficiency. The feedback experience was good for planning and implementing decommissioning projects. This paper deals with the decommissioning projects and the feedback experience in JAERI. At present more than 20 research nuclear facilities are listed for decommissioning in the near future in JAERI, and some of the facilities are in dismantling stage. In addition, nearly 200 nuclear facilities will be decommissioned in JAERI and JNC for 80 years after unification of both research organizations. Consequently, it has been required to implement the decommissioning projects in safe and economical manner by effectively referring the past decommissioning experience. JPDR and JRTF decommissioning projects were set up as demonstration programs for future decommissioning of large nuclear facilities. The JPDR decommissioning project was completed successfully without serious problems, accumulating various data and know-how. The JRTF decommissioning project has also been in progress, in which the experience of JPDR dismantling activities are referred and various data and experience are collected to characterize the dismantling activities in fuel cycle facilities. In case of JRR-2 decommissioning project, it has been decided that the building will be used for a centralized fuel storage facility for the time before dismantling the core part. Various lessons learnt have been accumulated through these projects, including technology application, project management and organizational matters. The project data and the

Decommissioning and dismantling of 305-M test pile at the Savannah River Plant

International Nuclear Information System (INIS)

Horton, H.L.

1985-01-01

The 305-M Test Pile was started up at the Savannah River Plant in 1952 and operated until 1981. The pile was used to measure the uranium content of reactor fuel. In 1984 work began to decommission and dismantle the pile. Extensive procedures were used that included a detailed description of the radiological controls and safety measures. These controls allowed the job to be completed with radiation doses as low as reasonably achievable

Site decommissioning management plan

International Nuclear Information System (INIS)

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

1993-10-01

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

Site decommissioning management plan

Energy Technology Data Exchange (ETDEWEB)

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

1993-10-01

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

Management of waste associated with the decommissioning of the JASON research reactor and the nuclear laboratories at the Royal Naval College Greenwich

International Nuclear Information System (INIS)

Beeley, P.A.; Lockwood, R.J.S.; Hoult, D.; Major, R.

2001-01-01

tonnes packed in 6 disposal skips. These estimates will be compared to the actual waste inventories as reported in the projects Post Decommissioning Report. With respect to the overall waste management strategy, a Post Operational Clean Out (POCO) phase preceded decommissioning. This allowed all approved discharges and transfers to occur under the facility operational safety case, including the disposal of laboratory sources and the reactor start-up source (185 GBq 241 Am/Be) by Safeguards International. The reactor fuel was then transported off-site under a fuel removal safety case. In addition, the reactor control plates, drive motors and in-core nuclear detectors were removed, designated as ILW, packaged and transported under the decommissioning safety case so that all major radioactive hazards were removed from the facility prior to construction of the main waste handling and transfer facilities. All ILW was sent for storage at the UK's national facility at UKAEA Harwell. Waste categorisation, size reduction and initial packaging was carried out in the reactor hall and items were transferred by trolley to an airlock/storage area. Waste was segregated according to type, monitored and transported across the airlock/storage boundary for further interim storage or direct loading of ISO containers. The assay of waste, size reduction, packaging, radiological monitoring and final, removal of waste to designated ILW, LLW or FLW facilities will be described. In addition, the special case of low level tritium waste in the facility, its assay and removal will be discussed. Finally, the results and conclusions of the Post Decommissioning Report will be compared to the proposed waste management scheme in the Preliminary Safety Report and any significant lessons learned will be addressed

Communications programme for the RA nuclear reactor decommission

International Nuclear Information System (INIS)

Milanovic, S.; Antic, D.

2002-01-01

During the decommissioning of the RA research nuclear reactor at the VINCA Institute of Nuclear Sciences, an adequate number of radiation and contamination surveys should be conduced to assure radiological safety of the workers, the public and the environment. Public would like to know more about the nuclear and radiological safety. The communications programme defines the ways to informing the public, its representatives and the information media about the health and safety aspects of the activities during the RA nuclear reactor decommission. (author)

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

The WAK decommissioning and dismantling program

International Nuclear Information System (INIS)

Eiben, K.; Fritz, P.

1995-01-01

After an extensive rinsing of the reprocessing equipment the operation in the plant was terminated in 1991 following the principal political decision to abolish reprocessing of nuclear fuel in Germany. Since July 1991 only the safety relevant units are still in operation including the waste storage facilities for 80 m 3 of high active waste concentrate (HAWC). The decommissioning and dismantling will be achieved in six steps taking into account that some of the reprocessing equipment can be dismantled before and the rest only after the HAWC has been vitrified approximately by mid 2000. So far two licenses for decommissioning have been granted. An application for the dismantling of twelve systems in the process building including headend and tailend facilities will be licensed in 1995. The remote dismantling of equipment from the hot cells in the process building is being planned and will be executed between 1998--2001. New remote handling equipment will be cold tested in a test facility scheduled to start in the middle of this year. The final task is the green meadow after demolishing of the building and remediation of the site which is scheduled for 2005

Nuclear Safety Technical Progress Journal, January--June 1995. Volume 36, No. 1

Energy Technology Data Exchange (ETDEWEB)

Silver, E G [ed.

1995-01-01

This journal covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

State fund of decommissioning of nuclear installations and handling of spent nuclear fuels and nuclear wastes (Slovak Republic)

International Nuclear Information System (INIS)

Kozma, Milos

2006-01-01

State Fund for Decommissioning of Nuclear Installations and Handling of Spent Nuclear Fuels and Nuclear Wastes was established by the Act 254/1994 of the National Council of the Slovak Republic as a special-purpose fund which concentrates financial resources intended for decommissioning of nuclear installations and for handling of spent nuclear fuels and radioactive wastes. The Act was amended in 2000, 2001 and 2002. The Fund is legal entity and independent from operator of nuclear installations Slovak Power Facilities Inc. The Fund is headed by Director, who is appointed and recalled by Minister of Economy of the Slovak Republic. Sources of the Fund are generated from: a) contributions by nuclear installation operators; b) penalties imposed by Nuclear Regulatory Authority of the Slovak Republic upon natural persons and legal entities pursuant to separate regulation; c) bank credits; d) interest on Fund deposits in banks; e) grants from State Budget; f) other sources as provided by special regulation. Fund resources may be used for the following purposes: a) decommissioning of nuclear installations; b) handling of spent nuclear fuels and radioactive wastes after the termination of nuclear installation operation; c) handling of radioactive wastes whose originator is not known, including occasionally seized radioactive wastes and radioactive materials stemming from criminal activities whose originator is not known, as confirmed by Police Corps investigator or Ministry of Health of the Slovak Republic; d) purchase of land for the establishment of nuclear fuel and nuclear waste repositories; e) research and development in the areas of decommissioning of nuclear installations and handling of nuclear fuels and radioactive wastes after the termination of the operation of nuclear installations; f) selection of localities, geological survey, preparation, design, construction, commissioning, operation and closure of repositories of spent nuclear fuels and radioactive wastes

Decommissioning and environmental remediation: An overview

International Nuclear Information System (INIS)

Chatzis, Irena

2016-01-01

The objective in both decommissioning and environmental remediation is to lower levels of residual radioactivity enough that the sites may be used for any purpose, without restriction. In some cases, however, this may not be practical and restrictions may be placed on future land use. Following decommissioning, for example, some sites may be reused for non-nuclear industrial activities, but not for habitation. Some former uranium mining sites may be released for reuse as nature reserves or for other leisure activities. Both decommissioning and environmental remediation are major industrial projects in which the safety of the workforce, the local public and the environment must be ensured from both radiological and conventional hazards. Hence, an appropriate legal and regulatory framework, as well as proper training for personnel both in implementation and in regulatory oversight are among the necessary preconditions to ensure safety.

Decommissioning and environmental remediation: An overview

International Nuclear Information System (INIS)

Chatzis, Irena

2016-01-01

The objective in both decommissioning and environmental remediation is to lower levels of residual radioactivity enough that the sites may be used for any purpose, without restriction. In some cases, however, this may not be practical and restrictions may be placed on future land use. Following decommissioning, for example, some sites may be reused for non-nuclear industrial activities, but not for habitation. Some former uranium mining sites may be released for reuse as nature reserves or for other leisure activities. Both decommissioning and environmental remediation are major industrial projects in which the safety of the workforce, the local public and the environment must be ensured from both radiological and conventional hazards. Hence, an appropriate legal and regulatory framework, as well as proper training for personnel both in implementation and in regulatory oversight are among the necessary preconditions to ensure safety

Decommissioning: guiding principles and best practices for involving local stakeholders

International Nuclear Information System (INIS)

Keyes, D.

2005-01-01

Full text: A wide range of nuclear facilities covering the entire nuclear fuel cycle have been constructed and operated for many years worldwide. For communities where the facilities are located, concerns about safety and environmental contamination are paramount. Working together with elected officials, local community leaders and the public at large during the earliest planning stages will help alleviate concerns about facility operation and ultimate disposition, and will result in better decisions about facility design, location, construction, operation and, ultimately, decommissioning. Such comprehensive community involvement has been the exception rather than the norm. Now that older facilities are being considered for decommissioning, efforts to involve local stakeholders and alleviate their concerns face major challenges. This is particularly true where some residual radioactive contamination will remain onsite and future use of the site may need to be restricted. Plans for stakeholder involvement at the decommissioning stage should be carefully designed and provide for honest, authentic and meaningful involvement of all stakeholders affected by decommissioning decisions. A set of principles and best practices is proposed to help guide the design and implementation of effective community involvement programs. The principles and best practices are drawn from the experiences of public involvement practitioners in a variety of environmental contamination applications. Successful community involvement is the result of a carefully crafted set of coordinated activities conducted over the long term. Ideally, facility decommissioning is simply the end stage of the involvement process, or the beginning of a site stewardship process in those cases where decommissioning does not produce an uncontaminated site. In either case, decommissioning will not be a new, unexpected event, and stakeholders could be involved just as they have been over the life of the facility. In

Predisposal management of low and intermediate level radioactive waste. Safety guide

International Nuclear Information System (INIS)

2003-01-01

Radioactive waste is generated in the generation of electricity in nuclear power reactors and in the use of radioactive material in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized. The principles and requirements that govern the safety of the management of radioactive waste are presented in 'The Principles of Radioactive Waste Management', 'Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety' and 'Predisposal Management of Radioactive Waste, Including Decommissioning'. The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established in Refs for the predisposal management of LLW. This Safety Guide deals with the safety issues associated with the predisposal management of LLW from nuclear fuel cycle facilities, large research and development installations and radioisotope production facilities. This includes all steps and activities in the management of waste, from its initial generation to its final acceptance at a waste disposal facility or the removal of regulatory control. The predisposal management of radioactive waste includes decommissioning. The term 'decommissioning' encompasses both the process of decommissioning a facility and the management of the waste that results (prior to its disposal). Recommendations on the process of decommissioning are provided in Refs. Recommendations on the management of the waste resulting from decommissioning are included in this Safety Guide. Although the mining and milling of uranium and thorium ores is part of the nuclear fuel cycle, the management of the operational waste (e.g. waste rock, tailings and effluent treatment waste) from these activities is not within the scope of this Safety Guide. The LLW that is

Planning and management for reactor decommissioning

International Nuclear Information System (INIS)

Miyasaka, Yasuhiko

2001-01-01

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

National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2003

International Nuclear Information System (INIS)

Burclova, J.; Ivan, J.; Jurina, V.

