Development of an integrated cost model for nuclear plant decommissioning

International Nuclear Information System (INIS)

Amos, G.; Roy, R.

2003-01-01

A need for an integrated cost estimating tool for nuclear decommissioning and associated waste processing and storage facilities for Intermediate Level Waste (ILW) was defined during the authors recent MSc studies. In order to close the defined gap a prototype tool was developed using logically derived CER's and cost driver variables. The challenge in developing this was to be able to produce a model that could produce realistic cost estimates from the limited levels of historic cost data that was available for analysis. The model is an excel based tool supported by 3 point risk estimating output and is suitable for producing estimates for strategic or optional cost estimates (±30%) early in the conceptual stage of a decommissioning project. The model was validated using minimal numbers of case studies supported by expert opinion discussion. The model provides an enhanced approach for integrated decommissioning estimates which will be produced concurrently with strategic options analysis on a nuclear site

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 handbook

Energy Technology Data Exchange (ETDEWEB)

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

1980-11-01

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

Decommissioning handbook

International Nuclear Information System (INIS)

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

1980-11-01

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

Offshore Wind Energy Cost Modeling Installation and Decommissioning

CERN Document Server

Kaiser, Mark J

2012-01-01

Offshore wind energy is one of the most promising and fastest growing alternative energy sources in the world. Offshore Wind Energy Cost Modeling provides a methodological framework to assess installation and decommissioning costs, and using examples from the European experience, provides a broad review of existing processes and systems used in the offshore wind industry. Offshore Wind Energy Cost Modeling provides a step-by-step guide to modeling costs over four sections. These sections cover: ·Background and introductory material, ·Installation processes and vessel requirements, ·Installation cost estimation, and ·Decommissioning methods and cost estimation.  This self-contained and detailed treatment of the key principles in offshore wind development is supported throughout by visual aids and data tables. Offshore Wind Energy Cost Modeling is a key resource for anyone interested in the offshore wind industry, particularly those interested in the technical and economic aspects of installation and decom...

Information management for decommissioning projects

International Nuclear Information System (INIS)

LeClair, A.N.; Lemire, D.S.

2011-01-01

This paper explores the importance of records and information management for decommissioning projects. Key decommissioning information and elements of a sound information management strategy are identified. Various knowledge management strategies and tools are discussed as opportunities for leveraging decommissioning information. The paper also examines the implementation of Atomic Energy of Canada Limited's (AECL) strategy for the long term preservation of decommissioning information, and its initiatives in leveraging of information with the application of several knowledge management strategies and tools. The implementation of AECL's strategy illustrates common as well as unique information and knowledge management challenges and opportunities for decommissioning projects. (author)

The IAEA Safety Regime for Decommissioning

International Nuclear Information System (INIS)

Bell, M.J.

2002-01-01

Full text of publication follows: The International Atomic Energy Agency is developing an international framework for decommissioning of nuclear facilities that consists of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, and a hierarchy of Safety Standards applicable to decommissioning. The Joint Convention entered into force on 18 June 2001 and as of December 2001 had been ratified by 27 IAEA Member States. The Joint Convention contains a number of articles dealing with planning for, financing, staffing and record keeping for decommissioning. The Joint Convention requires Contracting Parties to apply the same operational radiation protection criteria, discharge limits and criteria for controlling unplanned releases during decommissioning that are applied during operations. The IAEA has issued Safety Requirements document and three Safety Guides applicable to decommissioning of facilities. The Safety Requirements document, WS-R-2, Pre-disposal Management of Radioactive Waste, including Decommissioning, contains requirements applicable to regulatory control, planning and funding, management of radioactive waste, quality assurance, and environmental and safety assessment of the decommissioning process. The three Safety Guides are WS-G-2.1, Decommissioning of Nuclear Power Plants and Research Reactors, WS-G-2.2, Decommissioning of Medical, Industrial and Research Facilities, an WS-G-2.4, Decommissioning of Nuclear Fuel Cycle Facilities. They contain guidance on how to meet the requirements of WS-R-2 applicable to decommissioning of specific types of facilities. These Standards contain only general requirements and guidance relative to safety assessment and do not contain details regarding the content of the safety case. More detailed guidance will be published in future Safety Reports currently in preparation within the Waste Safety Section of the IAEA. Because much material arising during the decommissioning

Development and application of thermal cutting techniques during Phase 1 decommissioning of WAGR

International Nuclear Information System (INIS)

White, S.J.

1992-01-01

The Windscale Advanced Gas Cooled Reactor is the UK's lead Stage 3 Decommissioning Project. One of the main objectives of the project is to demonstrate that a nuclear reactor can be safely and effectively decommissioned to a greenfield site using existing technology. Techniques using thermal cutting processes are used widely in industry and have been successfully adapted and applied to the first phase of the dismantling project. Over 1000 operational cuts have been performed using plasma cutting technology. Oxypropane and thermic lancing technique have also been applied to the dismantling the Top Biological Shield and Top Dome of the reactor pressure vessel. This paper describes the development and application of these standard technologies to the task of decommissioning a nuclear reactor. (Author)

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

,; the fifth part presents the external points of view on dismantling with: the decommissioning of Saint-Laurent A, as seen by the local information committee, decommissioning: the urge for a public consultation, an evaluation of the work of the 'conseil superieur de la surete et de linformation nucleaire' (C.S.S.I.N.) - a consultative body dealing with information in the field of nuclear safety) on the issue of decommissioning basic nuclear installations, monitoring the decommissioning of nuclear facilities and examining applications. (N.C.)

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

Applicability of Learning From Experience to Sellafield Post-Operation Clean Out and Decommissioning Programmes

International Nuclear Information System (INIS)

Ytournel, Bertrand; Clement, Gilles; Macpherson, Ian; Dunlop, Alister

2016-01-01

Nuclear cycle facilities, such as recycling plants, over the world differ in their design and operation history. Transferability of Learning From Experience (LFE), Best Practices and Decommissioning tools and techniques may not appear as relevant as it would be for a fleet of reactors. Moreover Regulatory, Economic and Social Drivers may differ from one country to another. Technical Drivers being comparable, AREVA and Sellafield Ltd (SL) have conducted various benchmarks and technical peer reviews to consider LFE from AREVA's Post-Operation Clean Out (POCO) and Decommissioning projects (such as UP2-400 on the La Hague site) and those performed for customers (such as CEA's UP1 on the Marcoule site). The intention is that Sellafield can benefit from AREVA experience and incorporate some recommendations in their own programmes. These reviews highlighted not only that investigation tools and methods as well as Decommissioning techniques are fully transferable, but also that strategic, technical and organizational key recommendations are applicable. 1. End-state definition (for each programme step) has a strong impact on POCO and Decommissioning scenarios. 2. A waste-driven strategy is essential for the overall programme cost and schedule management, and it avoids detrimental activities and short-term decisions made under pressure that may have negative impacts on the Programme. 3. Safety issues associated with POCO and decommissioning programmes are different from the commercial operations environment. 4. An extensive characterization plan (with physical and radiological surveys and active sampling) is essential to underpin the final POCO / decommissioning scenario and build a plant configuration baseline that will be updated as the decommissioning progresses. 5. Transition from operations to decommissioning requires a major change in culture; the organization must adapt to the new decommissioning environment. 6. Securing specific competencies, resources and

Remote machine engineering applications for nuclear facilities decommissioning

International Nuclear Information System (INIS)

Toto, G.; Wyle, H.R.

1983-01-01

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

The application of modern project management principles and processes in major nuclear decommissioning programmes

International Nuclear Information System (INIS)

Bayliss, C. R.

2003-01-01

The UKAEA has embarked upon an accelerated programme of decommissioning works. This has resulted in a review of its project management systems and processes. This paper describes these processes and their application to nuclear decommissioning and associated new build construction projects. Efficiencies from these processes are necessary. In addition this paper describes how UKAEA, where appropriate, utilizes modern forms of alliance contract so as to work in partnership with its contractors. (author)

A model study of cost estimates of decontamination and decommissioning with an emphasis to derive cost functions for alpha contaminated material using OMEGA code

Energy Technology Data Exchange (ETDEWEB)

Kristofova, Kristina; Daniska, Vladimir; Ondra, Frantisek; Rehak, Ivan; Vasko, Marek [DECOM SLOVAKIA spol. s.r.o., Trnava (Slovakia)

2004-12-01

The presented study is focused on model decommissioning cost calculations for primary circuit of A-1 nuclear power plant in Jaslovske Bohunice. In addition, the survey of advanced decommissioning costing is included together with impact analyses of contamination on particular decommissioning parameters. OMEGA code decommissioning cost calculations for primary circuit of A-1 NPP presented in the study are performed and evaluated under the following conditions: different contamination level of inner and outer surfaces; different waste management scenarios; application and non-application of pre-dismantling decontamination; different start of decommissioning: 2004, 2010, 2020, 2030, 2040; radionuclide composition of primary circuit contamination in A-1 NPP with occurrence of alpha radionuclides and fission products as a consequence of operational accident with damaged fuel cladding; radionuclide composition of primary circuit contamination in V-2 NPP in Jaslovske Bohunice as a representative NPP with an operation without accidents and therefore neither non-alpha contaminants nor fission products are included. The results of all the above mentioned conditions impacts on calculated costs, manpower, exposure and distribution of materials arisen from decommissioning are evaluated in detail within the calculation sensitivity analysis.

A model study of cost estimates of decontamination and decommissioning with an emphasis to derive cost functions for alpha-contaminated material using OMEGA code

International Nuclear Information System (INIS)

Kristofova, Kristina; Daniska, Vladimir; Ondra, Frantisek; Rehak, Ivan; Vasko, Marek

2004-12-01

The presented study is focused on model decommissioning cost calculations for primary circuit of A-1 nuclear power plant in Jaslovske Bohunice. In addition, the survey of advanced decommissioning costing is included together with impact analyses of contamination on particular decommissioning parameters. OMEGA code decommissioning cost calculations for primary circuit of A-1 NPP presented in the study are performed and evaluated under the following conditions: different contamination level of inner and outer surfaces; different waste management scenarios; application and non-application of pre-dismantling decontamination; different start of decommissioning: 2004, 2010, 2020, 2030, 2040; radionuclide composition of primary circuit contamination in A-1 NPP with occurrence of alpha radionuclides and fission products as a consequence of operational accident with damaged fuel cladding; radionuclide composition of primary circuit contamination in V-2 NPP in Jaslovske Bohunice as a representative NPP with an operation without accidents and therefore neither non-alpha contaminants nor fission products are included. The results of all the above mentioned conditions impacts on calculated costs, manpower, exposure and distribution of materials arisen from decommissioning are evaluated in detail within the calculation sensitivity analysis

Shippingport station decommissioning project technology transfer program

International Nuclear Information System (INIS)

Pasquini, L.A.

1986-01-01

The purpose of the Shippingport Station Decommissioning Project (SSDP) is to place the Shippingport Atomic Power Station in a long-term radiologically safe condition following defueling of the reactor, to perform decommissioning in such a manner as to demonstrate to the nuclear industry the application of decommissioning procedures to a large scale nuclear power plant, and to provide useful planning data for future decommissioning projects. This paper describes the Technology Transfer Program for collecting and archiving the decommissioning data base and its availability to the nuclear industry

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

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

International Nuclear Information System (INIS)

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

2003-01-01

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

Applicability of compton imaging in nuclear decommissioning activities

International Nuclear Information System (INIS)

Ljubenov, V.Lj.; Marinkovic, P.M.

2002-01-01

During the decommissioning of nuclear facilities significant part of the activities is related to the radiological characterization, waste classification and management. For these purposes a relatively new imaging technique, based on information from the gamma radiation that undergoes Compton scattering, is applicable. Compton imaging systems have a number of advantages for nuclear waste characterization, such as identifying hot spots in mixed waste in order to reduce the volume of high-level waste requiring extensive treatment or long-term storage, imaging large contaminated areas and objects etc. Compton imaging also has potential applications for monitoring of production, transport and storage of nuclear materials and components. This paper discusses some system design requirements and performance specifications for these applications. The advantages of Compton imaging are compared to competing imaging techniques. (author)

Decommissioning challenges - an industrial reality

International Nuclear Information System (INIS)

Moore, H.; Mort, P.; Hutton, E.

2008-01-01

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

Investigation of Appropriate Applications for Reuse of Conditionally Released Materials from Decommissioning

International Nuclear Information System (INIS)

Daniska, V.; Vasko, M.; Necas, V.

2012-01-01

During the decommissioning (D and D) phase of nuclear facility life cycle a lot of original facility materials are generated as a primary decommissioning waste. One portion of these materials is unconditionally releasable, i.e. their radioactivity content is below the stipulated concentration limits for clearance thus they can be further recycled or dumped without any constraints as a conventional waste. Second portion of generated waste is waste with radioactivity content higher than limits for free release and it has to be handled and disposed of as the radioactive waste (RAW) within special RAW repositories. Disposal of RAW is quite expensive therefore it seems to be reasonable to reduce amount of waste destined for disposal and to identify RAW with radioactivity content slightly higher than stipulated concentration limits for unconditional release which could be released with some constraints for further recycling and reuse while stipulated safety requirements are observed, i.e. conditional release of RAW. The most perspective materials from decommissioning for such material reuse are steel and concrete. These materials can be reused within the long term robust constructions for applications with infrequent or only short time presence of personnel/public, minimum interaction of human with materials and controllable interaction of materials with environment. Ideal applications for deployment of such materials are steel reinforcement in pylons for highways, tunnel linings, industry prefabricates, big tanks or linings in nuclear applications, for concrete debris it can be filling material for road construction. Presented paper deals with preconditions for reuse of conditionally released materials. It maps legal pre-requisites in the Slovak Republic, appropriate material application scenarios, methodology of assessment of impact on human health and environment - external and internal exposure assessment, possible optimisation of scenarios and estimation of

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

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.

Investment and Decommissioning Decisions under Conditions of Uncertainty: An Application to the Electricity Sector

International Nuclear Information System (INIS)

Chaton, Corinne

2001-01-01

The purpose of this study is to use real options theory to answer the following question: Is it necessary, in France, to invest in new nuclear power units or should some of the existing units be decommissioned? The theoretical model developed establishes two price thresholds which determine investment or decommissioning rules for a regulated risk-neutral firm which does not know the future price of its input. It also provides an empirical reading of past choices in construction of French nuclear power plants. The main finding is that, on a certain number of theoretical and empirical assumptions, it is optimal at present is to leave French nuclear power capacity unchanged. Other more general findings follow from the theoretical model. Thus an increase in uncertainty facilitates investment, defers decommissioning and extends the range of input prices for which there is no change in capacity

Financial aspects of decommissioning (key aspects of decommissioning costing)

International Nuclear Information System (INIS)

Danska, V.

2009-01-01

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

Development of computer systems for planning and management of reactor decommissioning

International Nuclear Information System (INIS)

Yanagihara, Satoshi; Sukegawa, Takenori; Shiraishi, Kunio

2001-01-01

The computer systems for planning and management of reactor decommissioning were developed for effective implementation of a decommissioning project. The systems are intended to be applied to construction of work breakdown structures and estimation of manpower needs, worker doses, etc. based on the unit productivity and work difficulty factors, which were developed by analyzing the actual data on the JPDR dismantling activities. In addition, information necessary for project planning can be effectively integrated as a graphical form on a computer screen by transferring the data produced by subprograms such as radioactive inventory and dose rate calculation routines among the systems. Expert systems were adopted for modeling a new decommissioning project using production rules by reconstructing work breakdown structures and work specifications. As the results, the systems were characterized by effective modeling of a decommissioning project, project management data estimation based on feedback of past experience, and information integration through the graphical user interface. On the other hands, the systems were validated by comparing the calculated results with the actual manpower needs of the JPDR dismantling activities; it is expected that the systems will be applicable to planning and evaluation of other decommissioning projects. (author)

Workshop on decommissioning

International Nuclear Information System (INIS)

Broden, K.

2005-12-01

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

The Reuse of Decommissioned Facilities and Sites as an Emerging Means to Alleviate the Decommissioning Burden and its Potential Applications within IAEA's International Decommissioning Network

International Nuclear Information System (INIS)

Laraia, M.