2003-04-01

A brief national safety report of the Slovak Republic in 2003 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (A) Introduction; (B) Policies and practices; (C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement; (J) Disused sealed sources; (K) Planned activities to improve safety; (L) Annexes: (I and II) List of SF and RAW management nuclear facilities; (III) List of nuclear facilities subject to decommissioning; (IV) Inventory of stored SF (t HM); (V) Inventory of disposed of and stored RAW; (VI) List of selected national laws, regulations and guidelines; (VII) List of international expert reports and safety analysis reports; (VIII) List of authors

National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2003

Energy Technology Data Exchange (ETDEWEB)

Burclova, J [Nuclear Regulatory Authority of the Slovak Republic, Bratislava (Slovakia); Ivan, J [Slovenske elektrarne, a.s., Bratislava (Slovakia); Jurina, V [Health Ministry of the Slovak Republic, Bratislava (Slovakia); and others

2003-04-01

A brief national safety report of the Slovak Republic in 2003 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (A) Introduction; (B) Policies and practices; (C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement; (J) Disused sealed sources; (K) Planned activities to improve safety; (L) Annexes: (I and II) List of SF and RAW management nuclear facilities; (III) List of nuclear facilities subject to decommissioning; (IV) Inventory of stored SF (t HM); (V) Inventory of disposed of and stored RAW; (VI) List of selected national laws, regulations and guidelines; (VII) List of international expert reports and safety analysis reports; (VIII) List of authors.

3D based integrated support concept for improving safety and cost-efficiency of nuclear decommissioning projects

International Nuclear Information System (INIS)

Szoeke, Istvan

2016-01-01

extensive rework during the decommissioning phase. 3D technologies have the potential for minimising knowledge loss during the transition to decommissioning, and support efficient reconstruction of design and other knowledge supporting more optimised decommissioning strategies. Application of advanced 3D visualisation technologies are applied for planning the manipulation of heavy large components in decommissioning projects. With the decreasing time and cost investment required for application of 3D simulation and AR technology, an increasing number of experts are exploring the possibilities in using such methods for supporting on-site logistics (categorisation, transportation, and temporary storage) of contaminated and activated components during decommissioning. 3D radiological simulation and visualisation technology provides a new more efficient way for explaining complex radiological conditions, work plans, and compliance with regulatory requirements. Advanced support systems based on 3D technologies have successfully been applied in the decommissioning of a number of nuclear installations (e.g. Fugen NPP, Chernobyl NPP, Leningrad NPP, Andreeva Bay branch of Northwest Center for Radioactive Waste Management in NW Russia) for increasing safety and optimising costs. For further details the reader is referred to the literature

JAEA involvement in Education and Training for Decommissioning

International Nuclear Information System (INIS)

Nakayama, Shinichi

2017-01-01

Education and Training for Decommissioning in Japan: E&T for decommissioning in Japan is: prioritized to decommissioning of TEPCO’s Fukushima Daiichi NPS; mostly government-funded: - Ministry Of Education, Culture, Sports, Science And Technology; -Ministry Of Economy, Trade And Industry; performed through collaborative R&D activities between research institutes, university/college, and academic societies. JAEA is involved in the E&T through: - University summer schools on robotics, decommissioning robot competition; - Participation in and/or invitation to JAEA’s international Fukushima Research Conferences, and to cooperative courses with scientific institutions; - Lectures at universities/colleges; - Hot facility construction/operation for engineers, characterization of radioactive wastes and fuel debris for radiochemists and technicians

Implementation of the II. Stage decommissioning of A1 NPP

International Nuclear Information System (INIS)

Ficher, T.

2015-01-01

Presentation is focused on the implementation of the II. stage decommissioning of A1 NPP. Introductory part focuses on brief characteristics of the power plant with a history of operation, basic technical parameters and actions that were made after operation. The next section describes the basic schedule for decommissioning, structure of management and implementation of the II. stage decommissioning of the A1 NPP and objectives of the individual stages. The last and largest part of the presentation is devoted to detailed description of the II. stage decommissioning of the A1 NPP, its individual tasks and verbal and visual description of the activities that were performed. Presented is decommissioning of the technology and construction of external objects NPP A1 including storage tanks for liquid RAW, next are presented activities carried out in the Main Production Unit - decommissioning of non-operating technologies in various places/rooms, management of waste arising from these activities, treatment of case of A1 long-term spent fuel storage and long-term spent fuel storage. The subsequent section is devoted to the management and handling of contaminated soil, concrete and construction waste, including management of VLLW. (authors)

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

An analysis of decommissioning costs

International Nuclear Information System (INIS)

Teunckens, L.; Loeschhorn, U.; Yanagihara, S.; Wren, G.; Menon, S.

1992-01-01

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

Activation analysis of dual-purpose metal cask after the end of design lifetime for decommission

Energy Technology Data Exchange (ETDEWEB)

Kim, Tae Man; Ku, Ji Young; Dho Ho Seog; Cho, Chun Hyung [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of); Ko, Jae Hun [Korea Nuclear Engineering and Service Co., Daejeon (Korea, Republic of)

2016-12-15

The Korea Radioactive Waste Agency (KORAD) has developed a dual-purpose metal cask for the dry storage of spent nuclear fuel that has been generated by domestic light-water reactors. The metal cask was designed in compliance with international and domestic technology standards, and safety was the most important consideration in developing the design. It was designed to maintain its integrity for 50 years in terms of major safety factors. The metal cask ensures the minimization of waste generated by maintenance activities during the storage period as well as the safe management of the waste. An activation evaluation of the main body, which includes internal and external components of metal casks whose design lifetime has expired, provides quantitative data on their radioactive inventory. The radioactive inventory of the main body and the components of the metal cask were calculated by applying the MCNP5·ORIGEN-2 evaluation system and by considering each component's chemical composition, neutron flux distribution, and reaction rate, as well as the duration of neutron irradiation during the storage period. The evaluation results revealed that 10 years after the end of the cask's design life, {sup 60}Co had greater radioactivity than other nuclides among the metal materials. In the case of the neutron shield, nuclides that emit high-energy gamma rays such as {sup 28}Al and {sup 24}Na had greater radioactivity immediately after the design lifetime. However, their radioactivity level became negligible after six months due to their short half-life. The surface exposure dose rates of the canister and the main body of the metal cask from which the spent nuclear fuel had been removed with expiration of the design lifetime were determined to be at very low levels, and the radiation exposure doses to which radiation workers were subjected during the decommissioning process appeared to be at insignificant levels. The evaluations of this study strongly suggest that

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

Decommissioning and material recycling. Radiation risk management issues

International Nuclear Information System (INIS)

Dodd, D.H.

1996-09-01

Once nuclear fuel cycle facilities have permanently stopped operations they have to be decommissioned. The decommissioning of a nuclear facility involves the surveillance and dismantling of the facility systems and buildings, the management of the materials resulting from the dismantling activities and the release of the site for further use. The management of radiation risks associated with these activities plays an important role in the decommissioning process. Existing legislation covers many aspects of the decommissioning process. However, in most countries with nuclear power programmes legislation with respect to decommissioning is incomplete. In particular this is true in the Netherlands, where government policy with respect to decommissioning is still in development. Therefore a study was performed to obtain an overview of the radiation risk management issues associated with decommissioning and the status of the relevant legislation. This report describes the results of that study. It is concluded that future work at the Netherlands Energy Research Foundation on decommissioning and radiation risk management issues should concentrate on surveillance and dismantling activities and on criteria for site release. (orig.)

AMNT 2014. Key Topic: Reactor operation, safety - report. Pt. 1

International Nuclear Information System (INIS)

Schaffrath, Andreas

2014-01-01

Summary report on one session of the Annual Conference on Nuclear Technology held in Frankfurt, 6 to 8 May 2014: - Safety of Nuclear Installations - Methods, Analysis, Results: Backfittings for the Improvement of Safety and Efficiency. The other Sessions of the Key Topics 'Reactor Operation, Safety', 'Competence, Innovation, Regulation' and 'Fuel, Decommissioning and Disposal' will be covered in further issues of atw.

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

International Nuclear Information System (INIS)

England, M.R.; Parry, D.R.; Smith, C.

1998-01-01

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

Needs for European decommissioning academy (EDA)

International Nuclear Information System (INIS)

Slugen, Vladimir

2014-01-01

other countries, especially those having a large nuclear programme, and promote the highest safety levels. The EU 'Community acquits' includes key legislation such as the recent Council Directive 2011/70/EURATOM establishing the Community framework for the responsible and safe management of spent fuel and radioactive waste, which sets the legal obligations for adequate funding, financial security and transparency applicable to the national waste management systems. The need to maintain and increase competent and qualified staff is a recurrent concern in the nuclear sector. In particular, in view of the growing decommissioning market, it can be expected that industry will involve new actors, including, in some cases, small and middle enterprises. The organisation of ad hoc training programs is also essential with a strong link to research and educational organisations. For Central and Eastern European countries, where several units were shut-down before the end of their operating lifetime, decommission is one of most important tasks. According to the conclusions of the conference 'Eastern and Central European Decommissioning', held in June 2013, in Trnava, Slovakia it was stated that: 1. According to common experiences from VVER decommissioning - the creation of a master approach and procedures that could be recommended for all VVER countries. NPP V-1 in Bohunice, Slovakia can be perhaps the proper place for the verification of these procedures. 2. Education, training and proper knowledge management have specific relevance for decommissioning. Based on the training courses that we run at the Slovak University of Technology we would like to create a European Academy for Decommissioning for VVER countries in collaboration with EC and IAEA. Knowledge and decommissioning skills could be shared on an international level. Input from several organisations present here at the conference would be beneficial. We recommend that specific lessons, practical

Study on decommissioning

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

This study examines the status of maintenance of the decommissioning-related regulations to which the maintenance is still insufficient. The contents in 2012 are as follows. First, we examined site release criteria through reports by international organizations, by overseas countries where nuclear sites have been released, and the environment standards in Japan. Then we also examined the standards of decommissioning completion confirmation (in other words, site release criteria). The study results will be utilized to document standards. Second, we assessed the present Japanese decommissioning regulatory system based on safety requirements of IAEA, and identified improvements. Then we prepared an improvement plan benefiting from the regulatory experiences in foreign countries. The study results will be utilized to document standards. Third, the Fukushima Daiichi NPS, which experienced serious core accident in March, 2011, has become a Specified Nuclear Facilities according to the new nuclear regulation, and the examination of the implementation plan is performed of the Nuclear Regulation Authority. As Units 1 to 4 at the Fukushima Daiichi NPS are planned to be decommissioned, we investigated regulatory requirements in foreign countries which experienced severe accidents. (author)

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)

The decommissioning of commercial magnox gas cooled reactor power stations in the United Kingdom

International Nuclear Information System (INIS)

Holt, G.

1998-01-01

There are nine commercial Magnox gas-cooled reactor power stations in the United Kingdom. Three of these stations have been shutdown and are being decommissioning, and plans have also been prepared for the eventual decommissioning of the remaining operational stations. The preferred strategy for the decommissioning of the Magnox power stations has been identified as 'Safestore' in which the decommissioning activities are carried out in a number of steps separated by quiescent periods of care and maintenance. The final clearance of the site could be deferred for up to 135 years following station shutdown so as to obtain maximum benefit from radioactive decay. The first step in the decommissioning strategy is to defuel the reactors and transport all spent and new fuel off the site. This work has been completed at all three shutdown stations. Decommissioning work is continuing on the three sites and has involved activities such as dismantling, decontamination, recycling and disposal of some plant and structures, and the preparation of others for retention on the site for a period of care and maintenance. Significant experience has been gained in the practical application of decommissioning, with successful technologies and processes being identified for a wide range of activities. For example, large and small metallic and concrete structures, some with complex geometries, have been successfully decontaminated. Also, the reactors have been prepared for a long period of care and maintenance, with instrumentation and sampling systems having been installed to monitor their continuing integrity. All of this work has been done under careful safety, technical, and financial control. (author)

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.