2009-01-01

Around the world, but particularly in developing Member States, there are disused nuclear facilities or those approaching the end of their useful lives, for which appropriate decommissioning steps have not been taken, primarily due to limited technical and financial resources or competing priorities. One way of alleviating the financial and social burden associated with the final shutdown and decommissioning of nuclear facilities is the redevelopment of decommissioned facilities and sites for new, productive uses, either nuclear or non-nuclear. Sustainable development implies economic development with maintenance of social and community integrity. This objective can best be served by the sensitive redevelopment of sites to provide continuity of employment and new productive activity. Finally, experience to date with redevelopment both inside and outside the nuclear field suggests that successful engagement of the stakeholders can be a key success factor in promoting outcomes which are both profitable for the operator and recognised as responsible and worthwhile by the wider community. Following a generic discussion on factors and issues inherent to the re-development of decommissioned sites, this paper expands on several examples. It is noted that experience from the non-nuclear industrial sector is much more extensive than from the nuclear sector, and lessons from this sector should not be neglected. Many of world's nuclear facilities are small and widely distributed geographically, e.g. ∼300 aging or shut-down research reactors. Requests for assistance to address this issue from Member States exceed the capability of IAEA (and others) to deliver. However, integrating individual initiative into a designed-for-purpose network may compensate for these limitations. A new IAEA initiative amongst organizations from both potential 'donor' and 'recipient' Member States has taken the form of an 'International Decommissioning Network (IDN)'. The objectives of the IDN are

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-10-15

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

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

International Nuclear Information System (INIS)

Song, Chan-Ho; Park, Seung-Kook; Park, Hee-Seong; Moon, Jei-kwon

2014-01-01

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

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

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

International Nuclear Information System (INIS)

Efraimsson, Henrik; Amft, Martin; Leisvik, Mathias

2016-01-01

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

Decommissioning Handbook

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

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

Development of computer program for estimating decommissioning cost - 59037

International Nuclear Information System (INIS)

Kim, Hak-Soo; Park, Jong-Kil

2012-01-01

The programs for estimating the decommissioning cost have been developed for many different purposes and applications. The estimation of decommissioning cost is required a large amount of data such as unit cost factors, plant area and its inventory, waste treatment, etc. These make it difficult to use manual calculation or typical spreadsheet software such as Microsoft Excel. The cost estimation for eventual decommissioning of nuclear power plants is a prerequisite for safe, timely and cost-effective decommissioning. To estimate the decommissioning cost more accurately and systematically, KHNP, Korea Hydro and Nuclear Power Co. Ltd, developed a decommissioning cost estimating computer program called 'DeCAT-Pro', which is Decommission-ing Cost Assessment Tool - Professional. (Hereinafter called 'DeCAT') This program allows users to easily assess the decommissioning cost with various decommissioning options. Also, this program provides detailed reporting for decommissioning funding requirements as well as providing detail project schedules, cash-flow, staffing plan and levels, and waste volumes by waste classifications and types. KHNP is planning to implement functions for estimating the plant inventory using 3-D technology and for classifying the conditions of radwaste disposal and transportation automatically. (authors)

Environmental impact assessment of decommissioning treatment about radioactive model plant waste ore storage site

International Nuclear Information System (INIS)

Bei Xinyu

2012-01-01

Aiming at decommissioning treatment project of radioactive model plant waste ore storage site, based on the detailed investigations of source terms and project description, systematic environmental impacts have been identified. The environmental impacts both during decommissioning treatment, radioactive waste transportation and after treatment are assessed. Some specific environmental protection measures are proposed so as to minimize the adverse environmental impacts. (author)

Development of improved technology for decommissioning operations

International Nuclear Information System (INIS)

Allen, R.P.

1982-07-01

This paper describes the technology development activities conducted at Pacific Northwest Laboratory under US Department of Energy sponsorship to help ensure the availability of safe, cost-effective and environmentally sound decommissioning technology for radioactively contaminated facilities. These improved decommissioning technologies include techniques for the removal of contaminated concrete surfaces and coatings, adaptation of electropolishing and vibratory finishing decontamination techniques for field decommissioning applications, development of sensitive field instrumentation and methods for the monitoring of large surface areas, techniques for the field sectioning of contaminated components, improved contamination-stabilizing coatings and application methods, and development of a small solidification system for the field solidification of liquid waste. The results of cost/benefit studies for some of these technologies are also reported

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)

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

IDMT an integrated system to manage decommissioning activities

International Nuclear Information System (INIS)

Marsiletti, M.; Mini, G.; Orlandi, S.

2003-01-01

In the frame of decommissioning activities Ansaldo has developed a set of Integrated Decommissioning Management Tools (IDMT) addressed to dismantling work as well as to management of the wastes. The tools MIRAD and DECOM arise from the project of dismantling Italian NPPs (e.g. Caorso) as described in this paper. MIRAD is an integration between a 3 D CAD Model of the NPP in as build configuration and a computerized database (presently an MS Access application) which stores the information related to the radiological measurements detected through in field monitoring associated to any item present in the plant. DECOM is an integration system between a 3 D CAD Model of the NPP (as minimum for the controlled zone) in as-built configuration and a computerized database (presently an MS Access application) which stores the information associated to primary and secondary wastes produced during operation, dismantling or treatment activities.The IDMT system is currently used in the following NPPs in Italy: Caorso NPP (Mark II GE Containment BWR), Garigliano NPP (Dual Cycle GE BWR) and Trino NPP (Westinghouse PWR Plant). (authors)

Decommissioning of Brennilis NPP

International Nuclear Information System (INIS)

Baize, Jean-Marc

1998-01-01

This EDF press communique give information related to the decommissioning of the Brennilis NPP. The following five items are developed in this report: 1. the level-2 decommissioning operations at the Brennilis NPP; 2. the Brennilis NPP, a pilot operation from the commissioning up to the decommissioning; 3. history of the Brennilis NPP decommissioning; 4. the types of radioactive wastes generated by the Brennilis NPP decommissioning; 5. the Brennilis NPP - a yard management as a function of the wastes. The document contains also seven appendices addressing the following subjects: 1. the share of decommissioning assigned to EDF and the decommissioning steps; 2. the EDF installations in course of decommissioning; 3. the CEA decommissioned installations or in course of decommissioning; 4. regulations; 5. costs; 6. waste management - principles; 7. data on the decommissioning yard

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)

Building confidence in decommissioning in France: Towards a safe, industrially applicable, coherent national system without site or waste liberation

International Nuclear Information System (INIS)

Averous, J.; Chapalain, E.

2002-01-01

The rate of decommissioning in France is accelerating, as the first generation of power reactors will be actively decommissioned in the next few years. Experience has been gathered from past decommissioning activities and some current pilot decommissioning operations. This experience has shown that a national system has to be put in place to deal with decommissioning, waste elimination and site cleaning up activities in order to allow a consistent, safe, transparent and industrially applicable management of these matters. A system founded on successive lines of defence has been put into enforcement, which does not involve any site nor waste liberation, as it is considered that the criteria associated are always prone to discussion and contradiction. This system is based on the following concepts : 'nuclear waste', waste prone to have been contaminated or activated, is segregated from 'conventional waste' using a system involving successive lines of defence, and hence, building a very high level of confidence that no 'nuclear waste' will be eliminated without control in conventional waste eliminators or recycling facilities ; 'nuclear waste' is eliminated in dedicated facilities or repositories, or in conventional facilities under the condition of a special authorisation based on a radiological impact study and a public inquiry ; a global safety evaluation of the nuclear site is conducted after decommissioning in order to define possible use restrictions. In all cases, minimum restrictions will be put into enforcement in urbanisation plans to ensure sufficient precaution when planning future uses of the ground or the building. This paper describes this global system in detail and shows that its inherent consistency allows it to be easily applicable by operators while achieving a high level of safety and confidence. (author)

Shippingport Station Decommissioning Project Start of Physical Decommissioning

International Nuclear Information System (INIS)

Crimi, F. P.

1987-01-01

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

Methods of control of inaccuracy in calculation of nuclear power plant decommissioning parameters - 16383

International Nuclear Information System (INIS)

Ondra, Frantisek; Daniska, Vladimir; Rehak, Ivan; Necas, Vladimir

2009-01-01

The aim of the article is a development of analytical methodology for evaluation of input data inaccuracies impact on calculation of cost and other output decommissioning parameters. This methodology is based on analytical model calculations using the OMEGA code and taking into account the probability of input data inaccuracies occurrence also. To achieve about mentioned aim, the article identifies possible sources of input data inaccuracies and analyzes their level of impact on output parameters. Then the methodology for calculation of input parameters inaccuracies impact is developed, based on analytical model calculation. The model calculation takes into consideration output parameters impact on cost and other decommissioning output parameters in analytical way. The methodology used in model calculations is original, more over it implements the international standardized structure (IAEA, OECD/NEA, EC) [6] of decommissioning cost for the first time. A probabilistic occurrence of input data inaccuracies is taken into consideration and implemented in the methodology developed. A correction factors matrix for evaluation of input data inaccuracies impact on decommissioning output parameters is set up. The matrix contains parameters based on model calculations using the proposed methodology. Finally the methodology for application of correction factor matrix is proposed and tested; the methodology is used for calculation of contingency in the standardized structure which reflected the level of input data inaccuracies. The cost for individual decommissioning projects for common nuclear power plants are in the range 300 - 500 mil. EUR. Contingencies are from 10% to 30%, depending on the level of detailed during preparation of decommissioning projects. A implementation about mentioned methodology in the OMEGA code improves the accuracy of contingency. Consequently it makes calculated contingency more trustworthy and makes calculated decommissioning cost closer to reality

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

Social effects of decommissioning Trawsfynydd Power Station

International Nuclear Information System (INIS)

Jones, H.

2001-01-01

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

Radiological characterization and challenges at decommissioning sites

International Nuclear Information System (INIS)

Moore, Scott

2002-01-01

Scott Moore described the dose-based radiological characterisation process used in the USA, and four current characterisation issues faced there. His paper emphasized the importance of characterisation to control decommissioning hazards and costs: The License Termination Rule (LTR), Subpart E to 10 CFR Part 20, provides the dose-based criteria that the U.S. Nuclear Regulatory Commission (NRC) uses as the basis for regulating cleanup at material and reactor sites. The LTR permits the release of sites for unrestricted use, if the radioactivity that is distinguishable from background results in a total effective dose equivalent to an average member of a critical group that does not exceed 0.25 milli-Sievert per year (mSv/yr) (25 milli-rem/year) and the residual radioactivity has been reduced to levels that are as low as reasonably achievable. Additionally, the LTR establishes criteria for license termination with restrictions on future land use, which allow for a dose to the critical group of 0.25 mSv/yr (25 milli-rem/year) with restrictions in place, and 1 mSv/yr (100 milli-rem/year) if the restrictions fail. In certain circumstances as outlined in Subpart E, a dose as high as 5 mSv/yr (500 milli-rem/year) is permitted if restrictions fail. Following issuance of the dose-based LTR in 1997, NRC staff developed the Standard Review Plan for Decommissioning Plans (NUREG-1727). NUREG-1727 is a guidance document that describes the methods that NRC has determined are acceptable for implementing the LTR and other decommissioning regulations. While NUREG-1727 is focused on the review of decommissioning plans for nuclear material sites, it provides general guidance that in many cases is applicable to reactor sites (e.g., review criteria for dose-modeling and radiological surveys). In addition to NUREG-1727, staff developed the Standard Review Plan for Evaluating Nuclear Power Reactor License Termination Plans (NUREG-1700) as specific guidance for reactor decommissioning. NUREG

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)

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

Development of a Multi-Arm Mobile Robot for Nuclear Decommissioning Tasks

Directory of Open Access Journals (Sweden)

Mohamed J. Bakari

2008-11-01

Full Text Available This paper concerns the design of a two-arm mobile delivery platform for application within nuclear decommissioning tasks. The adoption of the human arm as a model of manoeuvrability, scale and dexterity is the starting point for operation of two seven-function arms within the context of nuclear decommissioning tasks, the selection of hardware and its integration, and the development of suitable control methods. The forward and inverse kinematics for the manipulators are derived and the proposed software architecture identified to control the movements of the arm joints and the performance of selected decommissioning tasks. We discuss the adoption of a BROKK demolition machine as a mobile platform and the integration with its hydraulic system to operate the two seven-function manipulators separately. The paper examines the modelling and development of a real-time control method using Proportional-Integral-Derivative (PID and Proportional-Integral-Plus (PIP control algorithms in the host computer with National Instruments functions and tools to control the manipulators and obtain feedback through wireless communication. Finally we consider the application of a third party device, such as a personal mobile phone, and its interface with LabVIEW software in order to operate the robot arms remotely.

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)

IAEA Assistance on Decommissioning of Small Facilities with Limited Resources

International Nuclear Information System (INIS)

Batandjieva, B.; Warnecke, E.

2008-01-01

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

Training practices to support decommissioning of nuclear facilities

International Nuclear Information System (INIS)

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

2006-01-01

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

Utility planning for decommissioning

International Nuclear Information System (INIS)

Williams, D.H.

1982-01-01

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

Study on the decommissioning of research reactor

Energy Technology Data Exchange (ETDEWEB)

Suh, Doo Hwan; Jun, Kwan Sik; Choi, Yoon Dong; Lee, Tae Yung; Kwon, Sang Woon; Lee, Jong Il [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-01-01

Currently, KAERI operates TRIGA Mark-II and TRIGA Mark-III research reactors as a general purpose research and training facility. As these are, however, situated at Seoul office site of KAERI which is scheduled to be transferred to KEPCO as well as 30 MW HANARO research reactor which is expected to reach the first criticality in 1995 is under construction at head site of KAERI, decommissioning of TRIGA reactors has become an important topic. The objective of this study is to prepare and present TRIGA facility decontamination and decommissioning plan. Estimation of the radioactive inventory in TRIGA research reactor was carried out by the use of computational method. In addition, summarized in particular were the methodologies associated with decontamination, segmenting processes for activated metallic components, disposition of wastes. Particular consideration in this study was focused available technology applicable to decommissioning of TRIGA research reactor. State-of-the-art summaries of the available technology for decommissioning presented here will serve a useful document for preparations for decommissioning in the future. 6 figs, 41 tabs, 30 refs. (Author).

Development of Cost Estimation Methodology of Decommissioning for PWR

International Nuclear Information System (INIS)

Lee, Sang Il; Yoo, Yeon Jae; Lim, Yong Kyu; Chang, Hyeon Sik; Song, Geun Ho

2013-01-01

The permanent closure of nuclear power plant should be conducted with the strict laws and the profound planning including the cost and schedule estimation because the plant is very contaminated with the radioactivity. In Korea, there are two types of the nuclear power plant. One is the pressurized light water reactor (PWR) and the other is the pressurized heavy water reactor (PHWR) called as CANDU reactor. Also, the 50% of the operating nuclear power plant in Korea is the PWRs which were originally designed by CE (Combustion Engineering). There have been experiences about the decommissioning of Westinghouse type PWR, but are few experiences on that of CE type PWR. Therefore, the purpose of this paper is to develop the cost estimation methodology and evaluate technical level of decommissioning for the application to CE type PWR based on the system engineering technology. The aim of present study is to develop the cost estimation methodology of decommissioning for application to PWR. Through the study, the following conclusions are obtained: · Based on the system engineering, the decommissioning work can be classified as Set, Subset, Task, Subtask and Work cost units. · The Set and Task structure are grouped as 29 Sets and 15 Task s, respectively. · The final result shows the cost and project schedule for the project control and risk management. · The present results are preliminary and should be refined and improved based on the modeling and cost data reflecting available technology and current costs like labor and waste data

Use of data processing tools in decommissioning nuclear facilities

International Nuclear Information System (INIS)

Petrasch, P.; Lukacs, G.

1995-01-01

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

Decommissioning and decontamination

International Nuclear Information System (INIS)

Dadoumont, J.; Cantrel, E.; Valenduc, P.; Noynaert, L.

2009-01-01

The SCK-CEN has built a large know-how in decommissioning and decontamination, thanks to its BR3 decommissioning project. In 2007, the decommissioning activities at BR3 have been continued according to the strategy. This article discusses main realisations the following domains: decommissioning of the neutron shield tank and installation of new ventilation for the controlled area, dismantling of the former one and characterization of the stack

Pipeline Decommissioning Trial AWE Berkshire UK - 13619

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

; - Hot tapping - a method of breaching the pipe while maintaining containment to remove residual liquids, - Crimp and shear - remote crimping, cutting and handling of pipe using the excavator - Pipe jacking - a way of removing pipes avoiding excavations and causing minimal disturbance and disruption. The details of the decommissioning trial design, the techniques employed, their application and effectiveness are discussed and evaluated here in. (authors)

Technical assessment of environmental and cost implications of superconducting super collider decommissioning

International Nuclear Information System (INIS)

Chen, S.Y.; Opelka, J.H.; Chambers, W.C.; Stavrou, J.

1988-07-01

Potential environmental and cost implications of decommissioning the proposed Superconducting Super Collider (SSC) are examined. One decommissioning alternative is selected for general assessment. That alternative includes removal of the major sources of radioactivity induced during operation and temporary entombment of remaining underground facilities. On the suface, the campus complex would be left in place for future use, but most other aboveground features would be dismantled and removed. Because of the low level of radioactivity that would be induced in SSC components during system operation, potential radiological impacts to the environment from decommissioning would be benign, and the estimated total occupational radiation dose to workers would be less that 5 person-rem. Potential nonradiological impacts of decommissioning are not evaluated because of the lack of site-specific data. The total estimated cost of decommissioning operations is $38 million. Although few current regulations are explicitly applicable, the SSC decommissioning operation should not encounter any difficulty in complying with potentially applicable regulatory constraints. Upon completion of decommissioning, the SSC site surface could be returned to unrestricted use, but it is recommended that a degree of institutional control and environmental monitoring be carried out for a short period following decommissioning. 11 refs., 8 figs., 6 tabs

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

International Nuclear Information System (INIS)

Varasano, Giovanni; Baldassarre, Leonardo; Petagna, Edoardo

2014-01-01

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

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

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

Site Decommissioning Management Plan. Supplement 1

International Nuclear Information System (INIS)

Fauver, D.N.; Weber, M.F.; Johnson, T.C.; Kinneman, J.D.

1995-11-01

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

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)

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

Energy Technology Data Exchange (ETDEWEB)

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

2015-05-15

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

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

International Nuclear Information System (INIS)

Song, Chan-Ho; Park, Hee-Seong; Ha, Jea-Hyun; Jin, Hyung-Gon; Park, Seung-Kook

2015-01-01

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

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

International Nuclear Information System (INIS)

Matsuhashi, Kazuya; Yanagihara, Satoshi

2015-01-01

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

The decision on the application to carry out a decommissioning project at Hinkley Point A Power Station under the Nuclear Reactors (Environmental Impact Assessment for Decommissioning) Regulations 1999

International Nuclear Information System (INIS)

2003-01-01

European Council Directive 85/337/EEC, as amended by Council Directive 97/1 I/EC, sets out a framework on the assessment of the effects of certain public and private projects on the environment. The Directive is implemented in Great Britain for decommissioning nuclear reactor projects by the Nuclear Reactors (Environmental Impact Assessment for Decommissioning) Regulations 1999. The intention of the Directive and Regulations is to involve the public through consultation in considering the potential environmental impacts of a decommissioning project, and to make the decision-making process on granting consent open and transparent. The Regulations require the licensee to undertake an environmental impact assessment, prepare an environmental statement that summarises the environmental effects of the project, and apply to the Health and Safety Executive (HSE) for consent to carry out a decommissioning project. There is an optional stage where the licensee may request from HSE an opinion on what the environmental statement should contain (called a pre-application opinion). The licensee of Hinkley Point A Power Station, Magnox Electric pie, requested a pre-application opinion and provided information in a scoping report in December 2000. HSE undertook a public consultation on the scoping report and provided its pre- application opinion in April 2001. The licensee applied to HSE for consent to carry out a decommissioning project and provided an environmental statement in December 2001. Following a public consultation on the environmental statement, HSE requested further information that was subsequently provided by the licensee. A further public consultation was undertaken on the further information that ended in March 2003. All these public consultations involved around 60 organisations. HSE granted consent to carry out a decommissioning project at Hinkley Point A Power Station under the Regulations in July 2003, and attached conditions to the Consent. HSE took relevant

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)

Securing decommissioning funds. Why organization matters?

International Nuclear Information System (INIS)

Tchapga, F.

2005-01-01

customers. Because of electricity sector restructuring, businesses are no longer protected from market sanctions and stock market volatility. The objective of this paper is to evaluate the compatibility of the design of reserve fund models with the liberalised electricity context. The paper first considers the design of reserve funds and concludes that there is no single design. Based on the variety of design, section two assess their respective compatibility with the new electricity context. It appears that the monitoring and control of the management of the funds are the main determinant of compatibility. The paper concludes that, as secure funding is a dimension of safe decommissioning, there is a necessity for an optimal design of decommissioning funds model. The paper also suggests that external management solution improve the credibility of decommissioning commitment. This paper has completed two objectives. Firstly, it has highlighted the diversity of designs of the decommissioning reserve funds. We have seen that the reserve funds are organised differently, regarding the key features of their design, namely the collection of funds, the management of the funds collected, and the monitoring and control of that management. Secondly, and in respect of the objective to ensure the availability of the funds when needed, the paper has shown that current designs of decommissioning reserve funds are not equally compatible with the constraints of the electricity sector liberalisation. In fact, the new electricity context is characterised by electricity price volatility with, at some conditions, harmful effects on the financial viability of electric companies. The paper has shown that external fund designs offer a satisfactory compatibility with these constraints. This is because the design of external funds imposes clear limitations on the behaviour of the manager of the funds. Therefore, the paper suggests that in a context of liberalised electricity market, external funds

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

Energy Technology Data Exchange (ETDEWEB)

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

2002-02-25

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

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

Decommissioning of nuclear power plants

International Nuclear Information System (INIS)

Friske, A.; Thiele, D.

1988-01-01

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

Policy on the decommissioning of nuclear facilities

International Nuclear Information System (INIS)

1988-08-01

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

Quality assurance program application during the decommissioning phase of the Shoreham Nuclear Plant

International Nuclear Information System (INIS)

Patch, R.L.

1993-01-01

The application of Quality Assurance (QA) requirements for operating nuclear power plants has evolved over the last 30 years. QA programs started as good management practices and evolved to a process that is implemented integral to very detailed Probabilistic Risk Assessments (PRAs). QA programs for controlling activities during decommissioning of nuclear power plants are still in their infancy. Regulatory guidance is currently being developed, and much of what exists is in the form of draft guidance documents. In determining where to apply QA controls during decommissioning, a series of questions must be asked: Is there an existing regulatory commitment? (Safety related or safety significant activity); Are there any postulated accidents which need to be prevented or mitigated; What are the unacceptable risks; Are there other key factors, such as human performance issues and Industrial Safety Programs, to be considered? Which QA controls are needed and to what extent they should be applied must be evaluated on a case by case basis. How much QA to apply is usually a risk evaluation in itself. Can you afford not to apply a specific control? Can you afford to apply costly and rigorous quality control programs? These questions had to be answered at the Shoreham Nuclear Power Station (SNPS) in order to develop and implement an acceptable and effective Quality Assurance program. Exploring the SNPS open-quotes lessons learnedclose quotes on how to apply a quality assurance program during decommissioning is what the following discussion is about

Decommissioning of Division of Military Application equipment at Hanford. Summary report

International Nuclear Information System (INIS)

Raile, M.N.

1977-06-01

This report describes the successful decommissioning of plutonium-contaminated equipment used for weapon component fabrication and inspection at the Hanford Plant. Special materials, techniques, and equipment were employed during the course of the decommissioning program. Most significant was the development and design of large, double-wall fiberglassed plywood boxes for long-term (20-years, minimum) retrievable storage of the contaminated equipment in underground transuranic waste trenches

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

Assuring the availability of funds for decommissioning nuclear reactors

International Nuclear Information System (INIS)

1990-08-01

The general requirements for applications for license termination and decommissioning nuclear power, research, and test reactors are contained in 10 CFR Part 50, ''Domestic Licensing of Production and Utilization Facilities.'' On June 27, 1988, the Commission published amendments to 10 CFR Part 50 (53 FR 24018) concerning specific criteria for decommissioning nuclear facilities. Amended 10 CFR 50.33(k), 50.75, and 50.82(b) require operating license applicants and existing licensees to submit information on how reasonable assurance will be provided that funds are available to decommission the facility. Amended section 50.75 establishes requirements for indicating how this assurance will be provided, namely the amount of funds that must provided, including updates, and the methods to be used for assuring funds. This regulatory guide has been developed in conjunction with the rule amendments and was published for public comment in May 1989. This version incorporates, where appropriate, the public comments received. Its purpose is to provide guidance to applicants and licensees of nuclear power, research, and test reactors concerning methods acceptable to the NRC staff for complying with requirements in the amended rule regarding the amount of funds for decommissioning. It also provides guidance on the content and form of the financial assurance mechanisms indicated in the rule amendments. 9 refs

Economic aspects of decommissioning

International Nuclear Information System (INIS)

Jenne, C.

1988-01-01

Two viewpoints on decommissioning are quoted; the first suggests that decommissioning can be viewed as a technical detail that is of limited relevance whereas the second suggests that decommissioning is a key financial issue. Both are specifically relevant to United Kingdom nuclear power stations. This paper attempts to reconcile the two views. It suggests that decommissioning does raise some important issues for regulation and financing of a privatised industry but, despite this, the economics of nuclear do remain insensitive. The paper begins by examining the significance of decommissioning costs in a number of contexts, including nuclear unit generating costs and financing requirements. It then addresses the degree of uncertainty in the decommissioning cost estimates. With privatisation on the horizon, the paper considers the significance of decommissioning and the associated uncertainty for the investor; this last section considers regulatory issues raised in relation to funding, accounting policy and electricity pricing. (author)

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

International Nuclear Information System (INIS)

Tachibana, Mitsuo

2016-01-01

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

1982 international decommissioning symposium

International Nuclear Information System (INIS)

Mickelson, S.

1982-01-01

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

Decommissioning of multiple-reactor stations: facilitation by sequential decommissioning

International Nuclear Information System (INIS)

Moore, E.B.; Smith, R.I.; Wittenbrock, N.G.

1982-01-01

Reductions in cost and radiation dose can be achieved for decommissionings at multiple reactor stations because of factors not necessarily present at a single reactor station: reactors of similar design, the opportunity for sequential decommissioning, a site dedicated to nuclear power generation, and the option of either interim or permanent low-level radioactive waste storage facilities onsite. The cost and radiation dose reductions occur because comprehensive decommissioning planning need only be done once, because the labor force is stable and need only be trained once, because there is less handling of radioactive wastes, and because central stores, equipment, and facilities may be used. The cost and radiation dose reductions are sensitive to the number and types of reactors on the site, and to the alternatives selected for decommissioning. 3 tables

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

Assessment of financial expenditure for Rivne NPP power units decommissioning

International Nuclear Information System (INIS)

Nosovskij, A.V.; Salij, L.M.

2007-01-01

The article covers some financial aspects of developing a decommissioning concept for Rivne NPP power units with reactor VVER-440 and VVER-1000. Possible methodological approaches to costs estimate have been analyzed. Preliminary results of cost estimation are presented for two decommissioning options: deferred and immediate dismantling. Principally possible options for accumulating assets have been analyzed to finance measures related to Rivne NPP decommissioning. A mathematical model has been proposed for creating decommissioning financial reserve

Decommissioning of Ukrainian NPPs

International Nuclear Information System (INIS)

Skripov, A.E.

2002-01-01

The decision about the development of 'Decommissioning Concept of Ukrainian NPPs' being on commercial operational stage was approved by NAEK 'Energoatom' Board of Administration by way of the decommissioning activity effective planning. The Concept will be the branch document, containing common approaches formulations on problem decisions according to the units decommissioning with generated resources, and RAW and SNF management strategy during decommissioning

Summary of Session 2.A. Decommissioning strategies and regulations

International Nuclear Information System (INIS)

Schattke, H.

2003-01-01

The discussion focused largely on the decommissioning of large nuclear facilities. Equivalent strategies and procedures need to be developed for the safe decommissioning of the many other applications in medicine, industry and research involving radioactive materials. Planning for decommissioning should start early. Ideally, decommissioning considerations should have been taken into account at the design stage. Three basic decommissioning strategies are envisaged as possibilities for nuclear installations: immediate dismantling; safe enclosure prior to deferred dismantling; and entombment. All have advantages and disadvantages, but immediate dismantling is the generally preferred option. Immediate dismantling typically has the fewest uncertainties. It also eliminates the risks associated with the facility as promptly as possible, normally costs less than delaying and allows the retention of operational staff who know the facility and its history to contribute their expertise and experience during decommissioning. Approaches to regulating the implementation of decommissioning plans vary, but the common aim is to provide effective regulatory control to ensure safe decommissioning. The transition from operation to decommissioning will usually be accompanied by organizational changes, particularly reductions in staff. Such reductions may be inevitable, but the operator must manage the change so as to retain the expertise needed and to guard against a degradation of safety culture due to demotivation of the remaining staff. The absence of an available disposal route has been used as another argument for the safe enclosure strategy rather than immediate dismantling, the idea being that dismantling is delayed until a repository is available. The ultimate aim of decommissioning is to allow the removal of some or all regulatory control from a site, but internationally agreed criteria for the removal of such controls are needed

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

International Nuclear Information System (INIS)

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

2013-01-01

government and private industry decommissioning applications. SRS offers critical services based upon the SRS experience in decommissioning and reactor entombment technology (e.g., grout formulations for varying conditions, structural and material sciences). The SRS ISD approach follows a systems engineering framework to achieve a regulatory acceptable end state based on established protocols, attains the final end state with minimal long stewardship requirements, protects industrial workers, and protects groundwater and the environment. The ISD systems engineering framework addresses key areas of the remedial process planning, technology development and deployment, and assessment to attain the ultimate goal of natural resource stewardship and protecting the public. The development and deployment of the SRS ISD approach has established a path for ISD of other large nuclear facilities in the United States and around the globe as an acceptable remedial alternative for decommissioning nuclear facilities. (authors)

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

international government and private industry decommissioning applications. SRS offers critical services based upon the SRS experience in decommissioning and reactor entombment technology (e.g., grout formulations for varying conditions, structural and material sciences). The SRS ISD approach follows a systems engineering framework to achieve a regulatory acceptable end state based on established protocols, attains the final end state with minimal long stewardship requirements, protects industrial workers, and protects groundwater and the environment. The ISD systems engineering framework addresses key areas of the remedial process planning, technology development and deployment, and assessment to attain the ultimate goal of natural resource stewardship and protecting the public. The development and deployment of the SRS ISD approach has established a path for ISD of other large nuclear facilities in the United States and around the globe as an acceptable remedial alternative for decommissioning nuclear facilities. (authors)

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.

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)

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

Decontamination and decommissioning technology tree and the current status of the technologies

Energy Technology Data Exchange (ETDEWEB)

Oh, Won Zin; Won, H.J.; Kim, G.N.; Lee, K.W.; Chol, W.K.; Jung, C.H.; Kim, C.J.; Kim, S.H.; Kwon, S.O.; Chung, C.M

2001-03-01

A technology tree diagram was developed on the basis of the necessary technologies applicable to the decontamination and decommissioning of nuclear facilities. The technology tree diagram is consist of 6 main areas such as characterization, decontamination, decommissioning and remote technology, radwaste management, site restoration, and decommissioning plan and engineering. Characterization is divided into 4 regions such as sampling and data collection, general characterization, chemical analysis and radiological analysis. Decontamination is also divided into 4 regions such as chemical decontamination, mechanical decontamination, the other decontamination technologies and new decontamination technologies. Decommissioning and remote technology area is divided into 4 regions such as cutting techniques, decommissioning technologies, new developing technologies and remote technologies. Radwaste management area is divided into 5 regions such as solid waste treatment, sludge treatment, liquid waste treatment, gas waste treatment and thermal treatment. Site restoration area is divided into 3 regions such as the evaluation of site contamination, soil decontamination and ground water decontamination. Finally, permission, decommissioning process, cost evaluation, quality assurance and the estimation of radionuclide inventory were mentioned in the decommissioning plan and engineering area. The estimated items for each technology are applicable domestic D and D facilities, D and D problem area and contamination/requirement, classification of D and D technology, similar technology, principle and overview of technology, status, science technology needs, implementation needs, reference and contact point.

Decontamination and decommissioning technology tree and the current status of the technologies

International Nuclear Information System (INIS)

Oh, Won Zin; Won, H. J.; Kim, G. N.; Lee, K. W.; Chol, W. K.; Jung, C. H.; Kim, C. J.; Kim, S. H.; Kwon, S. O.; Chung, C. M.

2001-03-01

A technology tree diagram was developed on the basis of the necessary technologies applicable to the decontamination and decommissioning of nuclear facilities. The technology tree diagram is consist of 6 main areas such as characterization, decontamination, decommissioning and remote technology, radwaste management, site restoration, and decommissioning plan and engineering. Characterization is divided into 4 regions such as sampling and data collection, general characterization, chemical analysis and radiological analysis. Decontamination is also divided into 4 regions such as chemical decontamination, mechanical decontamination, the other decontamination technologies and new decontamination technologies. Decommissioning and remote technology area is divided into 4 regions such as cutting techniques, decommissioning technologies, new developing technologies and remote technologies. Radwaste management area is divided into 5 regions such as solid waste treatment, sludge treatment, liquid waste treatment, gas waste treatment and thermal treatment. Site restoration area is divided into 3 regions such as the evaluation of site contamination, soil decontamination and ground water decontamination. Finally, permission, decommissioning process, cost evaluation, quality assurance and the estimation of radionuclide inventory were mentioned in the decommissioning plan and engineering area. The estimated items for each technology are applicable domestic D and D facilities, D and D problem area and contamination/requirement, classification of D and D technology, similar technology, principle and overview of technology, status, science technology needs, implementation needs, reference and contact point

R and D and Innovation Needs for Decommissioning Nuclear Facilities

International Nuclear Information System (INIS)

Farr, Harvey; LaGuardia, Thomas S.

2014-01-01

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

Basic Research on Selecting ISDC Activity for Decommissioning Costing in KRR-2 Decommissioning Project Experience Data

Energy Technology Data Exchange (ETDEWEB)

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

2015-10-15

KAERI is performing research for calculation of expected time of a decommissioning work and evaluation of decommissioning cost and this research calculate a decommissioning work unit productivity based on the experience data of decommissioning activity for KRR-2. The KAERI be used to calculate the decommissioning cost and manage the experience data from the decommissioning activity through the Decommissioning Information Management System (DECOMMIS), Decommissioning Facility Characterization DB System (DEFACS), and Decommissioning Work-unit Productivity Calculation System (DEWOCS). In this paper, the methodology was presented how select the ISDC activities in dismantling work procedures of a 'removal of radioactive concrete'. The reason to select the 'removal of radioactive concrete' is main key activity and generates the amount of radioactive waste. This data will take advantage of the cost estimation after the code for the selected items derived ISDC. There are various efforts for decommissioning costing in each country. In particular, OECD/NEA recommends decommissioning cost estimation using the ISDC and IAEA provides for Cost Estimation for Research Reactors in Excel (CERREX) program that anyone is easy to use the cost evaluation from a limited decommissioning experience in domestic. In the future, for the decommissioning cost evaluation, the ISDC will be used more widely in a strong position. This paper has described a method for selecting the ISDC item from the actual dismantling work procedures.

MODELLING OF NUCLEAR POWER PLANT DECOMMISSIONING FINANCING

Czech Academy of Sciences Publication Activity Database

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

2015-01-01

Roč. 164, č. 4 (2015), s. 519-522 ISSN 0144-8420 Institutional support: RVO:61389005 Keywords : nuclear power plant * methodology * future decommissioning costs Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.894, year: 2015

Decommissioning, mothballing and revamping

International Nuclear Information System (INIS)

Briggs, M.; Buck, S.; Smith, M.

1997-01-01

This guide, written to assist those concerned with the decommissioning of redundant facilities, is applicable to nuclear, chemical and power plants. Legal aspects and risk management is covered in the pre-project stage. Preparation for and execution of renovation, modification or mothballing of various plants is also covered. Dismantling operations and the necessary follow-up conclude the book. (UK)

Workshop on decommissioning; Seminarium om avveckling

Energy Technology Data Exchange (ETDEWEB)

Broden, K. (ed.)

2005-12-15

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

Identification and evaluation of facilitation techniques for decommissioning light water power reactors

International Nuclear Information System (INIS)

LaGuardia, T.S.; Risley, J.F.