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)

The decommissioning and redevelopment of NECSA site

International Nuclear Information System (INIS)

Visagie, A.L.; Fourie, E.

2008-01-01

Full text: The South African nuclear programme started in 1948 and was focussed on research and development in the nuclear field. In the early 70s a uranium conversion plant and a uranium enrichment plant were constructed on the NECSA site. The enriched uranium was used for military purposes, as fuel for the research reactor SAFARI-1 at Necsa. A semi-commercial uranium enrichment plant and a fuel manufacturing plant were commissioned in the 80's to supply fuel for the nuclear power plant at Koeberg near Cape Town. Currently the research reactor is utilized for the generation of radioactive isotopes for industrial and medical applications. Various other research projects were initiated and buildings constructed on the Necsa site to accommodate the different projects. The uranium conversion and enrichment projects were terminated in the early 90's, and many buildings on the Necsa site became redundant. An initial decommissioning strategy was to return the Necsa site to green fields. This endpoint of decommissioning has changed dramatically with the nuclear renaissance to include redevelopment and reuse options. In the case of a multi-facility nuclear site, such as the Necsa site, it is vital to develop a total site redevelopment plan rather than to decommission and allocate individual facilities for isolated reuse demands. A holistic approach should be assured by considering current and projected future redevelopment demands in the development of a redevelopment and reuse plan. It is important not to allow the redevelopment and reuse of a single facility on a multi-facility site based on short- term financial gain. With the recent increase in demand for nuclear facilities the redevelopment and reuse of nuclear facilities for non-nuclear applications should generally not be considered due to the inherent advantages associated with an existing licensed site. The initial decommissioning plan did not consider the Necsa site as a whole. Decommissioning costs, and the

Public attitudes toward nuclear power plant decommissioning

International Nuclear Information System (INIS)

Lough, W.T.

1987-01-01

A public workshop was conducted with a group of citizens to obtain the concerns and preferences of the group with respect to decommissioning. Seventeen concerns about decommissioning were identified and prioritized. The participants were most concerned about the potential health and safety effects from decommissioning. The potential impacts from the lost tax base and loss of employment were also rated highly. The estimated increase in electric utility rates was not a major concern. The participants were split fairly evenly on preferences about the methods of decommissioning. However, nine of the ten participants preferred power plant life extension over decommissioning by any method. Finally, the participants were given an evaluation questionnaire about the workshop. In general, they concluded that the process was effective, and they felt like they were a part of the Commission's planning process

Rapporteur's Report of the Workshop on Radiological Characterisation for Decommissioning

International Nuclear Information System (INIS)

Thierfeldt, Stefan

2012-01-01

In April 2012, the Nuclear Energy Agency, in co-operation with Studsvik Nuclear AB, the Swedish Radiation Safety Authority (SSM), Swedish Nuclear Fuel and Waste Management Company (SKB) and AB SVAFO, held a Workshop on Radiological Characterisation in Decommissioning in Studsvik near Nykoeping (Sweden). During three days, a wide range of presentations, posters, discussions and site visits brought together over 120 participants from 23 countries and 4 international organisations, the IAEA, the WNA, the European Commission and the OECD/NEA. Members of the Task Group on Radiological Characterisation for Decommissioning (RCD) of the WPDD were involved in the preparation of the workshop. Many decommissioning projects of all types of nuclear installations have progressed substantially and/or have been completed to brown field or green field conditions, so that it was the right time to bring together operators, regulators, scientists, consultants and contractors to exchange information and views and to evaluate the information on radiological characterisation gained from this multitude of projects. The outcome will be valuable for the large number of decommissioning projects about to start in the near future. The Workshop consisted of 5 topical sessions and a poster session. The topical sessions were complemented by discussions in the plenary and in smaller groups. This report provides a short summary of the various presentations and discussions. It concentrates on the outcome of the presentations, posters and discussions than giving an account of the spoken word

Sweden's first national report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

International Nuclear Information System (INIS)

2003-01-01

-assessment by each Contracting Party regarding compliance with the obligations of the Joint Convention. This self-assessment should be reported in the National Report to the Review Meetings. Sweden's self-assessment has demonstrated compliance with all the obligations of the Convention, as shown in detail in section B to K of this report. Having taken a very active part in the creation of the Joint Convention, Sweden wishes to emphasise this incentive. In Sweden's opinion, the Convention implies a commitment to the continuous improvement of safety whenever operating experience, safety research or technical development indicate room for such improvement. Continuous learning from experience and a proactive approach to safety are in fact corner stones of the current Swedish nuclear and radiation safety work, both for the industry and the regulatory bodies. Therefore, Sweden has found it important that its National Report highlights strong features in national practices, as well as areas in which improvements are justified. Implementation of such improvements should then be followed up in the National Reports to subsequent Review Meetings. As general conclusions with regard to strong features in national practices, Sweden would like to point out the following: - The responsibility for safety is clearly defined in the Swedish legal framework. In order not to dilute the responsibility of the licence holders, the Swedish regulations are designed to define requirements to be achieved, not the detailed means to achieve them. Within the framework given by the regulations, the licence holders have to define their own solutions, and demonstrate the safety level achieved to the regulatory bodies. - The legislation clearly defines that all licence holders are responsible for the safe handling and disposal of spent fuel and radioactive waste, as well as for the decommissioning and dismantling of facilities. - The operators of nuclear power plants must jointly carry out the research and

Decommissioning and disposal costs in Switzerland

International Nuclear Information System (INIS)

Zurkinden, Auguste

2003-01-01

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

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.

Safety decommissioning regulations of radiochemical objects - the problem, requires urgent decision

International Nuclear Information System (INIS)

Rovnyj, S.I.; Arsent'eva, N.V.; Emel'yanov, N.M.; Kolesnikov, V.N.

2001-01-01

The necessity of planning and pursuance of the measures on decommissioning of radiochemical industry is discussed. Technological processes were stopped more than in 30 buildings and constructions of the PO Mayak. The characteristics of the technological buildings to be decommissioned were treated in the context of building peculiarities, function, character and level of contamination. An acceptable variant for reactor decommissioning invites development of the standard-legal aspects [ru

CPP-603 Chloride Removal System Decontamination and Decommissioning

International Nuclear Information System (INIS)

Moser, C.L.

1993-02-01

The CPP-603 (annex) Chloride Removal System (CRS) Decontamination and Decommissioning (D ampersand D) Project is described in this report. The CRS was used for removing Chloride ions and other contaminants that were suspended in the waters of the underwater fuel storage basins in the CPP-603 Fuel Receiving and Storage Facility (FRSF) from 1975 to 1981. The Environmental Checklist and related documents, facility characterization, decision analysis', and D ampersand D plans' were prepared in 1991. Physical D ampersand D activities were begun in mid summer of 1992 and were completed by the end of November 1992. All process equipment and electrical equipment were removed from the annex following accepted asbestos and radiological contamination removal practices. The D ampersand D activities were performed in a manner such that no radiological health or safety hazard to the public or to personnel at the Idaho National Engineering Laboratory (INEL) occurred

A nationwide modelling approach to decommissioning - 16182

International Nuclear Information System (INIS)

Kelly, Bernard; Lowe, Andy; Mort, Paul

2009-01-01

In this paper we describe a proposed UK national approach to modelling decommissioning. For the first time, we shall have an insight into optimizing the safety and efficiency of a national decommissioning strategy. To do this we use the General Case Integrated Waste Algorithm (GIA), a universal model of decommissioning nuclear plant, power plant, waste arisings and the associated knowledge capture. The model scales from individual items of plant through cells, groups of cells, buildings, whole sites and then on up to a national scale. We describe the national vision for GIA which can be broken down into three levels: 1) the capture of the chronological order of activities that an experienced decommissioner would use to decommission any nuclear facility anywhere in the world - this is Level 1 of GIA; 2) the construction of an Operational Research (OR) model based on Level 1 to allow rapid what if scenarios to be tested quickly (Level 2); 3) the construction of a state of the art knowledge capture capability that allows future generations to learn from our current decommissioning experience (Level 3). We show the progress to date in developing GIA in levels 1 and 2. As part of level 1, GIA has assisted in the development of an IMechE professional decommissioning qualification. Furthermore, we describe GIA as the basis of a UK-Owned database of decommissioning norms for such things as costs, productivity, durations etc. From level 2, we report on a pilot study that has successfully tested the basic principles for the OR numerical simulation of the algorithm. We then highlight the advantages of applying the OR modelling approach nationally. In essence, a series of 'what if...' scenarios can be tested that will improve the safety and efficiency of decommissioning. (authors)

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.)

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.)

Decommissioning and demolition in the European Union. Current status

International Nuclear Information System (INIS)

Blohm-Hieber, Ute

2009-01-01

The European Commission pursues the environmental and energy policy goals of limiting global warming to a maximum of 2 C and, therefore, reducing CO 2 emissions by at least 20%. Nuclear power, with its present 30% contribution to the Community's electricity supply and the low CO 2 emissions of the entire fuel cycle, makes an important contribution to an energy mix matching the 3 factors of competitiveness, security of supply, and sustainability. The decision to use nuclear power plants in their respective countries for electricity production is left to each member state. As of mid-2008, 146 nuclear power plants were in operation in the European Union, while 74 had been shut down permanently. Two nuclear power plants had been demolished completely, showing that the European Community is just at the beginning of the learning curve in this field. The importance of nuclear power plant decommissioning and demolition will increase in the future as replacement capacity in nuclear power generation will become necessary. The European Commission's activities in decommissioning and demolition date from the 1990s: The provisions about environmental impact assessment and the recommendations to apply Article 37 (potential impacts on water, soil and air) of the Euratom Treaty demand a description of decommissioning and demolition of nuclear power plants. In a ruling of 2002, the European Court of Justice assigns to the Community the required competences in the fields of nuclear safety and, consequently, also decommissioning and demolition. The financial provisions necessary for these activities are covered in the Electricity Directive within the framework of the rules for a common single market in 2003. After a first status report, the Commission published recommendations about financing decommissioning and demolition in 2006. (orig.)

Germany: Management of decommissioning waste in Germany

International Nuclear Information System (INIS)

Borrmann, F.; Brennecke, P.; Koch, W.; Kugel, K.; Steyer, S.