1986-06-01

This report describes a study sponsored by the US Nuclear Regulatory Commission to identify practical techniques to facilitate the decommissioning of nuclear power generating facilities. The objective of these ''facilitation techniques'' is to reduce the radioactive exposures and/or volumes of waste generated during the decommissioning process. The report presents the possible facilitation techniques identified during the study and discusses the corresponding facilitation of the decommissioning process. Techniques are categorized by their applicability of being implemented during the three stages of power reactor life: design/construction, operation, or decommissioning. Detailed cost-benefit analyses were performed for each technique to determine the anticipated exposure and/or radioactive waste reduction; the estimated costs for implementing each technique were then calculated. Finally, these techniques were ranked by their effectiveness in facilitating the decommissioning process. This study is a part of the Nuclear Regulatory Commission's evaluation of decommissioning policy and its modification of regulations pertaining to the decommissioning process. The findings can be used by the utilities in the planning and establishment of activities to ensure that all objectives of decommissioning will be achieved

Proceedings of the Workshop on Current and Emerging methods for Optimising Safety and Efficiency in Nuclear Decommissioning

International Nuclear Information System (INIS)

2017-02-01

The workshop was organised by the Institute for Energy Technology (IFE) on behalf of the OECD Halden Reactor Project (OECD-HRP) and in collaboration with the International Atomic Energy Agency (IAEA) and the Nuclear Energy Agency (NEA). The workshop brought together more than 100 people (operators, regulators, scientists, consultants, and contractors) from 25 countries. Program: Day 1 - Successful application of R and D in decommissioning and future needs (Welcome and Opening Speeches; Session 1: Workshop Introductory Presentations; Session 2: Experience from starting, on-going and completed decommissioning projects). Day 2 - R and D and application of advanced technologies for decommissioning (Session 3: New technologies for decommissioning; Session 4: Advanced information technologies for decommissioning). Day 3 - Improving decommissioning management on project, national and international level (Session 5: Challenges and methods for improving decommissioning; Session 6: Workshop closing)

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

,; the fifth part presents the external points of view on dismantling with: the decommissioning of Saint-Laurent A, as seen by the local information committee, decommissioning: the urge for a public consultation, an evaluation of the work of the 'conseil superieur de la surete et de linformation nucleaire' (C.S.S.I.N.) - a consultative body dealing with information in the field of nuclear safety) on the issue of decommissioning basic nuclear installations, monitoring the decommissioning of nuclear facilities and examining applications. (N.C.)

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)

Decommissioning Unit Cost Data

International Nuclear Information System (INIS)

Sanford, P. C.; Stevens, J. L.; Brandt, R.

2002-01-01

The Rocky Flats Closure Site (Site) is in the process of stabilizing residual nuclear materials, decommissioning nuclear facilities, and remediating environmental media. A number of contaminated facilities have been decommissioned, including one building, Building 779, that contained gloveboxes used for plutonium process development but did little actual plutonium processing. The actual costs incurred to decommission this facility formed much of the basis or standards used to estimate the decommissioning of the remaining plutonium-processing buildings. Recent decommissioning activities in the first actual production facility, Building 771, implemented a number of process and procedural improvements. These include methods for handling plutonium contaminated equipment, including size reduction, decontamination, and waste packaging, as well as management improvements to streamline planning and work control. These improvements resulted in a safer working environment and reduced project cost, as demonstrated in the overall project efficiency. The topic of this paper is the analysis of how this improved efficiency is reflected in recent unit costs for activities specific to the decommissioning of plutonium facilities. This analysis will allow the Site to quantify the impacts on future Rocky Flats decommissioning activities, and to develop data for planning and cost estimating the decommissioning of future facilities. The paper discusses the methods used to collect and arrange the project data from the individual work areas within Building 771. Regression and data correlation techniques were used to quantify values for different types of decommissioning activities. The discussion includes the approach to identify and allocate overall project support, waste management, and Site support costs based on the overall Site and project costs to provide a ''burdened'' unit cost. The paper ultimately provides a unit cost basis that can be used to support cost estimates for

Information on Hydrologic Conceptual Models, Parameters, Uncertainty Analysis, and Data Sources for Dose Assessments at Decommissioning Sites

International Nuclear Information System (INIS)

Meyer, Philip D.; Gee, Glendon W.; Nicholson, Thomas J.

1999-01-01

This report addresses issues related to the analysis of uncertainty in dose assessments conducted as part of decommissioning analyses. The analysis is limited to the hydrologic aspects of the exposure pathway involving infiltration of water at the ground surface, leaching of contaminants, and transport of contaminants through the groundwater to a point of exposure. The basic conceptual models and mathematical implementations of three dose assessment codes are outlined along with the site-specific conditions under which the codes may provide inaccurate, potentially nonconservative results. In addition, the hydrologic parameters of the codes are identified and compared. A methodology for parameter uncertainty assessment is outlined that considers the potential data limitations and modeling needs of decommissioning analyses. This methodology uses generic parameter distributions based on national or regional databases, sensitivity analysis, probabilistic modeling, and Bayesian updating to incorporate site-specific information. Data sources for best-estimate parameter values and parameter uncertainty information are also reviewed. A follow-on report will illustrate the uncertainty assessment methodology using decommissioning test cases

Information on Hydrologic Conceptual Models, Parameters, Uncertainty Analysis, and Data Sources for Dose Assessments at Decommissioning Sites

International Nuclear Information System (INIS)

Meyer D, Philip; Gee W, Glendon

2000-01-01

This report addresses issues related to the analysis of uncertainty in dose assessments conducted as part of decommissioning analyses. The analysis is limited to the hydrologic aspects of the exposure pathway involving infiltration of water at the ground surface, leaching of contaminants, and transport of contaminants through the groundwater to a point of exposure. The basic conceptual models and mathematical implementations of three dose assessment codes are outlined along with the site-specific conditions under which the codes may provide inaccurate, potentially nonconservative results. In addition, the hydrologic parameters of the codes are identified and compared. A methodology for parameter uncertainty assessment is outlined that considers the potential data limitations and modeling needs of decommissioning analyses. This methodology uses generic parameter distributions based on national or regional databases, sensitivity analysis, probabilistic modeling, and Bayesian updating to incorporate site-specific information. Data sources for best-estimate parameter values and parameter uncertainty information are also reviewed. A follow-on report will illustrate the uncertainty assessment methodology using decommissioning test cases

Commercialization of nuclear power plant decommissioning technology

International Nuclear Information System (INIS)

Williams, D.H.

1983-01-01

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

Waste from decommissioning of nuclear power plants

International Nuclear Information System (INIS)

Nielsen, P.O.

1992-05-01

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

Status of the Decommissioning Project Management Information System Development of KAERI in 2015

International Nuclear Information System (INIS)

Jin, Hyung Gon; Park, Seungkook; Park, Heeseong; Song, Chanho

2015-01-01

Various information systems have been developed and used at decommissioning sites for planning a project, record keeping for a post management and cost estimation. KAERI is the only one expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR-1 and 2 and UCP (Uranium Conversion Plant) decommission. KRR-1 and KRR-2 are TRIGA MARK type of research reactor which were constructed worldwide. Hence, there are many chance to use decommissioning experiences and data when other TRIGA MARK type of research reactors start to decommission. KAERI DPMIS stands for Decommissioning Project Management Information System, which is aiming to re-use of data effectively. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DPMIS application program, which is going to be an important mile stone of decommission industry in Korea. User friendly graphical interface and lots of actual data let people well understood on decommission planning. It is expected that continuous effort and funds will be delivered to this research

Status of the Decommissioning Project Management Information System Development of KAERI in 2015

Energy Technology Data Exchange (ETDEWEB)

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

2015-10-15

Various information systems have been developed and used at decommissioning sites for planning a project, record keeping for a post management and cost estimation. KAERI is the only one expert group which has decommissioning experiences and KAERI is trying to develop computer code to converge all the data which has been accumulated during KRR-1 and 2 and UCP (Uranium Conversion Plant) decommission. KRR-1 and KRR-2 are TRIGA MARK type of research reactor which were constructed worldwide. Hence, there are many chance to use decommissioning experiences and data when other TRIGA MARK type of research reactors start to decommission. KAERI DPMIS stands for Decommissioning Project Management Information System, which is aiming to re-use of data effectively. As a responsible leading group of Korean decommissioning research field, KAERI has been developing DPMIS application program, which is going to be an important mile stone of decommission industry in Korea. User friendly graphical interface and lots of actual data let people well understood on decommission planning. It is expected that continuous effort and funds will be delivered to this research.

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.

Optimization in the decommissioning of uranium tailings

International Nuclear Information System (INIS)

1987-06-01

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

Assessment of exposure dose to workers in virtual decommissioning environments

International Nuclear Information System (INIS)

Jeong, KwanSeong; Moon, JeiKwon; Choi, ByungSeon; Hyun, Dongjun; Lee, Jonghwan; Kim, Ikjune; Kim, GeunHo; Seo, JaeSeok

2014-01-01

This paper is intended to suggest the method analyze and assess the exposure dose to workers in virtual decommissioning environments. To simulate a lot of decommissioning scenarios, decommissioning environments were designed in virtual reality. To simulate and assess the exposure dose to workers, human model also was designed in virtual environments. These virtual decommissioning environments made it possible to real-time simulate and assess the exposure dose to workers. This work was to be able to simulate scenarios of decommissioning so that exposure dose to workers could be measured and assessed. To establish the plan of exposure dose to workers during decommissioning of nuclear facilities before decommissioning activities are accomplished, the method of simulation assessment was developed in virtual radiological environments. But this work was developed as a tool of simulation for single subject mode. Afterwards, the simulation environment for multi-subjects mode will be upgraded by simultaneous modules with networking environments. Then the much more practical method will be developed by changing number of workers and duration of time under any circumstances of decommissioning

Assessment of exposure dose to workers in virtual decommissioning environments

Energy Technology Data Exchange (ETDEWEB)

Jeong, KwanSeong; Moon, JeiKwon; Choi, ByungSeon; Hyun, Dongjun; Lee, Jonghwan; Kim, Ikjune; Kim, GeunHo; Seo, JaeSeok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-10-15

This paper is intended to suggest the method analyze and assess the exposure dose to workers in virtual decommissioning environments. To simulate a lot of decommissioning scenarios, decommissioning environments were designed in virtual reality. To simulate and assess the exposure dose to workers, human model also was designed in virtual environments. These virtual decommissioning environments made it possible to real-time simulate and assess the exposure dose to workers. This work was to be able to simulate scenarios of decommissioning so that exposure dose to workers could be measured and assessed. To establish the plan of exposure dose to workers during decommissioning of nuclear facilities before decommissioning activities are accomplished, the method of simulation assessment was developed in virtual radiological environments. But this work was developed as a tool of simulation for single subject mode. Afterwards, the simulation environment for multi-subjects mode will be upgraded by simultaneous modules with networking environments. Then the much more practical method will be developed by changing number of workers and duration of time under any circumstances of decommissioning.

INTERNATIONAL DECOMMISSIONING SYMPOSIUM 2000

Energy Technology Data Exchange (ETDEWEB)

M.A. Ebadian, Ph.D.

2001-01-01

The purpose of IDS 2000 was to deliver a world-class conference on applicable global environmental issues. The objective of this conference was to publicize environmental progress of individual countries, to provide a forum for technology developer and problem-holder interaction, to facilitate environmental and technology discussions between the commercial and financial communities, and to accommodate information and education exchange between governments, industries, universities, and scientists. The scope of this project included the planning and execution of an international conference on the decommissioning of nuclear facilities, and the providing of a business forum for vendors and participants sufficient to attract service providers, technology developers, and the business and financial communities. These groups, when working together with attendees from regulatory organizations and government decision-maker groups, provide an opportunity to more effectively and efficiently expedite the decommissioning projects.

Computer System Analysis for Decommissioning Management of Nuclear Reactor

International Nuclear Information System (INIS)

Nurokhim; Sumarbagiono

2008-01-01

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

Decommissioning and equipment replacement of nuclear power plants under uncertainty

International Nuclear Information System (INIS)

Takashima, Ryuta; Naito, Yuta; Kimura, Hiroshi; Madarame, Haruki

2007-01-01

This study examines the optimal timing for the decommissioning and equipment replacement of nuclear power plants. We consider that the firm has two options of decommissioning and equipment replacement, and determines to exercise these options under electricity price uncertainty. This problem is formulated as two optimal stopping problems. The solution of this model provides the value of the nuclear power plant and the threshold values for decommissioning and replacement. The dependence of decommissioning and replacement strategies on uncertainty and each cost is shown. In order to investigate the probability of events for decommissioning and replacement, Monte Carlo calculations are performed. We also show the probability distribution and the conditional expected time for each event. (author)

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

International Nuclear Information System (INIS)

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

1979-08-01

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

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

International Nuclear Information System (INIS)

2008-10-01

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

State of decommissioning process in Romania

International Nuclear Information System (INIS)

Ciuculescu, C.

2002-01-01

In Romania, there are several installations that arrived at the decommissioning stage. These installations are: VVR-S research reactor, Sub critical Assembly HELEN, and Zero Power Reactor (RP-0). In this paper, the methods the Romanian Regulatory Body is developing the legal framework for decommissioning process of nuclear installations are described. There is a draft of decommissioning norms for research reactors. This regulation provides each stage of decommissioning and requirements for decommissioning plan. Also, CNCAN has evaluated and made requirements for completion of a VVR-S research reactor decommissioning plan submitted by IFIN-HH. Further, the reasons for which the decommissioning plan was rejected and requirements that the owner of VVR-S research reactor must fulfil in order to receive decommissioning licence are presented. (author)

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

Current status of Chernobyl NPP decommissioning

International Nuclear Information System (INIS)

2009-01-01

Strategy of Chernobyl NPP decommissioning with the decommissioning license 2002-2064 is presented. The main activities at the stage of ChNPP units shutdown (2002 - 2012) are: units maintenance in safe state; decommissioning infrastructure construction; unloading of SNF – main activity determining the stage duration; systems and elements final shutdown; decommissioning life-support systems reconstruction; Comprehensive engineering and radiation survey (CERS); dismantling of the reactor facilities external equipment; removal of RAW from units; decommissioning documentation development. The decommissioning activities main results are presented

Decommissioning of the BR3 PWR

International Nuclear Information System (INIS)

Massaut, V.; Klein, M.

1998-01-01

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

Idea: an integrated set of tools for sustainable nuclear decommissioning projects

International Nuclear Information System (INIS)

Detilleux, M.; Centner, B.; Vanderperre, S.; Wacquier, W.

2008-01-01

Decommissioning of nuclear installations constitutes an important challenge and shall prove to the public that the whole nuclear life cycle is fully mastered by the nuclear industry. This could lead to an easier public acceptance of the construction of new nuclear power plants. When ceasing operation, nuclear installations owners and operators are looking for solutions in order to assess and keep decommissioning costs at a reasonable level, to fully characterise waste streams (in particular radiological inventories of difficult-to-measure radionuclides) and to reduce personnel exposure during the decommissioning activities taking into account several project, site and country specific constraints. In response to this need, Tractebel Engineering has developed IDEA (Integrated DEcommissioning Application), an integrated set of computer tools, to support the engineering activities to be carried out in the frame of a decommissioning project. IDEA provides optimized solutions from an economical, environmental, social and safety perspective. (authors)

Demonstration of safety of decommissioning of facilities using radioactive material

International Nuclear Information System (INIS)

Batandjieva, Borislava; O'Donnell, Patricio

2008-01-01

at national and regional level (e.g. Europe); (4) the international projects such as DeSa (Evaluation and Demonstration of Safety during Decommissioning of Nuclear Facilities) and its planned follow-up, R 2 D 2 P and Iraq project; as well as (5) through training and education of specialists working in the field of decommissioning and (6) facilitation of the exchange of knowledge and experience between all Member States (e.g. Athens conference in 2006, International decommissioning forum, Annual forum for operators and regulators in decommissioning). The ongoing cooperation with Member States shows that the areas of specific interest for the Member States remain the following: the relevant safety criteria and safety assessment methodology to be applied to decommissioning; application of the graded approach in the development and review of safety assessments or decommissioning plans; evolution of the decommissioning plan and the supporting arguments through the decommissioning project. This paper presents a summary of the recent IAEA activities and projects on demonstration of safety during decommissioning and the lessons learned to date. (author)

Development of decommissioning technologies in Sumitomo Mitsui Construction Co., Ltd

International Nuclear Information System (INIS)

Maruyama, Shinichiro; Suzuki, Toru; Ogane, Daisuke

2011-01-01

The decommissioning program of nuclear reactors in Japan first started in December 2001 on the Japan's first commercial nuclear power station Tokai Power Plant. In February 2008, the decommissioning of 'Fugen' was first approved as the program on a large-scale water reactor in Japan, and was started. From now on, decommissioning programs of LWRs constructed in the early stage of nuclear development will gradually increase. Decommissioning projects are required more than 20 years for completing the entire processes, because of its characteristics to placing the utmost priority to safety. Diverse types of element technologies are fully utilized in decommissioning projects, such as technology of evaluating remaining radioactivity, decontamination, dismantling/remote control, and treatment/disposal/recycling. Also there are a lot of civil engineering or building technologies and its applied technologies in these element technologies. Sumitomo Mitsui Construction Co., Ltd. has been committed to contributing to the promotion of decommissioning projects in Japan, and has carried out investigation/evaluation of applicability of the existing dismantling technologies to dismantling of reactors, seismic evaluation of the buildings for dismantling the reactor zone, development of recycling of concrete, and discussion of rational waste treatment/disposal methods. In this thesis, we present our decommissioning technologies focusing on the element technologies that our company has investigated and developed so far. (author)

New projects related to decommissioning

International Nuclear Information System (INIS)

Benbow, R.

2008-01-01

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

Nuclear decommissioning

International Nuclear Information System (INIS)

Anon.

1987-01-01

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

Proceedings of the International Symposium on Preparation for Decommissioning - PREDEC 2016

International Nuclear Information System (INIS)

2016-02-01

The objective of the PREDEC 2016 symposium is to share current practice, experiences and innovations relating to the preparations for decommissioning of nuclear facilities. The symposium will be a forum to: Learn about current practices, Highlight strategic issues related to radiological characterisation and decommissioning, Exchange experiences, Discuss innovative and new techniques and needs for improvements, Develop and maintain networks in the area of radiological characterisation. Seven sessions in total were scheduled with the following topics: 1. Preparation for decommissioning - strategic issues: Preparation for decommissioning requires several strategic decisions with significant impact on the activities. This session covers a wide span of strategic issues such as: Immediate vs. deferred dismantling, Timing and strategic approach for the decommissioning preparations, Prioritised strategic decisions in case of a non-scheduled final shutdown. 2. Early characterisation challenges: There are significant advantages with an early characterisation of a facility to be decommissioned but an early characterisation is faced with constraints, limitations and challenges. The session is open for all approaches and strategies for early characterisation issues, including facility characterisation using theoretical models. 3. Workforce transition, flexibility and knowledge management: The transition from normal operation to facility dismantling involves several important evaluations, decisions and actions. This session covers project organisation issues like: Dismantling by former operators or by specialised teams, Concepts for how the transition could be structured to secure that the required knowledge is kept within the organisation, Ways to achieve the required workforce flexibility for a cost efficient decommissioning project. 4. Key aspects for efficient and cost effective waste management: This session covers activities in the preparation phase that supports an

Deregulation in the field of decommissioning and dismantling of nuclear facilities

International Nuclear Information System (INIS)

Kurz, A.

1994-05-01

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

Decommissioning in western Europe

International Nuclear Information System (INIS)

Lundqvist, K.

1999-12-01

This report gives an overview of the situation in Western Europe. The original aim was to focus on organisational and human issues with regard to nuclear reactor decommissioning, but very few articles were found. This is in sharp contrast to the substantial literature on technical issues. While most of the reports on decommissioning have a technical focus, several provide information on regulatory issues, strategies and 'state of the art'. The importance of the human and organizational perspective is however discovered, when reading between the lines of the technical publications, and especially when project managers summarize lessons learned. The results are to a large extent based on studies of articles and reports, mainly collected from the INIS database. Decommissioning of nuclear facilities started already in the sixties, but then mainly research and experimental facilities were concerned. Until now about 70 reactors have been shutdown world-wide. Over the years there have been plenty of conferences for exchanging experiences mostly about technical matters. Waste Management is a big issue. In the 2000s there will be a wave of decommissioning when an increasing amount of reactors will reach the end of their calculated lifetime (40 years, a figure now being challenged by both life-extension and pre-shutdown projects). Several reactors have been shut-down for economical reasons. Shutdown and decommissioning is however not identical. A long period of time can sometimes pass before an owner decides to decommission and dismantle a facility. The conditions will also differ depending on the strategy, 'immediate dismantling' or 'safe enclosure'. If immediate dismantling is chosen the site can reach 'green-field status' in less than ten years. 'Safe enclosure', however, seems to be the most common strategy. There are several pathways, but in general a safe store is constructed, enabling the active parts to remain in safe and waterproof conditions for a longer period of

Plan for reevaluation of NRC policy on decommissioning of nuclear facilities

International Nuclear Information System (INIS)

1978-12-01

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

Decommissioning the Los Alamos Molten Plutonium Reactor Experiment (LAMPRE I)

International Nuclear Information System (INIS)

Harper, J.R.; Garde, R.

1981-11-01

The Los Alamos Molten Plutonium Reactor Experiment (LAMPRE I) was decommissioned at the Los Alamos National Laboratory, Los Alamos, New Mexico, in 1980. The LAMPRE I was a sodium-cooled reactor built to develop plutonium fuels for fast breeder applications. It was retired in the mid-1960s. This report describes the decommissioning procedures, the health physics programs, the waste management, and the costs for the operation

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

Money Related Decommissioning and Funding Decision Making

International Nuclear Information System (INIS)

Goodman, Lynne S.

2008-01-01

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

The application of VR-GIS to decommissioning decision support system (DDSS) of nuclear reactor

International Nuclear Information System (INIS)

Zhu Bo

2005-01-01

Advanced management technique and Decision Support System (DSS) are needed to solve the problems of the nuclear reactor decommissioning decision-making. In this study, a kind of new DSS technique for nuclear reactor decommissioning is introduced. It is based on the Virtual Reality (VR) and Geography Information System (GIS), which combine with the scientific management method, operational research, cybernetics and behavior science. The proposed DDSS (Decommissioning Decision Support System) can provide decision-maker the real time 3-D virtual Environment, GIS information and background material of the decommissioning reactor, help to ascertain the decision-making target, modify the decision module and optimize the dismantling plan. The data from three modules (VR Environment Module, VR-DOSE Management Module and Route Layout GIS Module) are used to continuously update and show the statistic at the same time, and the final advice will be given to decision-maker. (authors)

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

FIR 1 TRIGA activity inventories for decommissioning planning

International Nuclear Information System (INIS)

Raety, Antti; Kotiluoto, Petri

2016-01-01

The objective of the study has been to estimate the residual activity in the decommissioning waste of TRIGA Mark II type research reactor FiR 1 in Finland. Neutron flux distributions were calculated with Monte Carlo code MCNP. These were used in ORIGEN-S point-depletion code to calculate the neutron induced activity of materials at different time points by modelling the irradiation history and radioactive decay. The knowledge of radioactive inventory of irradiated materials is important in the planning of the decommissioning activities and is essential for predicting the radiological impact to personnel and environment. Decommissioning waste consists mainly of ordinary concrete, aluminium, steel and graphite parts. Results include uncertainties due to assumptions on material compositions and possible diffusion of gaseous nuclides. Comparison to activity inventory estimates of two other decommissioned research reactors is also presented. (authors)

Decommissioning of NPP A-1

International Nuclear Information System (INIS)

Anon

2009-01-01

In this presentation the Operation history of A1 NPP, Project 'Decommissioning of A1 NPP' - I stage, Project 'Decommissioning of A1 NPP ' - II stage and Next stages of Project 'Decommissioning of A1 NPP ' are discussed.

Fort St. Vrain decommissioning project

International Nuclear Information System (INIS)

Fisher, M.

1998-01-01

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

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

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

Costs of Decommissioning Nuclear Power Plants

International Nuclear Information System (INIS)

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

2016-01-01

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

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 strategy selection

International Nuclear Information System (INIS)

Warnecke, E.

2005-01-01

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

Decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Schneider, K.J.

1979-01-01

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

Financing the Decommissioning of Nuclear Facilities

International Nuclear Information System (INIS)

2016-01-01

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

Decommissioning funding: ethics, implementation, uncertainties

International Nuclear Information System (INIS)

2006-01-01

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

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)

Decommissioning Facility Characterization DB System

International Nuclear Information System (INIS)

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

2010-01-01

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

Decommissioning Facility Characterization DB System

Energy Technology Data Exchange (ETDEWEB)

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

2010-10-15

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

Implementation of requirements of environmental management (ISO 14000) for the decommissioning of the heavy water plant

International Nuclear Information System (INIS)

Gonzalez, Maria I.; Otero de Eppenstein, Marta; Tosi, Lidia E.; Sabio, Manuel

2000-01-01

The National Atomic Energy Commission (CNEA) of Argentina has a project of decommissioning in the heavy water plant (Planta Experimental de Agua Pesada - PEAP). The aim of this project is to get some experience for decommissioning of nuclear plants and to achieve knowledge about the application of the requirements in environmental management. The project is being carried out according to ISO 14001 standards 'Environmental Management Systems'. The objectives were taken from the model without any expectation of achieving the complete implementation or certification of the system. This report is a description of the acts that have been done. (author)

Survey of decontamination and decommissioning techniques

International Nuclear Information System (INIS)

Kusler, L.E.

1977-01-01

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

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

International Nuclear Information System (INIS)

2013-08-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

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

Evaluation of Nuclear Facility Decommissioning Projects program

International Nuclear Information System (INIS)

Baumann, B.L.

1983-01-01

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

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

Recordkeeping in the decommissioning process

International Nuclear Information System (INIS)

Boing, L. E.

2000-01-01

In the US, there are two sets of key decommissioning records clearly identified -- those that are essential for planning the D and D of a facility and then those that are the result of the decommissioning process itself. In some cases, the regulatory authorities require and in others advise the licensees of the records that may be useful or which are required to be kept from the decommissioning. In the remainder of the paper, the author attempts to highlight some important aspects of decommissioning recordkeeping

Decommissioning project management unit started its activities

International Nuclear Information System (INIS)

Medeliene, D.

2002-01-01

The Decommissioning Project Management Unit team comprises western experts as well as experts from INPP Decommissioning Service who all work as a single team. The DPMU will develop the Final Decommissioning Plan and a more detailed Decommissioning Project, which will describe how the plant will be removed from service and safely decommissioned

Decommissioning Funding: Ethics, Implementation, Uncertainties

International Nuclear Information System (INIS)

2007-01-01

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

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)

Decision and Recommendation of the Steering Committee Concerning the Application of the Paris Convention to Nuclear Installations in the Process of Being Decommissioned

International Nuclear Information System (INIS)

2013-01-01

The NEA Steering Committee for Nuclear Energy adopted the Decision and Recommendation Concerning the Application of the Paris Convention to Nuclear Installations in the Process of Being Decommissioned on 30 October 2014. The purpose of this Decision and Recommendation is to provide updated technical exclusion criteria, replacing the 1990 criteria that were in force. The criteria are relatively conservative, and some nuclear installations in the process of decommissioning will not, at first, be eligible for exclusion. However, at some point during the decommissioning process, the nuclear installation would meet the criteria and could be excluded from the Paris Convention nuclear liability regime, relieving the operator from the obligation to have and maintain the specific, high level nuclear liability insurance coverage. The Decision and Recommendation's Appendix and Explanatory Note are included in the document

European Decommissioning Academy

International Nuclear Information System (INIS)

Slugen, V. S.; Hornacek, M.

2016-01-01

Full text: Experiences from the first run of the European Decommissioning Academy (EDA) are reported in details. EDA was created at the Slovak University of Technology in Bratislava Slovakia, based on discussion and expressed needs declared at many international meetings including ECED2013. The first run successfully passed 15 participants during 7–26 June 2015. Academy was focused on decommissioning issues via lessons, practical exercises in laboratories, on-site training prepared at NPP V-1 in Jaslovské Bohunice, Slovakia as well as four day technical tour to other European decommissioning facilities in Switzerland and Italy. Detailed information can be found at http://kome.snus.sk/inpe/. (author

Expansive development of a decommissioning program 'recycle simulator' in nuclear power station

International Nuclear Information System (INIS)

Nishiuchi, T.; Ozaki, S.; Hironaga, M.

2004-01-01

A decommissioning program 'Recycle Simulator' should be put into practice in careful consideration of both recycle of non-radioactive wastes and reduce of radioactive wastes in the coming circulatory social system. Nevertheless current support systems for decommissioning planning mainly deal with decontamination, safety storage and dismantlement, so-called the prior part of the total decommissioning process. Authors emphasize the necessity of total planning of decommissioning including recycle or reuse of a large amount of demolition materials and are propelling the development of the multi expert system named 'Recycle Simulator'. This paper presents an algorithm of the recycling and reusing scenario of demolition materials and a summarized configuration. 'Recycle Simulator' for the demolished concrete was developed in 2000 and presented at a previous International Conference on Nuclear Engineering. Construction of a supporting multi expert system for the totally planning of decommissioning projects is objected by expansive development of the previous version. 3 main conclusions obtained from this paper are the following. (1) The previously developed expert system was advanced in its estimation function toward the satisfaction of decommissioning planners. (2) The applicability of the system was enlarged to all the radioactive and non-radioactive wastes, demolished metal and concrete products, in a corresponding site of decommissioning. (3) Finally decommissioning recycle simulator was completed in a harmonized unification. (authors)

Development of a digital mock-up system for selecting a decommissioning scenario

International Nuclear Information System (INIS)

Kim, Sung-Kyun; Park, Hee-Sung; Lee, Kune-Woo; Jung, Chong-Hun

2006-01-01

The evaluation of decommissioning scenarios is critical to the successful development and execution of a decommissioning project. In the past, many experts have used a physical mock-up system to find the exact work processes and the working positions. Nowadays, these jobs are being done by a Digital Mock-Up (DMU) system. The DMU, which is a technology to realize an effective work process by using virtual environments through representing the physical and logical schema and the behavior of a real decommissioning work, can save on the cost and time, reduce the risk of making later changes, and develop various decommissioning scenarios. In this research, a decommissioning DMU system was developed for simulating the relevant dismantling processes. Decommissioning data-computing modules which can calculate a dismantling schedule, quantify a radioactive waste, visualize a radioactive inventory, estimate a decommissioning cost, and estimate a worker's exposure were also developed to qualitatively assess the decommissioning information. And an analytic hierarchy process (AHP) model was developed to evaluate the decommissioning scenarios which reflected the quantitative and qualitative considerations. To establish the proper scenario for the thermal column in KRR-1, the developed decommissioning DMU system was applied to evaluate the two candidate scenarios of it

MAESTRO, a hydraulic manipulator for maintenance and decommissioning applications

International Nuclear Information System (INIS)

Olivier David; Yvan Measson; Catherine Bidard; Christine Libersa

2006-01-01

end effector of the arm is made of a tool changer. A complete set of working tools is therefore available for various applications starting from pipe cutting with hydraulics jaws to NDT sensors used in control tasks. Testing of the first MAESTRO system is under progress on a pilot decommissioning site at CEA Pierrelatte. All functions will be assessed under real operating conditions. This paper presents the complete MAESTRO system. An overview of the research and development programs is given: Failure detection (thanks to dynamic model), replace the oil by water. (authors)

Nuclear decommissioning

Energy Technology Data Exchange (ETDEWEB)

Lawton, H.

1987-02-01

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

Decommissioning Cost Estimating -The ''Price'' Approach

International Nuclear Information System (INIS)

Manning, R.; Gilmour, J.

2002-01-01

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

Decommissioning planning and the assessment of alternatives for the Hanford production reactors

International Nuclear Information System (INIS)

Miller, C.E. Jr.; Potter, R.F.

1985-01-01

Several years ago, the US Department of Energy began assessing alternatives and planning the decommissioning of eight shut-down plutonium production reactors located on the DOE Hanford Site in Washington State. The first of these graphite-moderated, water-cooled, reactors was built and started up in 1944 as part of the World War II Manhattan Project. The last of them started up in 1955. The eight reactors each operated for 12 to 24 years, with all eight operating simultaneously for about 10 years. In the 1960's, production needs declined and the reactors were one-by-one permanently shut down, the last of them in 1971. (A ninth Hanford production reactor, N Reactor, was started up in 1963; it is still operating and is not within the scope of the decommissioning planning and alternatives assessment work reported in this paper). This paper provides an overview description of the decommissioning plan for the eight shut-down Hanford production reactors and their associated fuel storage basins. Included are descriptions of the decommissioning alternatives considered for the facilities, along with discussions of National Environmental Policy Act (NEPA) process activities applicable to the Hanford decommissioning work. The criteria used in assessing decommissioning alternatives and the assumptions used in the decommissioning planning are identified. 4 refs., 8 figs., 3 tabs

Decommissioning: a problem or a challenge?

Directory of Open Access Journals (Sweden)

Mele Irena

2004-01-01

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

A Comparative Perspective on Reactor Decommissioning

International Nuclear Information System (INIS)

Devgun, J.S.; Zelmer, R.

2006-01-01

A comparative perspective on decommissioning, based on facts and figures as well as the national policies, is useful in identifying mutually beneficial 'lessons learned' from various decommissioning programs. In this paper we provide such a perspective on the US and European approaches based on a review of the programmatic experience and the decommissioning projects. The European countries selected for comparison, UK, France, and Germany, have nuclear power programs comparable in size and vintage to the US program but have distinctly different policies at the federal level. The national decommissioning scene has a lot to do with how national nuclear energy policies are shaped. Substantial experience exists in all decommissioning programs and the technology is in a mature state. Substantial cost savings can result from sharing of decommissioning information, technologies and approaches among various programs. However, the Achilles' heel for the decommissioning industry remains the lack of appropriate disposal facilities for the nuclear wastes. (authors)

Vandellos 1 NPP decommissioning feedback experience

International Nuclear Information System (INIS)

Fernandez, Rodriguez A.

2003-01-01

necessary to support in order to reuse and apply the model to others projects. This knowledge and experience are mostly in three areas: -Data Bases, -Basic Document and - Lessons Learned which are described. Lessons Learned are summarized in eleven conclusions: a) The dilemma about the difference between an installation in operation and a decommissioning works. A NPP in operation is an installation; a NPP in decommissioning process is an activity, this impact is fundamental from the documentary and controls points of view; b) The flexibility of the time schedule of the project. In opposition with a construction, the time schedule of a decommissioning project it possible to maintain with small delays due to the versatility of parallel tasks; c) The authorization procedure is one of the key points, before and during the process. As a new activity, decommissioning was born without specifics regulation; day by day all the actors realize that is necessary to reflect back together in order to define and establish new standards to regulate the decommissioning processes; d) The prevention of the risks on site is a topic not only related to the Protection Radiation, the conventional risks have more importance in the decommissioning tasks. The issue of the new regulation about it, impact directly in the executions of the works. The training and the information to the workers are the best corrective tool again the risks; e) Some performances or characteristics of the auxiliary systems must be taken in account in the procurement process for decommissioning, namely, the modularity, versatility of the auxiliary systems and the reuse as a way of reducing wastes and save row materials. The radiation protection is the subject concern during all the operations; Important issues of radioprotection as operational radiological history, the characterization of the materials and the environment to prevent the risk, and special care with the internal contamination of the body; g) The very big

The decommissioning information management system

International Nuclear Information System (INIS)

Park, Seung-Kook; Moon, Jei-Kwon

2015-01-01

At the Korea Atomic Energy Research Institute (KAERI), the Korea Research Reactor (KRR-2) and one uranium conversion plant (UCP) were decommissioned. A project was launched in 1997, for the decommissioning of KRR-2 reactor with the goal of completion by 2008. Another project for the decommissioning of the UCP was launched in 2001. The physical dismantling works were started in August 2003 and the entire project was completed by the end of 2010. KAERI has developed a computer information system, named DECOMMIS, for an information management with an increased effectiveness for decommissioning projects and for record keeping for the future decommissioning projects. This decommissioning information system consists of three sub-systems; code management system, data input system (DDIS) and data processing and output system (DDPS). Through the DDIS, the data can be directly inputted at sites to minimize the time gap between the dismantling activities and the evaluation of the data by the project staff. The DDPS provides useful information to the staff for more effective project management and this information includes several fields, such as project progress management, man power management, waste management, and radiation dose control of workers and so on. The DECOMMIS was applied to the decommissioning projects of the KRR-2 and the UCP, and was utilized to give information to the staff for making decisions regarding the progress of projects. It is also to prepare the reference data for the R and D program which is for the development of the decommissioning engineering system tools and to maintain the decommissioning data for the next projects. In this paper, the overall system will be explained and the several examples of its utilization, focused on waste management and manpower control, will be introduced. (author)

Preparation for Ignalina NPP decommissioning

International Nuclear Information System (INIS)

Medeliene, D.