2007-01-01

Over the past two decades, Germany has gained a substantial amount of experience in the decommissioning of nuclear facilities of different types and sizes. Many research reactors and all prototype nuclear power plants, as well as a few larger nuclear power plants and fuel cycle facilities, are currently at varying stages of decommissioning. Several facilities have been fully dismantled and the sites have been cleared for reuse. The decommissioning projects comprise 18 power and prototype reactors, 33 research reactors and 11 fuel cycle facilities which are being or have been decommissioned. In the future, further nuclear power plants will be shut down and decommissioned in accordance with Germany?s energy policy to phase out the use of nuclear power for commercial electricity generation as given in the April 2002 amendment of the Atomic Energy Act. Radioactive waste, from operations as well as from decommissioning activities, is to be conditioned in such a way as to comply with the waste acceptance requirements of a repository. In Germany, all types of radioactive waste (i.e., short-lived and long-lived) are to be disposed of in deep geological formations. A distinction is being made for heat generating waste (i.e., high level waste) and waste with negligible heat generation (i.e., low level and intermediate level waste). Radioactive decommissioning waste is waste with negligible heat generation. Waste acceptance requirements of a repository are of particular importance for the conditioning of radioactive waste, including decommissioning waste. The waste acceptance requirements, as they resulted from the Konrad licensing procedure, are being applied by the waste generators for the conditioning of decommissioning waste. Compliance with these requirements must be demonstrated through the waste package quality control, even if the waste will be disposed of in the future. In 2002 the Konrad repository was licensed for the disposal of all types of waste with negligible

AMNT 2014. Key Topic: Reactor operation, safety - report. Pt. 1

Energy Technology Data Exchange (ETDEWEB)

Schaffrath, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH (GRS), Garching (Germany). Forschungszentrum

2014-10-15

Summary report on one session of the Annual Conference on Nuclear Technology held in Frankfurt, 6 to 8 May 2014: - Safety of Nuclear Installations - Methods, Analysis, Results: Backfittings for the Improvement of Safety and Efficiency. The other Sessions of the Key Topics 'Reactor Operation, Safety', 'Competence, Innovation, Regulation' and 'Fuel, Decommissioning and Disposal' will be covered in further issues of atw.

Challenges for decommissioning policies

International Nuclear Information System (INIS)

Riotte, H.

2007-01-01

In the coming years, OECD member countries will be increasingly faced with the need to make appropriate provisions, in terms of policy, finance and management, for all aspects of decommissioning. Decommissioning requires regulatory approval and oversight, the directions of which are guided by national policy. In several instances, governments have only recently begun to address their approaches to decommissioning policy and regulation in national legislation, and international overviews of such approaches, which may eventually lead to international harmonization, are only now beginning to emerge. In parallel, policy and regulation have been evolving and a broadened competence has developed in relevant regulatory authorities. The challenge lying ahead is to establish a framework that will allow for the growth of nuclear industrial activities in competitive, globalized markets, while maintaining and assuring the safety of decommissioning for the public and for workers. Within this context, institutional arrangements, stakeholder issues, costs and funding, waste management and policies for release from regulatory control, as well as the availability of technologies and skills, need to be reviewed. (author)

CSNI Technical Opinion Papers No. 15 - Ageing management of nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Nocture, Pierre; Daubard, Jean-Paul; Lhomme, Veronique; Martineau, Dominique; Blundell, Neil; Conte, Dorothee; Dobson, Martin; Gmal, Bernhard; Hiltz, Thomas; Ueda, Yoshinori

2012-01-01

Managing the ageing of fuel cycle facilities (FCFs) means, as for other nuclear installations, ensuring the availability of required safety functions throughout their service life while taking into account the changes that occur with time and use. This technical opinion paper identifies a set of good practices by benchmarking strategies and good practices on coping with physical ageing and obsolescence from the facility design stage until decommissioning. It should be of particular interest to nuclear safety regulators, fuel cycle facilities operators and fuel cycle researchers [fr

The Nordic programme on waste and decommissioning (KAN) 1990-93

International Nuclear Information System (INIS)

1994-03-01

In assessing nuclear waste safety, both long term and short term aspects need to be considered. For the development of a system for the final disposal of spent nuclear fuel, the most challenging task is to develop a sufficient understanding of the long term safety of a potential repository. Two of the NKS-projects are directly relevant for the long term safety of a deep geological repository, whereas the other projects mainly concern issues in managing nuclear waste today. Information about repositories and their contents must be conserved so that it can be easily retrieved. The KAN-1.3 studies deal with available information and how to preserve it. Archive safety as well as the expected durability of different archive media is explored. In the long term the present day climate will change significantly. An important part of the KAN-3 project has been to assemble field evidence, such as historic data indicating effects of past glaciations. The potential impact of a future glaciation on a repository is also explored in this project. An unlikely accident at a nuclear power plant could result in deposition of radioactive elements in the environment so that cleanup becomes necessary. In the KAN-2 project waste volumes and activities in different environments are estimated. Experiments have been performed with soil removal, and with cement solidification, and cost-benefit analyses are developed for use in emergency planning. Clearance of radioactive materials from regulatory control may reduce waste volumes that must otherwise be handled as radioactive, especially in conjunction with decommissioning. In the KAN-1.1 project the essential aspects of the clearance problems are dealt with such as definitions, radiological assessments, monitoring, and preparation of a clearance application. Eventually all nuclear installations in the Nordic countries will have to be decommissioned. In the KAN-1.2 project, the decommissioning of a pilot reprocessing plant is documented and

Safety of research reactors. Topical issues paper no. 4

International Nuclear Information System (INIS)

Alcala-Ruiz, F.; Ferraz-Bastos, J.L.; Kim, S.C.; Voth, M.; Boeck, H.; Dimeglio, F.; Litai, D.

2001-01-01

Assessment of Research Reactors (INSARR) missions. The prime objective of these missions has been to conduct a comprehensive operational safety review of the research reactor facility and to verify compliance with the IAEA Safety Standards. The methods used during an INSARR mission have been collected and analysed. Some of the important issues identified are the following: general ageing of the facility; uncertain status of many research reactors (in extended shutdown); indefinite deferral of return to operation or decommissioning; inadequate regulatory supervision; insufficient systematic (periodic) reassessment of safety; lack of quality assurance (QA) programmes; lack of an international safety convention or arrangement; lack of financial support for safety measures (e.g. safety reassessment, safety upgrading, decommissioning) and utilization; lack of clear utilization programmes; inadequate emergency preparedness; inadequate safety documentation (e.g. safety analysis report, operating rules and procedures, emergency plan); inadequate funding of shutdown reactors; weak safety culture; loss of expertise and corporate memory; loss of information concerning radioactive materials contained in retired experimental devices stored in the facility indefinitely; obsolescence of equipment and lack of spare parts; inadequate training and qualifications of regulators and operators; safety implications of new fuel types. These issues have been addressed by the IAEA Secretariat and the chairman of the International Nuclear Safety Advisory Group (INSAG). INSAG has identified three major safety issues that are: the increasing age of research reactors, the number of research reactors that are not operating anymore but have not been decommissioned, and the number of research reactors in countries that do not have appropriate regulatory authorities. This issue paper discusses the concerns generated by an analysis of the results of INSARR missions and those expressed by INSAG. The

Issues, challenges, and approaches for risk-informed decommissioning in the United States

International Nuclear Information System (INIS)

Orlando, D.A.; Johnson, R.L.

2005-01-01

Full text: The U.S. Nuclear Regulatory Commission (US-NRC) is the principal Federal regulatory authority in the United States responsible for ensuring public health and safety from the civilian use of radioactive material. US-NRC staff has developed and implemented various risk-informed approaches for regulating and managing the remediation of contaminated sites. A risk-informed approach to regulating the decommissioning of nuclear facilities has been generally defined by the US-NRC staff as an approach to decision-making that uses risk insights as well as traditional considerations to focus regulator and licensee attention on decommissioning activities commensurate with their importance to health and safety. Ensuring that decommissioning is carried out using a risk-informed approach should improve the focus on safety in decommissioning, improve the effectiveness, efficiency, and realism in regulatory decisions, and reduce unnecessary regulatory burden, and cost, on licensees. This paper summarizes the efforts by the US-NRC to develop and implement risk-informed approaches to the remediation of nuclear facilities in the United States. It also discusses the issues and challenges encountered by the US-NRC in attempting to implement a risk-informed approach to decommissioning. The US-NRC has been incrementally implementing its existing risk-informed and performance-based approach as it has completed its decommissioning regulations, guidance and other tools over the past several years. The principal challenge for US-NRC is implementing the existing risk-informed approach at specific sites in a manner that maintains safety, reduces costs, and enhances public understanding of the US-NRC's approach. In addition, effectively communicating how the US-NRC approaches are risk-informed and performance-based; ensuring that licensees understand, and take advantage of, the flexibility in meeting the decommissioning goals; ensuring that licensees and staff are aware of the

Safety analysis of spent fuel packaging

International Nuclear Information System (INIS)

Akamatsu, Hiroshi; Taniuchi, Hiroaki; Tai, Hideto

1987-01-01

Many types of spent fuel packagings have been manufactured and been used for transport of spent fuels discharged from nuclear power plant. These spent fuel packagings need to be assesed thoroughly about safety transportation because spent fuels loaded into the packaging have high radioactivity and generation of heat. This paper explains the outline of safety analysis of a packaging, Safety analysis is performed for structural, thermal, containment, shielding and criticality factors, and MARC-CDC, TRUMP, ORIGEN, QAD, ANISN, KENO, etc computer codes are used for such analysis. (author)

Methodology for Determining the Radiological Status of a Process: Application to Decommissioning of a Fuel Reprocessing Plant

International Nuclear Information System (INIS)

Girones, Ph.; Ducros, C.; Legoaller, C.; Lamadie, F.; Fulconis, J.M.; Thiebaut, V.; Mahe, C.

2006-01-01

Decommissioning a nuclear facility is subject to various constraints including regulatory safety requirements, but also the obligation to limit the waste volume and toxicity. To meet these requirements the activity level in each component must be known at each stage of decommissioning, from the preliminary studies to the final release of the premises. This document describes a set of methods used to determine the radiological state of a spent fuel reprocessing plant. This approach begins with a bibliographical survey covering the nature of the chemical processes, the operational phases, and the radiological assessments during the plant operating period. In this phase it is also very important to analyze incidents and waste management practices. All available media should be examined, including photos and videos which can provide valuable data and must not be disregarded. At the end of this phase, any items requiring verification or additional data are reviewed to define further investigations. Although it is not unusual at this point to carry out an additional bibliographical survey, the essential task is to carry out in situ measurements. The second phase thus consists in performing in situ measurement campaigns involving essentially components containing significant activity levels. The most routinely used methods combine the results of elementary measurements such as the dose rate or more sophisticated measurements such as gamma spectrometry using CdZnTe detectors and gamma imaging to estimate and localize the radioactivity. Each instrument provides part of the answer (location of a contamination hot spot, standard spectrum, activity). The results are combined and verified through the use of calculation codes: Mercure, Visiplan and Microshield. (authors)

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

Potential of the non-waste concept under NPP decommissioning

International Nuclear Information System (INIS)

Oussanov, V.I.; Popov, E.P.; Markelov, P.I.

2001-01-01

There are three principal ways to approaching the non-waste nuclear cycle: radical reduction of the long-lived radioactivity generation; creation of the effective reuse procedure and, at last, radioactive waste transmutation. Unlike nuclear fuel cycle, the drastic reduction of the waste arising from the design materials cycle can be reached without need to address the technologies of burning or transmutation of the long-lived radioactive nuclei. The study shows the great potential of the nuclear technology in respect of the cardinal solution of the NPP decommissioning problem and decreasing of decommissioning cost. The key issue of the solution is a radical reduction of the radioactive waste arising from the decommissioning procedure. Generalizing, one may come to conclusion that approaching the non-waste nuclear technology consists in the further developing of the nuclear power infrastructure to a self-contained system including: innovated NPPs (more safe and generating less amount of decommissioning waste), plants for reprocessing fuel and exposed design materials, storage facilities. The paper contribute to the notion that such activity is economically and ecologically expedient. (author)

Radioactive waste management plan during the TRIGA Mark II and III decommissioning

International Nuclear Information System (INIS)

Jung, K.J.; Park, S.K.; Geong, G.H.; Lee, K.W.; Chung, U.S.; Paik, S.T.