2004-01-01

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

Decommissioning of nuclear facilities

International Nuclear Information System (INIS)

1975-01-01

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

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

International Nuclear Information System (INIS)

Shoji, Kimiaki

2017-01-01

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

Particle-accelerator decommissioning

International Nuclear Information System (INIS)

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

1979-12-01

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

Costing for decommissioning: Continuing NEA engagement

International Nuclear Information System (INIS)

Gillogly, Mari; Weber, Inge; ); Siemann, Michael; )

2017-01-01

On 20-21 September 2016, the International Conference on Financing of Decommissioning of nuclear power plants was held in Stockholm, Sweden. The conference focused on the exchange and sharing of information on current and emerging issues in the financing of nuclear power plant decommissioning and the underlying costs of decommissioning. It aimed at providing a good picture of the variety of financing systems in place to cover the costs of decommissioning of nuclear facilities. As an increasing number of nuclear reactors are expected to be permanently shut-down and enter into the decommissioning phase, the conference highlighted challenges for financing and delivering these decommissioning activities and explored the ways in which they were being addressed. This also included consideration of the implications of potentially under-funded or uncertain decommissioning liabilities. The insights gained in the course of the conference informed future development of work on these issues. The conference addressed a variety of issues from a range of perspectives under three main themes: financing systems - the variety of financing systems in place to provide the financial resources needed for decommissioning, including the arrangements for collecting and developing financial resources during operation and drawing down the assets during decommissioning activities, as well as oversight and reporting issues; decommissioning costing - understanding the cost estimates, quality and interpretation issues in decommissioning costing, the challenges of assurance, comparisons of estimates and actual costs, exploring ways to remedy the current lack of comparable actual cost data, possible benchmarking, etc.; [financial] risk management - effective management of financial assets, risk management strategies, the changing of markets and investment strategies for financial assets, balancing the rates of return and the reduction of risk, implications of the major changes in the energy and

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

Y-12 Plant Decontamination and Decommissioning Program

International Nuclear Information System (INIS)

1992-01-01

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

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

Application of Robotics in Decommissioning and Decontamination - 12536

Energy Technology Data Exchange (ETDEWEB)

Banford, Anthony; Kuo, Jeffrey A. [National Nuclear Laboratory, Risley, Warrington (United Kingdom); Bowen, R.A. [National Nuclear Laboratory, Sellafield, Cumbria (United Kingdom); Szilagyi, Andrew; Kirk, Paula [U.S. Department of Energy, Washington, D.C. (United States)

2012-07-01

Decommissioning and dismantling of nuclear facilities is a significant challenge worldwide and one which is growing in size as more plants reach the end of their operational lives. The strategy chosen for individual projects varies from the hands-on approach with significant manual intervention using traditional demolition equipment at one extreme to bespoke highly engineered robotic solutions at the other. The degree of manual intervention is limited by the hazards and risks involved, and in some plants are unacceptable. Robotic remote engineering is often viewed as more expensive and less reliable than manual approaches, with significant lead times and capital expenditure. However, advances in robotics and automation in other industries offer potential benefits for future decommissioning activities, with the high probability of reducing worker exposure and other safety risks as well as reducing the schedule and costs required to complete these activities. Some nuclear decommissioning tasks and facility environments are so hazardous that they can only be accomplished by exclusive use of robotic and remote intervention. Less hazardous tasks can be accomplished by manual intervention and the use of PPE. However, PPE greatly decreases worker productivity and still exposes the worker to both risk and dose making remote operation preferable to achieve ALARP. Before remote operations can be widely accepted and deployed, there are some economic and technological challenges that must be addressed. These challenges will require long term investment commitments in order for technology to be: - Specifically developed for nuclear applications; - At a sufficient TRL for practical deployment; - Readily available as a COTS. Tremendous opportunities exist to reduce cost and schedule and improve safety in D and D activities through the use of robotic and/or tele-operated systems. - Increasing the level of remote intervention reduces the risk and dose to an operator. Better

Development of the Decontamination and Decommissioning Technology for Nuclear Facilities

International Nuclear Information System (INIS)

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

2010-04-01

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

Decommissioning of U.S. uranium production facilities

Energy Technology Data Exchange (ETDEWEB)

1995-02-01

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

Decommissioning of U.S. uranium production facilities

International Nuclear Information System (INIS)

1995-02-01

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

Nuclear decommissioning

International Nuclear Information System (INIS)

Lawton, H.

1987-01-01

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

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.)

BN-350 nuclear power plant. Regulatory aspects of decommissioning

International Nuclear Information System (INIS)

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

2002-01-01

'General Provisions on Development of the Project on BN-350 Reactor Plant Decommissioning'; 2. Special Technical Conditions 'For Designing of the BN-350 Reactor Facility Decommissioning Project'; 3. Plan of priority measures for BN-350 reactor decommissioning. The documents 1 and 2 were prepared jointly by BN-350, technical institutes, KAEC and various other Kazakhstan Governmental agencies and departments, and they set out: stages in the development of the specifications for the Plan; applicable laws and regulations, and the procedure to follow if the regulations do not cover particular situations or issues; responsibilities of various organizations in the production, agreement and approval process; a recommended detailed list of contents for the Decommissioning Plan (Project); external factors, existing design and planning works which the Plan must take into account; other basic information which needs to be included into the Plan documentation. As the shutdown reactor continues to remain a source of nuclear and radioactive hazard, one have to take measures on putting the reactor to safe status, and thus 'Plan of priority measures for BN-350 reactor decommissioning' was developed. It includes following activities: measures on BN-350 decommissioning Project development; measures on provision of the reactor safety during transition period; measures on sodium drainage and utilization; measures on spent fuel disposal for a long term storage. KAEC was authorized to provide coordination of BN-350 decommissioning work. For example, some duties of KAEC in the Decommissioning Project are as follows: supervision of Project implementation by licensing and engagement of state licensed institutions only for decommissioning works; consideration, approval and authorization of technical documentation of enterprises and institutions implementing the Project within its competency. During the development and implementation of the Project all participants must act according to the laws and

Establishment the code for prediction of waste volume on NPP decommissioning

International Nuclear Information System (INIS)

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

2013-01-01

-2 and developed DEMOS(DEcommissioning MOdeling System) and DEPES(DEcommissioning Process Establish System) using these data. These systems may be able to help to establish decommissioning strategy of nuclear power plant. We tried to apply research reactor data to OPR-1000 which is commercial nuclear power plant. But code for research reactor was not consistent when applying to nuclear power plant. The decommissioning activity of nuclear power plant is basically performed by the unit facility or room. In order to apply research reactor data, each WBS code is needed to apply to the object of each facility. This means that one FAC code may have several WBS codes. However, current codes in DECOMMIS are hard to map WBS code to FAC code one by one, and are specialized to research reactor. So it is difficult to apply to nuclear power plant directly. In order to solve this problem, the common code that can be adapted to commercial nuclear power plant as well as to research reactor is required. It may be inferred from the mapping data in the case of mismatching, or it can be applied with some modifications in the case of similar facility. In this paper, the establishment method of the code which uses the research reactor data in decommissioning project of nuclear power plant was studied. Method for prediction of the decommissioning waste volume was discussed on the basis of the domestic nuclear power plant, OPR-1000. Decommissioning experience is very important to apply to the estimation of decommissioning waste volume. So method for the estimation of decommissioning waste volume using common code that link OPR-1000 and KRR-2 was suggested. This research result will be helpful to reliable estimation of decommissioning waste volume and further estimation of the decommissioning cost and establishment of decommissioning strategies

Application of clearance principles to radioactive waste from the decommissioning of nuclear reactors

International Nuclear Information System (INIS)

Lin Xiaoling; Feng Dingsheng; Dong Yonghe

2010-01-01

The definition of clearance is introduced. The principles and dose criterion of clearance are also clarified. The main radionuclides in radioactivity waste and the radioactivity waste which can be cleared are investigated. The techniques for the measurement of radioactivity waste from the decommissioning of nuclear reactors are summarized. This paper provides the scientific criterion and methods for the management of radioactive waste, and lays the foundation for the treatment of radioactive waste from the decommissioning of nuclear reactor. (authors)

Virtual reality in decommissioning projects: experiences, lessons learned and future plans

International Nuclear Information System (INIS)

Rindahl, G.; Mark, N.K.F.; Meyer, G.

2006-01-01

The work on Virtual Reality (VR) tools for decommissioning planning, dose estimation and work management started at the Norwegian Institute for Energy Technology (IFE) in 1999 in the VR dose project with Japan Nuclear Cycle development institute (JNC), now JAEA. The main aim of this effort has been to help minimize workers' radiation exposure, as well as help to achieve more efficient use of human resources. VR dose is now used in the decommissioning of one of JNC's reactors, the Fugen Nuclear Power Station. This VR decommissioning project has later resulted in a series of projects and applications. In addition to decommissioning, IFE also put great focus on two other branches of VR tools, namely tools for knowledge management, training and education in operating facilities and tools for control room design. During the last years, this work, beginning at different ends, has been converging more and more towards VR technology for use through out the life cycle of a facility. A VR training simulator for a refuelling machine of the Leningrad NPP (LNPP) developed in cooperation with the Russian Research Centre Kurchatov Institute (RRC KI) is now planned to be used in connection with the decommissioning of the three intact reactors at Chernobyl in Ukraine. In this paper we describe experiences from use of VR in decommissioning processes, as well as results from bringing the VR technology initially developed for planned or productive facilities into the decommissioning toolbox. (author)

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

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)

Decommissioning in British Nuclear Fuels plc

International Nuclear Information System (INIS)

Colquhoun, A.

1988-01-01

Decommissioning projects at the BNFL Sellafield site have been selected taking the following into account; the need to gain experience in preparation for the decommissioning of the Magnox reactors and for the post Magnox stage; the need to develop larger scale projects; the need to be cost effective and to foster long term safety. The balance between prompt or delayed decommissioning has to consider operator dose uptake and radioactive waste management. The ten year plan for decommissioning at Sellafield is described briefly. Currently decommissioning is of the fuel pond and decanning plant, the Windscale Pile Chimneys, the coprecipitation plant and the uranium recovery plant. (author)

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

A study on the applicability for primary system decontamination through analysis on NPP decommission technology and international experience

Energy Technology Data Exchange (ETDEWEB)

Song, Jong Soon; Jung, Min Young; Lee, Sang Heon [Chosun University, Gwangju (Korea, Republic of)

2016-03-15

Decontamination is one of the most important technologies for the decommissioning of NPP. The purpose of decontamination is to reduce the Risk of exposure of the decommissioning workers, and to recycle parts of the plant components. Currently, there is a lack of data on the efficiency of the decontamination technologies for decommissioning. In most cases, the local radiation level can be lowered below a regulatory limitation by decontamination. Therefore, more efficient decontamination technology must be continuously developed. This work describes the practical experiences in the United States and the European countries for NPP decommissioning using these decontamination technologies. When the decommissioning of domestic nuclear power plant is planned and implemented, this work will be helpful as a reference of previous cases.

IDMT, Integrated Decommissioning Management Tools

International Nuclear Information System (INIS)

Alemberti, A.; Castagna, P.; Marsiletti, M.; Orlandi, S.; Perasso, L.; Susco, M.

2005-01-01

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

Nuclear decommissioning

International Nuclear Information System (INIS)

Lawton, H.

1987-01-01

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

Decommissioning planning of Swedish nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hedin, Gunnar; Bergh, Niklas [Westinghouse Electric Sweden AB, Vaesteraes (Sweden)

2013-07-01

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

Implementation of 10 CFR 20.1406 through Life Cycle Planning for Decommissioning

International Nuclear Information System (INIS)

O'Donnell, E.; Ott, W.R.

2009-01-01

This paper summarizes a newly released regulatory guide (RG 4.21 'Minimization of Contamination and Radioactive Waste Generation - Life Cycle Planning') issued by the U.S. Nuclear Regulatory Commission (NRC) in June 2008. The purpose of RG 4.21 is to support implementation of 10 CFR 20.1406 'Minimization of Contamination'. That regulation is a portion of NRC's License Termination Rule and it is intended to avoid 'legacy sites', that is, those without financial means to satisfactorily terminate a license. As currently written, 10 CFR 20.1406 applies to all NRC license applications and applications for standard design certifications submitted after August 20, 1997. The regulation requires applicants to address in their application how they will (1) minimize contamination of the facility and environment, (2) minimize waste generation, and (3) facilitate decommissioning. The regulation represents a dramatically different approach to licensing because it mandates consideration of decommissioning before submittal of a license application or design for certification. The guidance in RG 4.21 consists of design considerations drawn from nuclear industry experience and lessons learned from decommissioning. These have been combined to support the development of a contaminant management philosophy. The principles embodied in this philosophy are threefold: (1) prevention of unintended releases; (2) early detection, if there is unintended release of radioactive contamination; and (3) prompt assessment to support a timely and appropriate response. Applying these principles requires the use of sound design, proven engineering practices, conservative radiation protection principles, and attention to operational practices. All of this should be considered in the context of the life cycle of the facility from the early planning stages through the final plans for decommissioning and waste disposal. This guide describes some of the mechanisms that can be employed for facility life

Remote Decommissioning Experiences at Sellafield

International Nuclear Information System (INIS)

Brownridge, M.

2006-01-01

British Nuclear Group has demonstrated through delivery of significant decommissioning projects the ability to effectively deploy innovative remote decommissioning technologies and deliver cost effective solutions. This has been achieved through deployment and development of off-the-shelf technologies and design of bespoke equipment. For example, the worlds first fully remotely operated Brokk was successfully deployed to enable fully remote dismantling, packaging and export of waste during the decommissioning of a pilot reprocessing facility. British Nuclear Group has also successfully implemented remote decommissioning systems to enable the decommissioning of significant challenges, including dismantling of a Caesium Extraction Facility, Windscale Pile Chimney and retrieval of Plutonium Contaminated Material (PCM) from storage cells. The challenge for the future is to continue to innovate through utilization of the supply chain and deploy off-the-shelf technologies which have been demonstrated in other industry sectors, thus reducing implementation schedules, cost and maintenance. (authors)

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)

Funding nuclear-power-plant decommissioning. Final report

International Nuclear Information System (INIS)

Burns, R.E.; Henderson, J.S.; Pollard, W.; Pryor, T.; Chen, Y.M.

1982-10-01

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

Decommissioning Technology Development for Nuclear Research Facilities

International Nuclear Information System (INIS)

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

2007-06-01

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

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

European Decommissioning Academy (EDA). Ready to start

International Nuclear Information System (INIS)

Slugen, Vladimir

2015-01-01

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

The Practice of Cost Estimation for Decommissioning of Nuclear Facilities

International Nuclear Information System (INIS)

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

2015-01-01

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

Measuring and reporting on decommissioning progress

International Nuclear Information System (INIS)

Lange, B.A.

2006-01-01

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

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)

Considerations about the European Decommissioning Academy (EDA)

International Nuclear Information System (INIS)

Slugen, V.; Hinca, R.

2014-01-01

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

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)

A Human Factors Study on an Information Visualization System for Nuclear Power Plants Decommissioning Engineering

Energy Technology Data Exchange (ETDEWEB)

Yang, Chih Wei; Yang, Li Chen [Institute of Nuclear Energy Research, Atomic Energy Council, Longtan (China)

2014-08-15

Most nuclear power plants (NPPs) in the world have an operating life of up to 40 years. The utility should prepare a comprehensive decommissioning plan with purpose to document and to display how decommissioning activities can be safely performed. In the past, most studies related to NPPs decommissioning planning put emphasis on technical issues, little attention have been given to human factors in decommissioning activities. In fact, human factors are a critical factor to successful NPPs decommissioning. NPPs decommissioning will face potential risks. These risks include not only dismantling and moving large equipment but also treating with the radioactive materials. Using information visualization system, such as virtual reality (VR) technology, for staff training can improve decommissioning work safety and economy. Therefore, this study presents a study using VR to solve real world problems in the nuclear plant decommissioning. Then appropriate cases for introducing VR systems are summarized and future prospects are given. This study assesses availability and performance of the work training system by using heuristic evaluation and actual experiment. In the result, block type of radiation visibility was found relatively better both in performance and person's preference than other types. The results presented in this paper illustrate the VR applications a NPP decommissioning perspective.

A Human Factors Study on an Information Visualization System for Nuclear Power Plants Decommissioning Engineering

International Nuclear Information System (INIS)

Yang, Chih Wei; Yang, Li Chen

2014-01-01

Most nuclear power plants (NPPs) in the world have an operating life of up to 40 years. The utility should prepare a comprehensive decommissioning plan with purpose to document and to display how decommissioning activities can be safely performed. In the past, most studies related to NPPs decommissioning planning put emphasis on technical issues, little attention have been given to human factors in decommissioning activities. In fact, human factors are a critical factor to successful NPPs decommissioning. NPPs decommissioning will face potential risks. These risks include not only dismantling and moving large equipment but also treating with the radioactive materials. Using information visualization system, such as virtual reality (VR) technology, for staff training can improve decommissioning work safety and economy. Therefore, this study presents a study using VR to solve real world problems in the nuclear plant decommissioning. Then appropriate cases for introducing VR systems are summarized and future prospects are given. This study assesses availability and performance of the work training system by using heuristic evaluation and actual experiment. In the result, block type of radiation visibility was found relatively better both in performance and person's preference than other types. The results presented in this paper illustrate the VR applications a NPP decommissioning perspective

Decommissioning Plan for European Spallation Source

Directory of Open Access Journals (Sweden)

Ene Daniela

2017-01-01

Full Text Available This paper is a survey of the European Spallation Source initial decommissioning plan developed in compliance with Swedish Regulatory Authority requirements. The report outlines the decommissioning strategy selected and the baseline plan for decommissioning. Types and quantities of radioactive waste estimated to be generated at the final shut-down of the facility are further provided. The paper ends up with the analysis of the key elements of the decommissioning plan and the recommendations to the ESS management team..