2001-01-01

The decontamination and decommissioning (D and D) project of TRIGA Mark-I and Mark-II (KRR 1 and 2) was started in January 1997 and will be completed by December 2002. In the first year of the project, work was performed in preparation of the decommissioning plan, start of the environmental impact assessment and setup licensing procedure and documentation for the project with cooperation of the Korea Institute of Nuclear Safety (KINS). In the second year, Hyundai Engineering Company (HEC) with British Nuclear Fuels pie (BNFL) as technical assisting partner was designated as the contractor to do design and licensing documentation for the D and D of both reactors. After pre-design, a hazard and operability (HAZOP) study checked each step of the work. At the end of 1998, the decommissioning plan documentation including environmental impact assessment report was finished and submitted to the Ministry of Science and Technology (MOST) for licensing. It is expected to be issued by the end of September 1999. Practical work will then be started around the end of 1999. The safe treatment and management of the radioactive waste arising from the D and D activities is of utmost importance for successful completion of the practical dismantling work. This paper summarizes general aspects of radioactive waste treatment and management plan for the TRIGA Mark-I and II decommissioning work. (author)

Impact of Fuel Failure on Criticality Safety of Used Nuclear Fuel

International Nuclear Information System (INIS)

Marshall, William J.; Wagner, John C.

2012-01-01

Commercial used nuclear fuel (UNF) in the United States is expected to remain in storage for considerably longer periods than originally intended (e.g., 45 GWd/t) may increase the potential for fuel failure during normal and accident conditions involving storage and transportation. Fuel failure, depending on the severity, can result in changes to the geometric configuration of the fuel, which has safety and regulatory implications. The likelihood and extent of fuel reconfiguration and its impact on the safety of the UNF is not well understood. The objective of this work is to assess and quantify the impact of fuel reconfiguration due to fuel failure on criticality safety of UNF in storage and transportation casks. This effort is primarily motivated by concerns related to the potential for fuel degradation during ES periods and transportation following ES. The criticality analyses consider representative UNF designs and cask systems and a range of fuel enrichments, burnups, and cooling times. The various failed-fuel configurations considered are designed to bound the anticipated effects of individual rod and general cladding failure, fuel rod deformation, loss of neutron absorber materials, degradation of canister internals, and gross assembly failure. The results quantify the potential impact on criticality safety associated with fuel reconfiguration and may be used to guide future research, design, and regulatory activities. Although it can be concluded that the criticality safety impacts of fuel reconfiguration during transportation subsequent to ES are manageable, the results indicate that certain configurations can result in a large increase in the effective neutron multiplication factor, k eff . Future work to inform decision making relative to which configurations are credible, and therefore need to be considered in a safety evaluation, is recommended.

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

2005-01-01

The procurement and preparation of fuel for nuclear power reactors, followed by its recovery, processing and management subsequent to reactor discharge, are frequently referred to as the ''front end'' and ''back end'' of the nuclear fuel cycle. The facilities associated with these activities have an extensive and well-documented safety record accumulated over the past 50 years by technical experts and safety authorities. This information has enabled an in-depth analysis of the complete fuel cycle. Preceded by two previous editions in 1981 and 1993, this new edition of the Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle. It will be of considerable interest to nuclear safety experts, but also to those wishing to acquire extensive information about the fuel cycle more generally. (author)

The safety of the nuclear fuel cycle

International Nuclear Information System (INIS)

2005-10-01

The procurement and preparation of fuel for nuclear power reactors, followed by its recovery, processing and management subsequent to reactor discharge, are frequently referred to as the 'front end' and 'back end' of the nuclear fuel cycle. The facilities associated with these activities have an extensive and well-documented safety record accumulated over the past 50 years by technical experts and safety authorities. This information has enabled an in-depth analysis of the complete fuel cycle. Preceded by two previous editions in 1981 and 1993, this new edition of The Safety of the Nuclear Fuel Cycle represents the most up-to-date analysis of the safety aspects of the nuclear fuel cycle. It will be of considerable interest to nuclear safety experts, but also to those wishing to acquire extensive information about the fuel cycle more generally. (author)

SOGIN Decommissioning strategy and funding (Italy)

International Nuclear Information System (INIS)

2006-01-01

Statement: In Italy, as it is well known, there are no more operational NPPs. The four existing nuclear plants are definitely shutdown and ready for decommissioning. Considerations on decommissioning funding system have to take into account this particular situation. Strategy for decommissioning: New inputs given to SOGIN by the Italian Government are: conditioning all radioactive waste existing on the NPPs within the year 2010, release all nuclear sites - free of radiological constraints - by 2020. The last task is conditioned by availability of the national waste repository by the year 2009. Strategy for decommissioning: Key issue is prompt dismantling considering No more nuclear activities in Italy and Progressive loss of competencies. Previously Existing funds: Before plant shutdown, ENEL has cumulated provisions for decommissioning, even in absence of a clear regulatory framework. These provisions were not sufficient for decommissioning, considering the early closure of the plants. An additional fund was granted to ENEL by the government, in the form of a 'credit' to be paid by the 'electric system' (CCSE). This fund (provisions + credit) was considered sufficient by ENEL for a decommissioning with Safe Store strategy (fund = discounted foreseen costs). The total fund (provisions + credit) was assigned to Sogin at the incorporation date. The amount, money 1999, was about 800 M euros. Considering the new context: new strategy (Prompt Dismantling with site release by 2020), Sogin constitution (societal costs), new economic conditions. The fund was not considered sufficient for all Sogin tasks. This conclusion was agreed upon also by the independent 'Authority for electric energy and gas'. A new regulatory framework was therefore defined. Regulatory aspects: The Legislative Decree 79/99 has stated that costs for the decommissioning of NPP, fuel cycle back end and related activities should be considered as stranded costs for the general electric system. The same

The spent fuel safety experiment

International Nuclear Information System (INIS)

Harmms, G.A.; Davis, F.J.; Ford, J.T.

1995-01-01

The Department of Energy is conducting an ongoing investigation of the consequences of taking fuel burnup into account in the design of spent fuel transportation packages. A series of experiments, collectively called the Spent Fuel Safety Experiment (SFSX), has been devised to provide integral benchmarks for testing computer-generated predictions of spent fuel behavior. A set of experiments is planned in which sections of unirradiated fuel rods are interchanged with similar sections of spent PWR fuel rods in a critical assembly. By determining the critical size of the arrays, one can obtain benchmark data for comparison with criticality safety calculations. The integral reactivity worth of the spent fuel can be assessed by comparing the measured delayed critical fuel loading with and without spent fuel. An analytical effort to model the experiments and anticipate the core loadings required to yield the delayed critical conditions runs in parallel with the experimental effort

Planning for the decommissioning of a research reactor

International Nuclear Information System (INIS)

Dodson, W.J.; Isakari, H.H.; Munro, J.F.; Lim, T.H.; Denton, M.M.; Vernig, P.G.

1988-01-01

This paper describes the steps that must be taken and the uncertainties and potential pitfalls that can be encountered in decommissioning a research reactor, whether owned by private industry, a university, or a government agency. The paper is based on the experience in preparing for decommissioning the TRIGA Mark III Berkeley Research Reactor (BRR). Six topics of interest to an owner-operator are addressed: task and schedule planning, decommissioning organization, cost estimating, health and safety considerations, waste management, and regulatory concerns

Mechanical properties of fuel debris for defueling toward decommissioning

International Nuclear Information System (INIS)

Hoshino, Takanori; Kitagaki, Toru; Yano, Kimihiko; Okamura, Nobuo; Koizumi, Kenji; Ohara, Hiroshi; Fukasawa, Tetsuo

2015-01-01

In the decommissioning of the Fukushima Daiichi Nuclear Power Plant (1F), safe and steady defueling work is required. Before defueling 1F, it is necessary to evaluate fuel debris for properties related to the defueling procedure and technology. While defueling after the Three Mile Island Nuclear Power Plant Unit 2 (TMI-2) accident, a core boring system played an important role. Considering the working principle of core boring, hardness, elastic modulus, and fracture toughness were found to be important fuel debris properties that had a profound effect on the performance of the boring machine. It is speculated that uranium and zirconium oxide solid solution ((U,Zr)O_2) is one of the major materials of fuel debris in 1F, according to the TMI-2 accident experience and the results of past severe accident studies. In addition, the Zr content of 1F fuel debris is expected to be higher than that of TMI-2 debris, because the 1F reactors were boiling-water reactor (BWR). In this report, the mechanical properties of (U,Zr)O_2 are evaluated in the ZrO_2 content range from 10% to 65%. The hardness, elastic modulus, and fracture toughness were measured by Vickers test, ultrasonic pulse echo method, and indentation fracture method, respectively. In the ZrO_2 content range under 50%, the Vickers hardness and fracture toughness of (U,Zr)O_2 increased, and the elastic modulus decreased slightly with ZrO_2 content. In the case of 55% and 65% ZrO_2, all of those measures increased slightly with ZrO_2 content. Summarizing those results, ZrO_2 content affects mechanical properties significantly in the case of low ZrO_2 content. Higher Zr content (exceeding 50%) has little effect on mechanical properties. In the future, nonradioactive surrogate debris will be necessary for small-scale functional and large-scale mockup tests of various defueling technologies. These results are useful to select the material for surrogate debris. (author)

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

Safety issues on advanced fuel

International Nuclear Information System (INIS)

Gross, H.; Krebs, W.D.

1998-01-01

In the recent years a general discussion has started whether unsolved safety issues are related to advanced fuel. Advanced fuel is in this context a summary of features like high burnup, improved clad materials, low leakage loading pattern with high peaking factors etc. The design basis accidents RIA and Loca are of special interest for this discussion. From the Siemens point of view RIA is not a safety issue. There are sufficient margins between the enthalpy rise calculated by modern 3D methods and the fuel failures which occurred in RIA simulation tests when the effect of pulse width is taken into account. The evaluation of possible uncertainties for the established Loca criteria (17% equivalent corrosion, 1200 C clad temperature) for high burnup makes sense. But fuel with high burnup has significantly lower peaking factors than fuel with lower burnup. This gives sufficient margin counterbalancing possible uncertainties. In contrast to the above incomplete control rod insertion at higher burnup is potentially a real safety issue. Although Siemens fuel was not affected by the reported incidents they addressed the problem and checked that they have sufficient design margin for their fuel. (orig.) [de

Lessons learned from the shut down, planning, and the preparatory activities of decommissioning the research reactor VVR-S Magurele, Bucharest

International Nuclear Information System (INIS)

Dragusin, M.; Copaciu, V.

2006-01-01

The nuclear research reactor type VVR was shut down in December 1997 after forty years of operation. The main characteristics of this reactor are: Thermal power 2 MW, Thermal energy - 9.59 GWhd, Average flux of thermal neutrons-10 13 n/cm 2 .s, nine horizontal channels, sixteen vertical exposure channels, three biological channels, reactor type tank, water used as a moderator, coolant and reflector. The reactor was used in research and radioisotope production. The reactor has been permanently shut down since April 2002, when the decommissioning was officially announced. Discussions regarding funding mechanisms for the conservation phase, and decommissioning (planning, preparatory activities, spent nuclear fuel management), have taken place since five years ago when the final decision of permanent shut down was taken. Quality management includes procedures for recording and archiving the lessons learned. The planning of decommissioning started in 1990 when the reactor was still operational. After fifteen years the regulatory body has not yet approved the decommissioning plan for the reactor. In this paper the following aspects are discussed: decommissioning strategy from safe enclosure to immediate dismantling, specific features of the site (treatment of radioactive waste near reactor) and state of decommissioning, use of the lessons learned in the planning of decommissioning for the other two small nuclear facilities situated in the same area with VVR-reactor: Sub critical Assembly 'HELEN' and Zero Power Critical Reactor RP-0, AFR ponds for spent nuclear fuel, other radiological facilities for radioisotopes production facilities radiation processing and accelerators. Preparatory activities for decommissioning have included: elaboration of a plan (inter alia, justification of the selected strategy, management of the radioactive waste in accordance with the waste acceptance criteria), reactor storage in parallel with the removal of the equipment and materials used in

76 FR 35511 - Decommissioning Planning

Science.gov (United States)

2011-06-17

... licensees to conduct their operations to minimize the introduction of residual radioactivity into the site... account and line of credit as approved financial assurance mechanisms, and modify other financial... additional information on the costs of decommissioning and spent fuel management. DATES: The final rule is...

DECOST: computer routine for decommissioning cost and funding analysis

International Nuclear Information System (INIS)

Mingst, B.C.

1979-12-01

One of the major controversies surrounding the decommissioning of nuclear facilities is the lack of financial information on just what the eventual costs will be. The Nuclear Regulatory Commission has studies underway to analyze the costs of decommissioning of nuclear fuel cycle facilities and some other similar studies have also been done by other groups. These studies all deal only with the final cost outlays needed to finance decommissioning in an unchangeable set of circumstances. Funding methods and planning to reduce the costs and financial risks are usually not attempted. The DECOST program package is intended to fill this void and allow wide-ranging study of the various options available when planning for the decommissioning of nuclear facilities

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

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2004-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Review and assessment of nuclear facilities by the regulatory body. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The purpose of this Safety Guide is to provide recommendations for regulatory bodies on reviewing and assessing the various safety related submissions made by the operator of a nuclear facility at different stages (siting, design, construction, commissioning, operation and decommissioning or closure) in the facility's lifetime to determine whether the facility complies with the applicable safety objectives and requirements. This Safety Guide covers the review and assessment of submissions in relation to the safety of nuclear facilities such as: enrichment and fuel manufacturing plants. Nuclear power plants. Other reactors such as research reactors and critical assemblies. Spent fuel reprocessing plants. And facilities for radioactive waste management, such as treatment, storage and disposal facilities. This Safety Guide also covers issues relating to the decommissioning of nuclear facilities, the closure of waste disposal facilities and site rehabilitation. Objectives, management, planning and organizational matters relating to the review and assessment process are presented in Section 2. Section 3 deals with the bases for decision making and conduct of the review and assessment process. Section 4 covers aspects relating to the assessment of this process. The Appendix provides a generic list of topics to be covered in the review and assessment process

Operation of spent fuel storage facilities

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide was prepared as part of the IAEA's programme on safety of spent fuel storage. This is for interim spent fuel storage facilities that are not integral part of an operating nuclear power plant. Following the introduction, Section 2 describes key activities in the operation of spent fuel storage facilities. Section 3 lists the basic safety considerations for storage facility operation, the fundamental safety objectives being subcriticality, heat removal and radiation protection. Recommendations for organizing the management of a facility are contained in Section 4. Section 5 deals with aspects of training and qualification; Section 6 describes the phases of the commissioning of a spent fuel storage facility. Section 7 describes operational limits and conditions, while Section 8 deals with operating procedures and instructions. Section 9 deals with maintenance, testing, examination and inspection. Section 10 presents recommendations for radiation and environmental protection. Recommendations for the quality assurance (QA) system are presented in Section 11. Section 12 describes the aspects of safeguards and physical protection to be taken into account during operations; Section 13 gives guidance for decommissioning. 15 refs, 5 tabs

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.

International Conference of Ukrainian Nuclear Society ''NPP's safety and protection''(annotations)

International Nuclear Information System (INIS)

Barbashev, S.V.

1997-01-01

The abstracts of reports submitted to the Conference include: - New developments of the safe nuclear installations; - NPP ecological safety; - Methods of personnel and population protection; - Waste management safety (at transportation, processing and storage); - Spent nuclear fuel management; - NPP life extension and decommissioning; - Public opinion as an element of NPP safety; - Training of personnel, scientific support and safety culture; - Forecasting of nuclear power and industry safe development; - Development of international cooperation in nuclear power

Proceedings of fuel safety research specialists' meeting

International Nuclear Information System (INIS)

Suzuki, Motoe

2002-08-01

Fuel Safety Research Specialists' Meeting, which was organized by Japan Atomic Energy Research Institute, was held on March 4-5, 2002 at JAERI in Tokai Establishment. Purposes of the Meeting are to exchange information and views on LWR fuel safety topics among the specialist participants from domestic and foreign organizations, and to discuss the recent and future fuel research activities in JAERI. In the Meeting, presentations were given and discussions were made on general report of fuel safety research activities, fuel behaviors in normal operation and accident conditions, FP release behaviors in severe accident conditions, and JAERI's ''Advanced LWR Fuel Performance and Safety Research Program''. A poster exhibition was also carried out. The Meeting significantly contributed to planning future program and cooperation in fuel research. This proceeding integrates all the pictures and papers presented in the Meeting. The 10 of the presented papers are indexed individually. (J.P.N.)

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

Sellafield Decommissioning Programme - Update and Lessons Learned

International Nuclear Information System (INIS)

Lutwyche, P. R.; Challinor, S. F.

2003-01-01

The Sellafield site in North West England has over 240 active facilities covering the full nuclear cycle from fuel manufacture through generation, reprocessing and waste treatment. The Sellafield decommissioning programme was formally initiated in the mid 1980s though several plants had been decommissioned prior to this primarily to create space for other plants. Since the initiation of the programme 7 plants have been completely decommissioned, significant progress has been made in a further 16 and a total of 56 major project phases have been completed. This programme update will explain the decommissioning arrangements and strategies and illustrate the progress made on a number of the plants including the Windscale Pile Chimneys, the first reprocessing plan and plutonium plants. These present a range of different challenges and requiring approaches from fully hands on to fully remote. Some of the key lessons learned will be highlighted

Radiation protection aspects in decommissioning of a fuel reprocessing plant

International Nuclear Information System (INIS)

Kotrappa, P.; Joshi, P.P.; Theyyunni, T.K.; Sidhwa, B.M.; Nadkarni, M.N.

1980-01-01

The decontamination of a fuel reprocessing plant which underwent partial decommissioning is described. The following radiation protection aspects of the work are discussed: dismantling and removal of process vessels, columns and process off-gas filters; decontamination of various process areas; and management of liquid and solid wastes. The work was completed safely by using personnel protective equipment such as plastic suits and respirators (gas, particulate and fresh air). Total dose commitment for this work was around 3000 man-rems, including dose received by staff for certain jobs related to the operation of a section of the plant. The external dose was kept below the annual limit of 5000 mrems for any individual. No internal contamination incident occurred which caused a dose commitment in excess of 10% of the annual limit. The fact that all the work was completed by the staff normally associated with the operation of the plant contributed significantly to the management and control of personnel exposures. (H.K.)

Analysis of high burnup fuel safety issues

Energy Technology Data Exchange (ETDEWEB)

Lee, Chan Bock; Kim, D. H.; Bang, J. G.; Kim, Y. M.; Yang, Y. S.; Jung, Y. H.; Jeong, Y. H.; Nam, C.; Baik, J. H.; Song, K. W.; Kim, K. S

2000-12-01

Safety issues in steady state and transient behavior of high burnup LWR fuel above 50 - 60 MWD/kgU were analyzed. Effects of burnup extension upon fuel performance parameters was reviewed, and validity of both the fuel safety criteria and the performance analysis models which were based upon the lower burnup fuel test results was analyzed. It was found that further tests would be necessary in such areas as fuel failure and dispersion for RIA, and high temperature cladding corrosion and mechanical deformation for LOCA. Since domestic fuels have been irradiated in PWR up to burnup higher than 55 MWD/kgU-rod. avg., it can be said that Korea is in the same situation as the other countries in the high burnup fuel safety issues. Therefore, necessary research areas to be performed in Korea were derived. Considering that post-irradiation examination(PIE) for the domestic fuel of burnup higher than 30 MWD/kgU has not been done so far at all, it is primarily necessary to perform PIE for high burnup fuel, and then simulation tests for RIA and LOCA could be performed by using high burnup fuel specimens. For the areas which can not be performed in Korea, international cooperation will be helpful to obtain the test results. With those data base, safety of high burnup domestic fuels will be confirmed, current fuel safety criteria will be re-evaluated, and finally transient high burnup fuel behavior analysis technology will be developed through the fuel performance analysis code development.

Analysis of high burnup fuel safety issues

International Nuclear Information System (INIS)

Lee, Chan Bock; Kim, D. H.; Bang, J. G.; Kim, Y. M.; Yang, Y. S.; Jung, Y. H.; Jeong, Y. H.; Nam, C.; Baik, J. H.; Song, K. W.; Kim, K. S

2000-12-01

Safety issues in steady state and transient behavior of high burnup LWR fuel above 50 - 60 MWD/kgU were analyzed. Effects of burnup extension upon fuel performance parameters was reviewed, and validity of both the fuel safety criteria and the performance analysis models which were based upon the lower burnup fuel test results was analyzed. It was found that further tests would be necessary in such areas as fuel failure and dispersion for RIA, and high temperature cladding corrosion and mechanical deformation for LOCA. Since domestic fuels have been irradiated in PWR up to burnup higher than 55 MWD/kgU-rod. avg., it can be said that Korea is in the same situation as the other countries in the high burnup fuel safety issues. Therefore, necessary research areas to be performed in Korea were derived. Considering that post-irradiation examination(PIE) for the domestic fuel of burnup higher than 30 MWD/kgU has not been done so far at all, it is primarily necessary to perform PIE for high burnup fuel, and then simulation tests for RIA and LOCA could be performed by using high burnup fuel specimens. For the areas which can not be performed in Korea, international cooperation will be helpful to obtain the test results. With those data base, safety of high burnup domestic fuels will be confirmed, current fuel safety criteria will be re-evaluated, and finally transient high burnup fuel behavior analysis technology will be developed through the fuel performance analysis code development

Fuel cycle and waste newsletter, Vol. 3, No. 3, December 2007

International Nuclear Information System (INIS)

2007-12-01

This issue of the Fuel Cycle and Waste Newsletter reports on the IAEA's International Conference on Research Reactors which focused on sharing the latest scientific, technical and safety information related to research reactors including projects on design, construction and commissioning of new research facilities. This issue further covers reports of some of the activities performed by the Division of Nuclear Fuel Cycle and Waste Technology including information on upgrading radioactive waste management facilities, aqueous homogeneous reactors for isotope production, activities of the contact experts group in 2007, current activities related to HEU minimization, repatriation of radioactive sources in Nigeria, the 2007 TWGNFCO (Nuclear Fuel Cycle Options and Spent Fuel Management) meeting, the stakeholder involvement in decommissioning (draft technical report in preparation), initial activities of the International Decommissioning Network (IDN), spent fuel publications, the thorium fuel cycle, the Nuclear Fuel Cycle Simulation System (NFCSS). Finally, it presents a bibliography of recent publications of IAEA's Division of Nuclear Fuel Cycle and Waste Technology as well as a list of Meetings in 2008

Safety research activities on radioactive waste management in JNES

International Nuclear Information System (INIS)