License stewardship and other approaches to commercial nuclear power plant decommissioning

International Nuclear Information System (INIS)

Daly, P.T.; Moloney, B.P.

2011-01-01

This paper addresses the challenge of how our industry could arrange itself to deliver decommissioning of Nuclear Power Plants (NPPs) safely, in good time and affordably. There is a growing wealth of experience across the world in safe decommissioning techniques. Most - arguably all - of the techniques required to perform the full decommissioning of NPPs have been demonstrated on full-scale projects. Waste processing and disposal challenges remain in many countries, where the major issues are societal acceptance and political will. Interim storage possibilities have been identified in most countries. In decommissioning, the outstanding significant issues lie now in the domain of affordability and risk management. This paper will illustrate approaches to decommissioning with examples from the US and UK, to explore how the industry can achieve configurations to deliver lower risk and improved affordability for utilities. Different configurations, or models, will be used to illustrate the approaches taken. (orig.)

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.

Nuclear decommissioning and society

International Nuclear Information System (INIS)

Pasqualetti, M.J.

1990-01-01

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

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

Decommissioning Licensing Process of Nuclear Installations in Spain

International Nuclear Information System (INIS)

Correa Sainz, Cristina

2016-01-01

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

The SGHWR decommissioning project-waste strategy

International Nuclear Information System (INIS)

Graham, G.; Napper, M.

1999-01-01

Every facility must reach a stage in the decommissioning process where low-level waste (LLW) becomes the major factor in the decommissioning costs, therefore a cost-effective strategy for dealing with the waste must be sought. This paper describes the waste management strategy process that was carried out at the steam generating heavy water reactor (SGHWR) at Winfrith in Dorset. Obviously, each facility will have its own specific radiological problems, with its own unique fingerprint, which will have to be addressed, and, therefore, the optimum waste management strategy will differ for each facility. However, from the work done at SGHWR, it can be seen that it is possible to formulate a structured approach for dealing with LLW which meets the requirements of all stake holders, is safe, technically acceptable, cost-effective, and, furthermore, is equally applicable to other plants. (author)

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.)

Decommissioning Technology Development for Nuclear Research Facilities

Energy Technology Data Exchange (ETDEWEB)

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

2007-06-15

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

Management of Decommissioning on a Multi-Facility Site

International Nuclear Information System (INIS)

Laraia, Michele; McIntyre, Peter; Visagie, Abrie

2008-01-01

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

The waste management implications of decommissioning

International Nuclear Information System (INIS)

Passant, F.H.

1988-01-01

Decommissioning policy can only be framed in the light of radioactive waste management policy. What can be done with the waste materials, how and when, will determine the overall decommissioning plans and costs. In this paper the waste management options and their costs are reviewed for the decommissioning of the Central Electricity Generating Boards civil nuclear power stations. The paper concentrates on the decommissioning of Magnox stations, although comparative information on waste volumes and costs are given for the AGR programme and a typical PWR. (author)

Decommissioning process of nuclear power plants and legislative base

International Nuclear Information System (INIS)

Bachovsky, J.

2003-01-01

The present paper contains some considerations about applicability and completeness of existing Regulation No. 10 in the field of decommissioning of nuclear power plants. No pretence exists for comprehensiveness, representativeness, or even applicability of these considerations. This paper presents personal views of the author and not official position of Risk Engineering Ltd

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).

Implementation of decommissioning materials conditional clearance process to the OMEGA calculation code

International Nuclear Information System (INIS)

Zachar, Matej; Necas, Vladimir; Daniska, Vladimir

2011-01-01

The activities performed during nuclear installation decommissioning process inevitably lead to the production of large amount of radioactive material to be managed. Significant part of materials has such low radioactivity level that allows them to be released to the environment without any restriction for further use. On the other hand, for materials with radioactivity slightly above the defined unconditional clearance level, there is a possibility to release them conditionally for a specific purpose in accordance with developed scenario assuring that radiation exposure limits for population not to be exceeded. The procedure of managing such decommissioning materials, mentioned above, could lead to recycling and reuse of more solid materials and to save the radioactive waste repository volume. In the paper an a implementation of the process of conditional release to the OMEGA Code is analyzed in details; the Code is used for calculation of decommissioning parameters. The analytical approach in the material parameters assessment, firstly, assumes a definition of radiological limit conditions, based on the evaluation of possible scenarios for conditionally released materials, and their application to appropriate sorter type in existing material and radioactivity flow system. Other calculation procedures with relevant technological or economical parameters, mathematically describing e.g. final radiation monitoring or transport outside the locality, are applied to the OMEGA Code in the next step. Together with limits, new procedures creating independent material stream allow evaluation of conditional material release process during decommissioning. Model calculations evaluating various scenarios with different input parameters and considering conditional release of materials to the environment are performed to verify the implemented methodology. Output parameters and results of the model assessment are presented, discussed and conduced in the final part of the paper

United States nuclear regulatory commission program for inspection of decommissioning nuclear power plants

International Nuclear Information System (INIS)

Harris, P.W.

2001-01-01

The United States Nuclear Regulatory Commission (USNRC or Commission) has been inspecting decommissioning commercial nuclear power plants in the United States (U.S.) since the first such facility permanently shutdown in September 1967. Decommissioning inspections have principally focused on the safe storage and maintenance of spent reactor fuel; occupational radiation exposure; environmental radiological releases; the dismantlement and decontamination of structures, systems, and components identified to contain or potentially contain licensed radioactive material; and the performance of final radiological survey of the site and remaining structures to support termination of the USNRC-issued operating license. Over the last 5 years, USNRC inspection effort in these areas has been assessed and found to provide reasonable confidence that decommissioning can be conducted safely and in accordance with Commission rules and regulations. Recently, the staff has achieved a better understanding of the risks associated with particular decommissioning accidents 1 and plans to apply these insights to amendments proposed to enhance decommissioning rules and regulations. The probabilities, scenarios, and conclusions resulting from this effort are being assessed as to their applicability to the inspection of decommissioning commercial power reactors. (author)

United States nuclear regulatory commission program for inspection of decommissioning nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Harris, P.W. [U.S. Nuclear Regulatory Commission, Washington, DC (United States)

2001-07-01

The United States Nuclear Regulatory Commission (USNRC or Commission) has been inspecting decommissioning commercial nuclear power plants in the United States (U.S.) since the first such facility permanently shutdown in September 1967. Decommissioning inspections have principally focused on the safe storage and maintenance of spent reactor fuel; occupational radiation exposure; environmental radiological releases; the dismantlement and decontamination of structures, systems, and components identified to contain or potentially contain licensed radioactive material; and the performance of final radiological survey of the site and remaining structures to support termination of the USNRC-issued operating license. Over the last 5 years, USNRC inspection effort in these areas has been assessed and found to provide reasonable confidence that decommissioning can be conducted safely and in accordance with Commission rules and regulations. Recently, the staff has achieved a better understanding of the risks associated with particular decommissioning accidents 1 and plans to apply these insights to amendments proposed to enhance decommissioning rules and regulations. The probabilities, scenarios, and conclusions resulting from this effort are being assessed as to their applicability to the inspection of decommissioning commercial power reactors. (author)

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.

The History and Evolution of the IAEA Technical Assistance Programme on Decommissioning and the International Decommissioning Network as its Highest Point

International Nuclear Information System (INIS)

Laraia, M.

2009-01-01

Around the world, but particularly in developing Member States, there are disused nuclear facilities or those approaching the end of their useful lives, for which appropriate decommissioning steps have not been taken, primarily due to limited technical and financial resources or competing priorities. In line with its mission to encourage safe and peaceful applications of nuclear energy, the International Atomic Energy Agency (IAEA) systematically covers the technical, regulatory, radiation protection, planning, management, and economic aspects related to the decommissioning of nuclear installations. The IAEA's overall objective of the decommissioning programme is to assist its Member States in developing the required expertise, equipment, and programmes so that they can decommission their nuclear facilities in a safe, timely, and cost-effective manner. Technical Cooperation (TC) with Member States having limited resources is commonly provided in the form of workshops, expert missions, equipment design and procurement, training courses, fellowships and scientific visits. Key examples are provided in this paper to illustrate the start, evolution and current status of TC activities and typical mechanisms by which such activities are implemented. Many of world's nuclear facilities are small and widely distributed geographically, e.g. ∼300 aging or shut-down research reactors. Requests for assistance to address this issue from Member States exceed the capability of IAEA (and others) to deliver. However, integrating individual initiative into a designed-for-purpose network may compensate for these limitations. A new IAEA initiative amongst organizations from both potential 'donor' and 'recipient' Member States has taken the form of an 'International Decommissioning Network (IDN)'. The objectives of the IDN are to improve the flow of knowledge and experience amongst those engaged in decommissioning, and specifically to enhance the 'user-oriented' focus for all IAEA

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

Asset Decommissioning Risk Metrics for Floating Structures in the Gulf of Mexico.

Science.gov (United States)

Kaiser, Mark J

2015-08-01

Public companies in the United States are required to report standardized values of their proved reserves and asset retirement obligations on an annual basis. When compared, these two measures provide an aggregate indicator of corporate decommissioning risk but, because of their consolidated nature, cannot readily be decomposed at a more granular level. The purpose of this article is to introduce a decommissioning risk metric defined in terms of the ratio of the expected value of an asset's reserves to its expected cost of decommissioning. Asset decommissioning risk (ADR) is more difficult to compute than a consolidated corporate risk measure, but can be used to quantify the decommissioning risk of structures and to perform regional comparisons, and also provides market signals of future decommissioning activity. We formalize two risk metrics for decommissioning and apply the ADR metric to the deepwater Gulf of Mexico (GOM) floater inventory. Deepwater oil and gas structures are expensive to construct, and at the end of their useful life, will be expensive to decommission. The value of proved reserves for the 42 floating structures in the GOM circa January 2013 is estimated to range between $37 and $80 billion for future oil prices between 60 and 120 $/bbl, which is about 10 to 20 times greater than the estimated $4.3 billion to decommission the inventory. Eni's Allegheny and MC Offshore's Jolliet tension leg platforms have ADR metrics less than one and are approaching the end of their useful life. Application of the proposed metrics in the regulatory review of supplemental bonding requirements in the U.S. Outer Continental Shelf is suggested to complement the current suite of financial metrics employed. © 2015 Society for Risk Analysis.

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

Preparatory activities of the Fugen decommissioning

International Nuclear Information System (INIS)

Iguchi, Y.; Tajiri, T.; Kiyota, S.

2004-01-01

The Advanced Thermal Reactor Fugen is a 165 MWe, heavy water moderated, light-water cooled, pressure-tube type reactor. In February 1998, the Atomic Energy Commission of Japan introduced a new policy that development and research of decommissioning of Fugen should be promoted in order to carry out the decommissioning smoothly after the shutdown. The Fugen reactor was shut down definitely in March 2003, and Fugen has been preparing for the project, including necessary development of technologies. The development of decommissioning for Fugen is divided into two areas. One area is the development of unique technology for dismantling special components such as the reactor core and the heavy water system. Another area is the improvement and enhancement of existing technologies. Especially the former area requires effort and comprises development of the reactor dismantlement, tritium decontamination of heavy water system and engineering support systems. The activities are as follows: the density and amount of radioactive nuclides in all equipment or concrete including the reactor core need to be evaluated for the decommissioning. To prepare for decommissioning, analysis, measurement and evaluation of the neutron flux density have been executed during reactor operation. Special dismantling process is necessary for the heavy water system and the reactor that are unique to Fugen. Some studies and tests are going on for the safe dismantling based on existing technologies and their combination. Systems engineering approach is necessary in order to optimize the work load, exposure dose, waste mass and cost by selecting appropriate dismantling process at the planning stage of the decommissioning. For this reason, in order to make a decommissioning plan efficiently, we have been developing an Engineering Support System for decommissioning by adopting new information technologies such as three-dimensional computer-aided design system and virtual reality system. Moreover, the

Decommissioning techniques for research reactors. Final report of a co-ordinated research project 1997-2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-02-01

in this technical publication. Operating experience in real-scale applications, lessons learned, key results in laboratory scale or pilot scale research, and validation of mathematical models, are among the most significant achievements of the CRP and have been highlighted. The objective of this CRP was to promote the exchange of information on the practical experience gained by Member States in decommissioning or operation, maintenance, and refurbishment activities which would be eventually related to the decommissioning of research reactors. Special emphasis was given to the development/adaptation of methods and approaches for optimization of the decommissioning process. The scope of the project included several technical areas of decommissioning rather than focusing on a single aspect of it. It was felt that this format would generate more awareness of the integrated approach to decommissioning. In particular, the scope included the following: design, construction and operational features to assist in final decommissioning; planning for decommissioning, including technical solution assessment; decommissioning strategies and their technological implications; radiological and physical characterization; dismantling technology; decontamination technology; remotely operated equipment; means to reduce occupational exposures; waste generation and management, including clearance of solid materials; restricted and unrestricted site release, including final surveys; costs and financial provisions; safe enclosure of shutdown reactors, including long-term integrity of buildings and systems; decommissioning experience; and ageing management and refurbishment experience.

Decommissioning techniques for research reactors. Final report of a co-ordinated research project 1997-2001

International Nuclear Information System (INIS)

2002-02-01

in this technical publication. Operating experience in real-scale applications, lessons learned, key results in laboratory scale or pilot scale research, and validation of mathematical models, are among the most significant achievements of the CRP and have been highlighted. The objective of this CRP was to promote the exchange of information on the practical experience gained by Member States in decommissioning or operation, maintenance, and refurbishment activities which would be eventually related to the decommissioning of research reactors. Special emphasis was given to the development/adaptation of methods and approaches for optimization of the decommissioning process. The scope of the project included several technical areas of decommissioning rather than focusing on a single aspect of it. It was felt that this format would generate more awareness of the integrated approach to decommissioning. In particular, the scope included the following: design, construction and operational features to assist in final decommissioning; planning for decommissioning, including technical solution assessment; decommissioning strategies and their technological implications; radiological and physical characterization; dismantling technology; decontamination technology; remotely operated equipment; means to reduce occupational exposures; waste generation and management, including clearance of solid materials; restricted and unrestricted site release, including final surveys; costs and financial provisions; safe enclosure of shutdown reactors, including long-term integrity of buildings and systems; decommissioning experience; and ageing management and refurbishment experience

Decommissioning of Facilities. General Safety Requirements. Pt. 6

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-07-15

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

UK reactor decommissioning strategy

International Nuclear Information System (INIS)

Woollam, P.B.

2004-01-01

With the cessation of electricity generation, nuclear power stations move into the next stage of the overall life cycle of the facility: decommissioning. Decommissioning is defined as the process whereby a nuclear facility, at the end of its economic life, is taken permanently out of service and its site made available for other purposes. This involves the implementation of a structured and safe programme for dismantling and clearing the site and making it available for alternative use in the future. In practical terms, 'decommissioning' means the systematic and progressive reduction of hazards to the point where the site could eventually be de-licensed. (author)

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

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

Incorporating design for decommissioning into the layout of nuclear facilities

International Nuclear Information System (INIS)

Collum, B.; Druart, A.

2008-01-01

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

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

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

Constructing Predictive Estimates for Worker Exposure to Radioactivity During Decommissioning: Analysis of Completed Decommissioning Projects - Master Thesis

Energy Technology Data Exchange (ETDEWEB)

Dettmers, Dana Lee; Eide, Steven Arvid

2002-10-01

An analysis of completed decommissioning projects is used to construct predictive estimates for worker exposure to radioactivity during decommissioning activities. The preferred organizational method for the completed decommissioning project data is to divide the data by type of facility, whether decommissioning was performed on part of the facility or the complete facility, and the level of radiation within the facility prior to decommissioning (low, medium, or high). Additional data analysis shows that there is not a downward trend in worker exposure data over time. Also, the use of a standard estimate for worker exposure to radioactivity may be a best estimate for low complete storage, high partial storage, and medium reactor facilities; a conservative estimate for some low level of facility radiation facilities (reactor complete, research complete, pits/ponds, other), medium partial process facilities, and high complete research facilities; and an underestimate for the remaining facilities. Limited data are available to compare different decommissioning alternatives, so the available data are reported and no conclusions can been drawn. It is recommended that all DOE sites and the NRC use a similar method to document worker hours, worker exposure to radiation (person-rem), and standard industrial accidents, injuries, and deaths for all completed decommissioning activities.

Human resource development for decommissioning

International Nuclear Information System (INIS)

Yanagihara, Satoshi

2016-01-01

This paper summarized the features of decommissioning work and the methods how to develop human resources. The general flow of decommissioning includes the following steps: (1) evaluation of facility characteristics, (2) planning, (3) decontamination and disassembly of equipment and structures contaminated with radioactivity, (4) radioactivity measurement, (5) treatment and disposal of radioactive waste, and (6) release from legal restrictions (termination of decommissioning). For this purpose, techniques in various fields are required. In the evaluation of facility characteristics, radiation measurement and calculation of activation amount in the core part are required. In decontamination and dismantling, cutting technology (mechanical cutting, thermal cutting, etc.), decontamination technology, and remote control technology are required. In the nuclear power education in the past, the fields related to design, construction, operation, and maintenance among the plant life cycle were the main parts. Much attention was not payed to decommissioning and the treatment/disposal of radioactive waste in the second half of life cycle. As university education, Hokkaido University and Fukui University have lectures on decommissioning. Furthermore, the education and research for students are proceeding at seven universities, with a focus on common reactors including those of Fukushima Daiichi Power Station. It is a key for promoting decommissioning, to incorporate project management, risk analysis, cost evaluation, and decision making into education, and to foster human resources heading toward challenging problems including social problems. (A.O.)