Otsuka, Ichiro; Aoki, Hiroomi; Suko, Takeshi; Onishi, Yuko; Masuda, Yusuke; Kato, Masami

2010-01-01

Research activities in safety regulation of radioactive waste management are presented. Major activities are as follows. As for the geological disposal, major research areas are, developing 'safety indicators' to judge the adequacy of site investigation results presented by an implementer (NUMO), compiling basic requirements of safety design and safety assessment needed to make a safety review of the license application and developing an independent safety assessment methodology. In proceeding research, JNES, Japan Atomic Energy Agency (JAEA) and the National Institute of Advanced Industrial Science and Technology (AIST) signed an agreement of cooperative study on geological disposal in 2007. One of the ongoing joint studies under this agreement has been aimed at investigating regional-scale hydrogeological modeling using JAEA's Horonobe Underground Research Center. In the intermediate depth disposal, JNES conducted example analysis of reference facility and submitted the result to Nuclear Safety Commission of Japan (NSC). JNES is also listing issues to be addressed in the safety review of the license application and tries to make criteria of the review. Furthermore, JNES is developing analysis tool to evaluate long term safety of the facility and conducting an experiment to investigate long term behavior of engineered barrier system. In the near surface disposal of waste package, it must be confirmed by a regulatory inspector whether each package meets safety requirements. JNES continuously updates the confirmation methodology depending on new processing technologies. The clearance system was established in 2005. Two stages of regulatory involvement were adapted, 1) approval for measurement and judgment methods developed by the nuclear operator and 2) confirmation of measurement and judgment results based on approved methods. JNES is developing verification methodology for each stage. As for decommissioning, based on the regulatory needs and a research program

Nuclear safety. Volume 36, Number 2, July--December 1995

Energy Technology Data Exchange (ETDEWEB)

None

1995-12-01

The primary scope of the journal is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. The following subjects are covered here: (1) the Chernobyl accident; (2) general safety considerations; (3) accident analysis; (4) design features; (5) environmental effects; (6) operating experiences; (7) US NRC information and analyses; and (8) recent developments. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

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)

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)

Summary of fuel safety research meeting 2004

International Nuclear Information System (INIS)

Fuketa, Toyoshi; Hidaka, Akihide; Nakamura, Jinichi; Suzuki, Motoe; Nagase, Fumihisa; Sasajima, Hideo; Fujita, Misao; Otomo, Takashi; Kudo, Tamotsu; Amaya, Masaki; Sugiyama, Tomoyuki; Ikehata, Hisashi; Iwasaki, Ryo; Ozawa, Masaaki; Kida, Mitsuko

2004-10-01

Fuel Safety Research Meeting 2004, which was organized by the Japan Atomic Energy Research Institute, was held on March 1-2, 2004 at Toranomon Pastoral, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meeting covered the status of fuel safety research activities, fuel behavior under RIA and LOCA conditions, high burnup fuel behavior, and radionuclides release under severe accident conditions. This summary contains all the abstracts and OHP sheets presented in the meeting. (author)

Risk Assessment Strategy for Decommissioning of Fukushima Daiichi Nuclear Power Station

Directory of Open Access Journals (Sweden)

Akira Yamaguchi

2017-03-01

Full Text Available Risk management of the Fukushima Daiichi Nuclear Power Station decommissioning is a great challenge. In the present study, a risk management framework has been developed for the decommissioning work. It is applied to fuel assembly retrieval from Unit 3 spent fuel pool. Whole retrieval work is divided into three phases: preparation, retrieval, and transportation and storage. First of all, the end point has been established and the success path has been developed. Then, possible threats, which are internal/external and technical/societal/management, are identified and selected. “What can go wrong?” is a question about the failure scenario. The likelihoods and consequences for each scenario are roughly estimated. The whole decommissioning project will continue for several decades, i.e., long-term perspective is important. What should be emphasized is that we do not always have enough knowledge and experience of this kind. It is expected that the decommissioning can make steady and good progress in support of the proposed risk management framework. Thus, risk assessment and management are required, and the process needs to be updated in accordance with the most recent information and knowledge on the decommissioning works.

Risk assessment strategy for decommissioning of Fukushima Daiichi Nuclear Power Station

Energy Technology Data Exchange (ETDEWEB)

Yamaguchi, Akira; Jang, Sung Hoon [The University of Tokyo, Tokyo (Japan); Hida, Kazuki [Nuclear Damage Compensation and Decommissioning Facilitation Corporation, Tokyo (Japan); Yamanaka, Yasunori [Tokyo Electric Power Company Holdings, Tokyo (Japan); Narumiya, Yoshiyuki [The Kansai Electric Power Co., Inc., Osaka (Japan)

2017-03-15

Risk management of the Fukushima Daiichi Nuclear Power Station decommissioning is a great challenge. In the present study, a risk management framework has been developed for the decommissioning work. It is applied to fuel assembly retrieval from Unit 3 spent fuel pool. Whole retrieval work is divided into three phases: preparation, retrieval, and transportation and storage. First of all, the end point has been established and the success path has been developed. Then, possible threats, which are internal/external and technical/societal/management, are identified and selected. “What can go wrong?” is a question about the failure scenario. The likelihoods and consequences for each scenario are roughly estimated. The whole decommissioning project will continue for several decades, i.e., long-term perspective is important. What should be emphasized is that we do not always have enough knowledge and experience of this kind. It is expected that the decommissioning can make steady and good progress in support of the proposed risk management framework. Thus, risk assessment and management are required, and the process needs to be updated in accordance with the most recent information and knowledge on the decommissioning works.

SGHWR fuel performance, safety and reliability

International Nuclear Information System (INIS)

Pickman, D.O.; Inglis, G.H.

1977-05-01

The design principles involved in fuel pins and elements need to take account of the sometimes conflicting requirements of safety and reliability. The principal factors involved in this optimisation are discussed and it is shown from fuel irradiation experience in the Winfrith SGHWR that the necessary bias towards safety has not resulted in a reliability level lower than that shown by other successful water reactor designs. Reliability has important economic implications. By a detailed evaluation of SGHWR fuel defects it is shown that very few defects can be shown to be related to design, rating, or burn-up. This demonstrates that economic aspects have not over-ridden necessary criteria that most be met to achieve the desirable reliability level. It is possible that large scale experience on SGHWR fuel may eventually demonstrate that the balance is too much in favour of reliability and consideration may be given to whether design changes favouring economy could be achieved without compromising safety. The safety criteria applied to SGHWR fuel are designed to avoid any possibility of a temperature runaway in any credible accident situation. the philosophy and supporting experimental work programme are outlines and the fuel design features which particularly contribute to maximising safety margins are outlined. Reference is made to the new 60-pin fuel element to be used in the commercial SGHWRs and to its comparison in design and performance aspects with the 36-pin element that has been used to date in the Winfrith SGHWR. (author)

Decommissioning in the United States - Past, present and future - 16318

International Nuclear Information System (INIS)

Devgun, Jas S.

2009-01-01

The experience related to decommissioning of nuclear facilities in the United States is very substantial and covers power reactors, research reactors, and many facilities in the Department of Energy complex. The focus of this paper however is on the commercial power plants. With 104 operating reactors, the U.S. fleet of civilian reactors is still the largest in the world. Nuclear power industry in the United States has undergone a dramatic upturn after decades of stalemate. One effect of this nuclear renaissance has been that the plans have changed for several reactors that were initially destined for decommissioning. Instead, the focus now is on re-licensing of the reactors and on power up-rates. In fact, after the peak period between 1987 and 1998, no additional power reactors have been shutdown. On the contrary, power up-rates in the past twenty years have added a cumulative capacity equivalent to five new reactors. Almost all the operating reactors plan to have license extensions, thus postponing the eventual decommissioning. Nevertheless, in addition to the 9 reactors where licenses have been terminated following decommissioning, 12 power and early demonstration reactors and 14 test and research reactors are permanently shutdown and are in decommissioning phase. Substantial experience and lessons learned are available from the U.S. projects that are of value to the international decommissioning projects, especially where such projects are in early stages. These lessons cover a wide array of areas from decommissioning plans, technology applications, large component removal, regulatory and public interface, decommissioning funding and costs, clean up criteria, surveys of the decommissioned site, and license termination. Additionally, because of the unavailability of a national spent fuel disposition facility, most decommissioning sites are constructing above ground interim storage facilities for the spent nuclear fuel. The U.S. nuclear power projects are also

Safety control and minimization of radioactive wastes

International Nuclear Information System (INIS)

Wang Jinming; Rong Feng; Li Jinyan; Wang Xin

2010-01-01

Compared with the developed countries, the safety control and minimization of the radwastes in China are under-developed. The research of measures for the safety control and minimization of the radwastes is very important for the safety control of the radwastes, and the reduction of the treatment and disposal cost and environment radiation hazards. This paper has systematically discussed the safety control and the minimization of the radwastes produced in the nuclear fuel circulation, nuclear technology applications and the process of decommission of nuclear facilities, and has provided some measures and methods for the safety control and minimization of the radwastes. (authors)

Decommissioning of the radio chemical hot laboratory of the european commission joint research centre of Ispra - 59207

International Nuclear Information System (INIS)

Ugolini, Daniele; Rossi, Francesco; Basile, Francesco

2012-01-01

The construction of the Radio Chemical Hot Laboratory (RCHL) of the Joint Research Centre (JRC) of Ispra began in the early 1960's while the laboratory activities started in 1964. In 1976 an annex to the main building was built. At this time the RCHL main research activities were in environment and biochemistry by means of radioactive tracers; neutron activation analyses; extraction of actinides from radioactive liquid waste coming from the nuclear fuel reprocessing plants; and analyses of U, Pu, and Th in samples from the nuclear fuel cycle in order to determine the isotopic ratio and the burn-up. In 1978, a new area of laboratories named 'Stabularium' was built to study the metabolism of heavy metal on laboratory animals. Complementary to the laboratory three pneumatic transfer systems for irradiated sources connected the RCHL to two research reactors. The decommissioning activities of the 2650 m 2 facility started in January 2008 and they were completed at the end of 2010 with the release for unrestricted use of all the buildings of the facility. They consisted in five main tasks: pre-decommissioning, licensing, dismantling, waste management, and final survey. The main pre-decommissioning activities were the physical and radiological characterization of the facility. The principal licensing activity was the preparation of the de-licensing documentation to obtain the license termination from the safety authorities. Dismantling consisted in the removal of all the equipments and ancillary systems, of the pneumatic transfer system, and in the decontamination of the structures of the controlled zone. The waste management was limited to the transfer of the waste and of the clearable material to the centralized waste management facility. The final survey consisted in the final radiological characterization to quantify the concentration of any residual radioactivity remained after the completion of the dismantling activities for the release of the RCHL without any

Consequences of Fuel Failure on Criticality Safety of Used Nuclear Fuel

International Nuclear Information System (INIS)

Marshall, William J.; Wagner, John C.

2012-09-01

This report documents work performed for the Department of Energy's Office of Nuclear Energy (DOENE) Fuel Cycle Technologies Used Fuel Disposition Campaign to assess the impact of fuel reconfiguration due to fuel failure on the criticality safety of used nuclear fuel (UNF) in storage and transportation casks. This work was motivated by concerns related to the potential for fuel degradation during extended storage (ES) periods and transportation following ES, but has relevance to other potential causes of fuel reconfiguration. Commercial UNF in the United States is expected to remain in storage for longer periods than originally intended. Extended storage time and irradiation of nuclear fuel to high-burnup values (>45 GWd/t) may increase the potential for fuel failure during normal and accident conditions involving storage and transportation. Fuel failure, depending on the severity, can result in changes to the geometric configuration of the fuel, which has safety and regulatory implications for virtually all aspects of a UNF storage and transport system's performance. The potential impact of fuel reconfiguration on the safety of UNF in storage and transportation is dependent on the likelihood and extent of the fuel reconfiguration, which is not well understood and is currently an active area of research. The objective of this work is to assess and quantify the impact of postulated failed fuel configurations on the criticality safety of UNF in storage and transportation casks. Although this work is motivated by the potential for fuel degradation during ES periods and transportation following ES, it has relevance to fuel reconfiguration due to the effects of high burnup. Regardless of the ultimate disposition path, UNF will need to be transported at some point in the future. To investigate and quantify the impact of fuel reconfiguration on criticality safety limits, which are given in terms of the effective neutron multiplication factor, a set of failed fuel

Accelerating the Whiteshell Laboratories Decommissioning Through the Implementation of a Projectized and Delivery-Focused Organization - 13074

Energy Technology Data Exchange (ETDEWEB)

Wilcox, Brian; Mellor, Russ; Michaluk, Craig [Atomic Energy of Canada Limited, Whiteshell Laboratories, Pinawa, Manitoba (Canada)

2013-07-01

Whiteshell Laboratories (WL) is a nuclear research site in Canada that was commissioned in 1964 by Atomic Energy of Canada Limited. It covers a total area of approximately 4,375 hectares (10,800 acres) and includes the main campus site, the Waste Management Area (WMA) and outer areas of land identified as not used for or impacted by nuclear development or operations. The WL site employed up to 1100 staff. Site activities included the successful operation of a 60 MW organic liquid-cooled research reactor from 1965 to 1985, and various research programs including reactor safety research, small reactor development, fuel development, biophysics and radiation applications, as well as work under the Canadian Nuclear Fuel Waste Management Program. In 1997, AECL made a business decision to discontinue research programs and operations at WL, and obtained government concurrence in 1998. The Nuclear Legacy Liabilities Program (NLLP) was established in 2006 by the Canadian Government to remediate nuclear legacy liabilities in a safe and cost effective manner, including the WL site. The NLLP is being implemented by AECL under the governance of a Natural Resources Canada (NRCan)/AECL Joint Oversight Committee (JOC). Significant progress has since been made, and the WL site currently holds the only Canadian Nuclear Safety Commission (CNSC) nuclear research site decommissioning license in Canada. The current decommissioning license is in place until the end of 2018. The present schedule planned for main campus decommissioning is 30 years (to 2037), followed by institutional control of the WMA until a National plan is implemented for the long-term management of nuclear waste. There is an impetus to advance work and complete decommissioning sooner. To accomplish this, AECL has added significant resources, reorganized and moved to a projectized environment. This presentation outlines changes made to the organization, the tools implemented to foster projectization, and the benefits

Sweden's second national report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

International Nuclear Information System (INIS)

2005-01-01

plant units at the Oskarshamn site. These events create new challenges for the safety work of the licensees as well as for the regulatory bodies. However, the generally positive impression reported to the first review meeting under the Convention still stands. Therefore, Sweden would like to point out the following as strong features in its national nuclear practice: - The responsibility for safety is clearly defined in the Swedish legal framework. In order not to dilute the responsibility of the licence holders, the Swedish regulations are designed to define requirements to be achieved, not the detailed means to achieve them. Within the framework given by the regulations, the licence holders have to define their own solutions, and demonstrate the safety level achieved to the regulatory bodies. - The legislation clearly defines that all licence holders are responsible for the safe handling and disposal of spent fuel and radioactive waste, as well as for the decommissioning and dismantling of facilities. - The operators of nuclear power plants must jointly carry out the research and development activities needed to ensure the safe handling and disposal of spent fuel and radioactive waste, as well as for the decommissioning of facilities. The RandD programme is presented to the Government regularly and is subject to regulatory review. - The operators of nuclear power plants must pay fees to the Nuclear Waste Fund, which is subject to regulatory supervision, to ensure that resources are available for the handling and disposal of spent fuel and radioactive waste, and for the decommissioning and dismantling of the facilities. - There is an open and generally constructive relationship between the regulatory bodies and the licence holders. Even though comprehensive and very active programmes for the management of spent fuel and radioactive waste have been established, many challenges remain. Over the next 10-20 years several new facilities will be sited, constructed and taken

Decommissioning of the Neuherberg Research Reactor (FRN)

International Nuclear Information System (INIS)

Demmeler, M.; Rau, G.; Strube, D.

1982-01-01

The Neuherberg Research Reactor is of type TRIGA MARK III with 1 MW steady state power and pulsable up to 2000 MW. During more than ten years of operation 12000 MWh and 6000 reactor pulses had been performed. In spite of its good technical condition and of permanent safe operation without any failures, the decommissioning of the Neuherberg research reactor was decided by the GSF board of directors to save costs for maintaining and personnel. As the mode of decommissioning the safe enclosure was chosen which means that the fuel elements will be transferred back to the USA. All other radioactive reactor components will be enclosed in the reactor block. Procedures for licensing of the decommissioning, dismantling procedures and time tables are presented

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.)

Decommissioning and demolition 1992

International Nuclear Information System (INIS)

Whyte, I.L.

1992-01-01

The decommissioning and demolition of structures offshore, onshore and in nuclear works involves new technologies and industries in demolition and removal. The aim of the conference was to provide a forum to keep up to date with technological developments, to publicise new techniques and to share and discuss present and future plans. A particular feature was the multi-disciplinary approach to promote and encourage communication between different sectors of this difficult field of operations. The conference emphasised not only technical issues but also legislative, management and health and safety aspects. Papers were presented by practising engineers, contractors and research workers involved in offshore structures, buildings, power stations, contaminated sites, nuclear plant and includes specialist techniques of cutting, lifting, explosives, ground treatment and decontamination. Many valuable case histories and records based on practical experience were reported. The volume provides a reference source on the state-of-the-art in decommissioning and demolition. The ten papers relevant to the decommissioning and demolition of nuclear facilities are indexed separately. (Author)

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)

Decommissioning of the pool reactor Thetis in Ghent, Belgium

Energy Technology Data Exchange (ETDEWEB)

Cortenbosch, Geert; Mommaert, Chantal [Bel V, Brussels (Belgium); Tierens, Hubert; Monsieurs, Myriam; Meierlaen, Isabelle; Strijckmans, Karel [Ghent Univ. (Belgium)

2016-11-15

The Thetis research pool reactor (with a nominal power of 150 kW) of the Ghent University was operational from 1967 till December 2003. The first phase of the decommissioning of the reactor, the removal of the spent fuel from the site, took place in 2010. The cumulative dose received was only 404 man . μSv. During the second phase, the transition period between the removal of the spent fuel in 2010 and the start of the decommissioning phase in March 2013, 3-monthly internal inspections and inspections by Bel V, were performed. The third and final decommissioning phase started on March 18, 2013. The total dose received between March 2013 and August 2013 was 1561 man . μSv. The declassification from a Class I installation to a Class II installation was possible by the end of 2015. The activated concrete in the reactor pool will remain under regulatory control until the activation levels are lower than the limits for free release.

Design of spent fuel storage facilities

International Nuclear Information System (INIS)

1994-01-01

This Safety Guide is for interim spent fuel storage facilities that are not integral part of an operating nuclear power plant. Following the introduction, Section 2 describes the general safety requirements applicable to the design of both wet and dry spent fuel storage facilities; Section 3 deals with the design requirements specific to either wet or dry storage. Recommendations for the auxiliary systems of any storage facility are contained in Section 4; these are necessary to ensure the safety of the system and its safe operation. Section 5 provides recommendations for establishing the quality assurance system for a storage facility. Section 6 discusses the requirements for inspection and maintenance that must be considered during the design. Finally, Section 7 provides guidance on design features to be considered to facilitate eventual decommissioning. 18 refs

AECL's waste management and decommissioning program

International Nuclear Information System (INIS)

Kupferschmidt, W.C.H.

2006-01-01

Full text: Canada has developed significant expertise in radioactive waste management since the mid 1940s, when the Canadian nuclear program commenced activities at Chalk River Laboratories (CRL). Atomic Energy of Canada Limited (AECL), created as a Federal Crown Corporation in 1952, continues to manage wastes from these early days, as well as other radioactive wastes produced by Canadian hospitals, universities, industry, and operational wastes from AECL's current programs. AECL is also carrying out decommissioning of nuclear facilities and installations in Canada, predominantly at its own sites in Ontario (CRL, and the Douglas Point and Nuclear Power Demonstration prototype reactors), Manitoba (Whiteshell Laboratories) and Quebec (Gentilly-1 prototype reactor). At the CRL site, several major waste management enabling facilities are being developed to facilitate both the near- and long-term management of radioactive wastes. For example, the Liquid Waste Transfer and Storage Project is underway to recover and process highly radioactive liquid wastes, currently stored in underground tanks that, in some cases, date back to the initial operations of the site. This project will stabilize the wastes and place them in modern, monitored storage for subsequent solidification and disposal. Another initiative, the Fuel Packaging and Storage Project, has been initiated to recover and condition degraded used fuel that is currently stored in below-ground standpipes. The fuel will be then be stored in new facilities based on an adaptation of AECL's proven MACSTOR TM * dry storage system, originally designed for intermediate-term above-ground storage of used CANDU fuel bundles. Other commercial-based development work is underway to improve the storage density of the MACSTOR TM design, and to extend its application to interim storage of used LWR fuels as well as to the storage of intermediate-level radioactive waste arising from upcoming reactor refurbishment activities in Canada

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

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

Fuel safety criteria technical review - Results of OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria

International Nuclear Information System (INIS)

Hollasky, N.; Valtonen, K.; Hache, G.; Gross, H.; Bakker, K.; Recio, M.; Bart, G.; Zimmermann, M.; Van Doesburg, W.; Killeen, J.; Meyer, R.O.; Speis, T.

2000-01-01

With the advent of advanced fuel and core designs, the adoption of more aggressive operational modes and the implementation of more accurate (best estimate or statistical) design and analysis methods, there is a concern if safety margins have remained adequate. Most - if not all - of the currently existing safety criteria were established during the 60's and early 70's, and verified against experiments with fuel that was available at that time, mostly with unirradiated specimens. Verification was of course performed as designs progressed in later years, however mostly with the aim to be able to prove that these designs adequately complied with existing criteria, and not to establish new limits. The OECD/CSNI/PWG2 Task Force on Fuel Safety Criteria (TFFSC) was therefore given the mandate to technically review the existing fuel safety criteria, focusing on the 'new design' elements (new fuel and core design, cladding materials, manufacturing processes, high burnup, MOX, etc.) introduced by the industry. It should also identify if additional efforts may be required (experimental, analytical) to ensure that the basis for fuel safety criteria is adequate to address the relevant safety issues. In this report, fuel-related criteria are discussed without attempting to categorize them according to event type or risk significance. For each of these 20 criteria, we present a brief description of the criterion as it is used in several applications along with the rationale for having such a criterion. New design elements, such as different cladding materials, higher burnup, and the use of MOX fuels, can affect fuel-related margins and, in some cases, the criteria themselves. Some of the more important effects are mentioned in order to indicate whether the criteria need to be re-evaluated. The discussion may not cover all possible effects, but should be sufficient to identify those criteria that need to be addressed. A summary of these discussions is given in Section 7. As part