An outsider's view of decommissioning

International Nuclear Information System (INIS)

Wilkie, T.

1996-01-01

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

Web-Based Training on Reviewing Dose Modeling Aspects of NRC Decommissioning and License Termination Plans

International Nuclear Information System (INIS)

LePoire, D.; Cheng, J.J.; Kamboj, S.; Arnish, J.; Richmond, P.; Chen, S.Y.; Barr, C.; McKenney, C.

2008-01-01

NRC licensees at decommissioning nuclear facilities submit License Termination Plans (LTP) or Decommissioning Plans (DP) to NRC for review and approval. To facilitate a uniform and consistent review of these plans, the NRC developed training for its staff. A live classroom course was first developed in 2005, which targeted specific aspects of the LTP and DP review process related to dose-based compliance demonstrations or modeling. A web-based training (WBT) course was developed in 2006 and 2007 to replace the classroom-based course. The advantage of the WBT is that it will allow for staff training or refreshers at any time, while the advantage of a classroom-based course is that it provides a forum for lively discussion and the sharing of experience of classroom participants. The objective of this course is to train NRC headquarters and regional office staff on how to review sections of a licensee's DP or LTP that pertain to dose modeling. The DP generally refers to the decommissioning of non-reactor facilities, while the LTP refers specifically to the decommissioning of reactors. This review is part of the NRC's licensing process, in which the NRC determines if a licensee has provided a suitable technical basis to support derived concentration guideline levels (DCGLs)1 or dose modeling analyses performed to demonstrate compliance with dose-based license termination rule criteria. This type of training is one component of an organizational management system. These systems 'use a range of practices to identify, create, represent, and distribute knowledge for reuse, awareness and learning'. This is especially important in an organization undergoing rapid change or staff turnover to retain organizational information and processes. NRC is committed to maintaining a dynamic program of training, development, and knowledge transfer to ensure that the NRC acquires and maintains the competencies needed to accomplish its mission. This paper discusses one specific project

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

Intelligent systems for remote decommissioning in hazardous environments

International Nuclear Information System (INIS)

Drotning, W.D.; Bennett, P.C.

1991-01-01

Investigation of advanced technologies utilizing intelligent machines is being supported jointly by the US Department of Energy Offices of Civilian Radioactive Waste Management (DOE/RW) and Environmental Restoration and Waste Management (DOE/EM) for automation of transportation package handling operations at nuclear facilities and of nuclear waste site remediation efforts. Handling operation requirements include identification, location, and health physics operation, followed by bolting/unbolting operations and package disassembly. To accommodate these operations and the diversity of packages, fast model-based automated programming and force feedback control of a robotic cask handling system were developed. In addition, sensor-directed model-based robotic control has been demonstrated for application to hazardous material cleanup. In this application, a graphical interface is used to simulate and evaluate operator-controlled motions and provide telerobotic control of the system. Remote automated handling technologies developed through these programs have the potential to decrease worker exposure and increase efficiency during decommissioning activities in hazardous environments. 8 refs., 4 figs

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)

Decommissioning of nuclear power plants

International Nuclear Information System (INIS)

Vollradt, J.

1977-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-10-15

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

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

International Nuclear Information System (INIS)

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

2016-01-01

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

Laser cutting of thick steel plates with 30 kW fiber laser for nuclear decommissioning

International Nuclear Information System (INIS)

Tamura, Koji

2015-01-01

Laser cutting technologies of the thick steel plates for the nuclear decommissioning were developed with a 30 kW fiber laser. Plates of stainless steel and carbon steel more than 100 mm thick were successfully cut, indicating that this technology is promising for the application to the nuclear decommissioning. (author)

Decommissioning of offshore installations

Energy Technology Data Exchange (ETDEWEB)

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

2010-07-01

New legislation on the handling and storage of radioactive substances came into force 1 January 2011. This version of the report is updated to reflect this new regulation and will therefore in some chapters differ from the Norwegian version (see NEI-NO--1660). The Ministry of the Environment commissioned the Climate and Pollution Agency to examine the environmental impacts associated with the decommissioning of offshore installations (demolition and recycling). This has involved an assessment of the volumes and types of waste material and of decommissioning capacity in Norway now and in the future. This report also presents proposals for measures and instruments to address environmental and other concerns that arise in connection with the decommissioning of offshore installations. At present, Norway has four decommissioning facilities for offshore installations, three of which are currently involved in decommissioning projects. Waste treatment plants of this kind are required to hold permits under the Pollution Control Act. The permit system allows the pollution control authority to tailor the requirements in a specific permit by evaluating conditions and limits for releases of pollutants on a case-to-case basis, and the Act also provides for requirements to be tightened up in line with the development of best available techniques (BAT). The environmental risks posed by decommissioning facilities are much the same as those from process industries and other waste treatment plants that are regulated by means of individual permits. Strict requirements are intended to ensure that environmental and health concerns are taken into account. The review of the four Norwegian decommissioning facilities in connection with this report shows that the degree to which requirements need to be tightened up varies from one facility to another. The permit for the Vats yard is newest and contains the strictest conditions. The Climate and Pollution Agency recommends a number of measures

Decommissioning standards: the radioactive waste impact

International Nuclear Information System (INIS)

Russell, J.L.; Crofford, W.N.

1979-01-01

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

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

International Nuclear Information System (INIS)

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

1986-06-01

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

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)

Program change management during nuclear power plant decommissioning

International Nuclear Information System (INIS)

Bushart, Sean; Kim, Karen; Naughton, Michael

2011-01-01

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

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)

Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

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

The specificity of decommissioning waste for disposal and from different facilities

International Nuclear Information System (INIS)

Jones, J.; Hilden, W.; Pla Campana, E.; )

2005-01-01

Full text: During the decommissioning of nuclear installations significant waste quantities arise, the bulk being material which qualifies for free release or exemption. Only minor quantities have to be submitted to regulatory control and have either to be disposed or can be released, recycled or reused under certain conditions defined by the regulatory body. Actually, it is almost impossible to derive at meaningful data for the expected waste quantities by a simple propagation of the experiences made in other installations. Rather, the quantities and categorisation are significantly installation specific and are determined by a variety of factors such as the plant construction and operation history, the thoroughness of facility characterisation in preparation for decommissioning, the timing of the decommissioning exercise, the kind and scope of the applied waste treatment and conditioning techniques, the possibility for recycling or reusing irradiated or contaminated materials as well as the applicable national legislation. Further international co-operation aiming at the development of waste estimation techniques is required. Moreover, a harmonisation of national legislation might help to compare waste arisings under the various decommissioning exercises

Evaluation of the I. Stage of decommissioning and implementation of the II. Stage of decommissioning of NPP V1

International Nuclear Information System (INIS)

Hrasnova, E.

2015-01-01

In this paper author deals with following aspects: 1. Introduction of company Nuclear and Decommissioning Company, plc; 2. Evaluation of the I. stage of decommissioning and implementation of the II. Stage of decommissioning of NPP V1; (author)

Decommissioning standards

International Nuclear Information System (INIS)

Crofford, W.N.

1980-01-01

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

Flexible solution of linear program with an application to decommissioning planning of nuclear reactor

International Nuclear Information System (INIS)

Shimizu, Yoshiaki

1988-01-01

Due to the simplicity and effectiveness, linear program has been popular in the actual optimization in various fields. In the previous study, the uncertainty involved in the model at the different stage of optimization was dealt with by post-optimizing analysis. But it often becomes insufficient to make a decision how to deal with an uncertain system especially suffering large parameter deviation. Recently in the field of processing systems, it is desired to obtain a flexible solution which can present the counterplan to a deviating system from a practical viewpoint. The scope of this preliminary note presents how to apply a methodology development to obtain the flexible solution of a linear program. For this purpose, a simple example associated with nuclear reactor decommissioning is shown. The problem to maximize a system performance given as an objective function under the constraint of the static behavior of the system is considered, and the flexible solution is determined. In Japan, the decommissioning of commercial nuclear power plants will being in near future, and the study using the retired research reactor JPDR is in progress. The planning of decontamination and the reuse of wastes is taken as the example. (Kako, I.)

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

Implementation of the international structure for decommissioning costing; examples and related IAEA projects - 59313

International Nuclear Information System (INIS)

Daniska, Vladimir; Laraia, Michele; O'Sullivan, Patrick

2012-01-01

In 1999, IAEA, the OECD Nuclear Energy Agency and the European Commission jointly proposed the standardised listing of decommissioning activities [1] to serve as a general basis for presentation of decommissioning costs and for promoting the harmonisation in decommissioning costing. The standardised listing of activities [1] was developed in three hierarchical levels based on analysis of typical decommissioning activities identified in various decommissioning projects. The structure [1] has been currently updated by the same organisations as the International Structure for Decommissioning Costing (ISDC) based on the experience gained over ten years of use of the original standardised listing [2]. First part of the paper presents the revised ISDC. The principle of the three-level original hierarchical structure has been preserved. Re-definition of the content and re-structuring was done to avoid ambiguity and to ensure comprehensiveness. Paper presents two basic approaches for implementation of the ISDC structure in costing - converting the cost data available in specific cost structures, mostly according the work breakdown structures of decommissioning projects into ISDC and implementation of the ISDC as the cost calculation structure. Examples of the second approach are given to show that this approach is feasible and may have several advantages. An ORACLE based costing model with implemented of the extended ISDC for detailed costing and an Excel based costing model for preliminary costing at IAEA for research reactors are given. (authors)

77 FR 41107 - Decommissioning Planning During Operations

Science.gov (United States)

2012-07-12

..., 40, 50, 70, and 72 [NRC-2011-0162] Decommissioning Planning During Operations AGENCY: Nuclear... (DG) 4014, ``Decommissioning Planning During Operations.'' This guide describes a method that the NRC staff considers acceptable for use in complying with the NRC's Decommissioning Planning Rule. The NRC...

76 FR 77431 - Decommissioning Planning During Operations

Science.gov (United States)

2011-12-13

... (DG) DG-4014, ``Decommissioning Planning During Operations.'' This guide describes a method that the.... The draft regulatory guide entitled, ``Decommissioning Planning During Operations,'' is temporarily..., 40, 50, 70, and 72 RIN 3150-AI55 [NRC-2011-0286; NRC-2008-0030] Decommissioning Planning During...

78 FR 663 - Decommissioning Planning During Operations

Science.gov (United States)

2013-01-04

...] Decommissioning Planning During Operations AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide..., ``Decommissioning Planning During Operations.'' The guide describes a method that the NRC staff considers acceptable for use by holders of licenses in complying with the NRC's Decommissioning Planning Rule (DPR) (76 FR...

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)

Nuclear decommissioning planning, execution and international experience

CERN Document Server

2012-01-01

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

Nuclear installations: decommissioning and dismantling

International Nuclear Information System (INIS)

Anon.

1995-01-01

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

Policy and systems analysis for nuclear installation decommissioning

International Nuclear Information System (INIS)

Gu Jiande

1995-01-01

On the basis of introducing into principal concept for nuclear installation decommissioning, form policy, sciences point of view, the author analyses present problems in the policy, the administrative and programme for decommissioning work in China. According to the physical process of decommissioning, the author studied engineering economics, derived method and formulas to estimate decommissioning cost. It is pointed out that basing on optimization principle for radiation protection and analysing cost-benefit for decommissioning engineering, the corresponding policy decision can be made

Decommissioning high-level waste surface facilities

International Nuclear Information System (INIS)

1978-04-01

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

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.

Decommissioning and Decontamination

International Nuclear Information System (INIS)

Massaut, V.

2000-01-01

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

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

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.

Experiences of development of IT support systems for decommissioning of Fugen NPS

International Nuclear Information System (INIS)

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

2017-01-01

Fugen (ATR: Advanced Thermal Reactor) is a 165 MWe, heavy water moderated, light water cooled, pressure-tube type reactor. After ca. 25 year operation, Fugen started decommissioning activities after the final shutdown in 2003 and the decommissioning project will lasts at least until 2034. It is important to execute the decommissioning economically and rationally. Therefore, a systems engineering approach is necessary in order to optimize the workload, exposure dose, waste mass and cost by selecting appropriate dismantling plan at the planning stage of the decommissioning. Because the nuclear facilities have a large number of components and structures, it is necessary to evaluate the process effectively. For this reason, in order to make an efficient decommissioning plan, we have developed an IT support system for decommissioning by adopting new technologies such as 3-dimensional computer aided design (3D-CAD) and virtual reality (VR) named DEXUS. After the approval of the decommissioning plan by the regulatory authority, we have started the decommissioning activities from dismantlement of turbine systems (which is slightly contaminated with radioactive material), designing remote-control systems of reactor removal by laser cutting, development of radioactive waste control system and application including the clearance method, etc. By using IT support systems for these activities more than 10 years, we have been accumulating useful experiences and lessons-learned. The most important thing is the financial optimization. The decommissioning of a plant is non-profit and one-time-only activities, then the plan should be rationalized and the budget should be minimized as much as possible. In other words, we should consider cost-benefit for the computer systems development and implementation. A graded approach should be introduced in this point of view. For example, 3D-CAD data is very useful for the planning of dismantling of highly radioactive materials such as reactor

Development of code system for management of reactor decommissioning (COSMARD), 1

International Nuclear Information System (INIS)

Yanagihara, Satoshi; Ogihara, Hirohito

1994-02-01

The Code System for Management of Reactor Decommissioning (COSMARD) was developed for use in the effective planning and management of reactor decommissioning. The decommissioning management data evaluation facility (DMAF) which is the main part of COSMARD has functions to evaluate various project management data such as manpower needs, radiation exposure of workers, amount of waste arisings necessary for each activity in a project using input data and calculation models consisting of simple arithmetic formulas and unit factors in the database. Using a set of command descriptors developed in COSMARD, work conditions and procedures for decommissioning a nuclear facility are describes as input data. The management data are evaluated by adopting the calculation models, which are placed in the activities at the lowest level of the work breakdown structure (WBS). The management data evaluated by the models are summed up in the ascending direction of WBS to obtain necessary data for the activities at any levels of WBS. In addition, scheduling calculations are conducted to obtain scheduling bar chart and histograms of the management data, on the basis of the work precedence conditions attached at certain activities. This report describes the outline of DMAF and user's manual of the sets of command descriptors. (author)

Radiological Characterisation for Decommissioning of Nuclear Installations - Final Report of the Task Group on Radiological Characterisation and Decommissioning (RCD) of the Working Party on Decommissioning and Dismantling (WPDD) - Final Report, September 2013

International Nuclear Information System (INIS)

Andrieu, Caroline; Olivier Dehaye, Catherine; Tardy, Frederic; Boisserie, Thierry; Desnoyers, Yvon; Thierfeldt, Stefan; Martin, Nieves; Henrik Efraimsson; Haakansson, Lars; Larsson, Arne; Dunlop, Alister A.; Jarman, Sean; Orr, Peter; Abu-Eid, Boby

2013-01-01

Radiological characterisation plays an important role in the decommissioning of nuclear facilities. It is the basis for radiation protection, identification of contamination, assessment of potential risks, cost estimation, planning and implementation of decommissioning and other matters. At all stages of a decommissioning project, adequate radiological characterisation is of crucial importance. The focus of this report is the task of radiological characterisation. The important role and the significance of radiological characterisation become clear when its various objectives are considered, including in particular: - determination of the type, isotopic composition and extent of contamination in structures, systems, components and environmental media; - identification of the nature and extent of remedial actions and decontamination; - supporting planning of decommissioning; - estimation of decommissioning costs. A large number of measurement techniques are available for successful application of radiological characterisation, allowing rapid and comprehensive determination of the activities of most relevant radionuclides. For other radionuclides that are hard to detect, scaling factors can be established that relate their activities to key nuclides. Radiological characterisation is relevant in all phases of the life cycle of a nuclear installation, albeit with different levels of detail and with differing objectives. Basically, the following characterisation phases can be distinguished: pre-operational characterisation; characterisation during operation; characterisation during the transition phase (after final shutdown before initiation of dismantling); characterisation during dismantling (including remediation and decontamination); and characterisation to support the final status survey for site release. The most comprehensive characterisation campaigns are usually carried out during the transition phase in preparation for implementation of dismantling activities

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)

Development of YAG laser cutting system for decommissioning nuclear equipments

International Nuclear Information System (INIS)

Kasai, Takeshi; Nitta, Kazuhiko; Hosoda, Hiroshi.

1995-01-01

Technology of remote controlled cutting and reduction of generative secondary products have been required to the cutting system for decommissioning nuclear equipments. At a point of view that laser cutting technology by use of a Nd:YAG laser is effective, we have developed the laser cutting machine and carried out cutting tests for several stainless steel plates. As a result, the stainless steel plate with a thickness of 22mm could be cut by using an optical fiber which can flexibly propagate laser power, and possibility of application of this laser cutting system to decommissioning nuclear equipments was verified. (author)

Development of YAG laser cutting system for decommissioning nuclear equipments

Energy Technology Data Exchange (ETDEWEB)

Kasai, Takeshi [Fuji Electric Co. Research and Development Ltd., Yokosuka, Kanagawa (Japan); Nitta, Kazuhiko; Hosoda, Hiroshi

1995-07-01

Technology of remote controlled cutting and reduction of generative secondary products have been required to the cutting system for decommissioning nuclear equipments. At a point of view that laser cutting technology by use of a Nd:YAG laser is effective, we have developed the laser cutting machine and carried out cutting tests for several stainless steel plates. As a result, the stainless steel plate with a thickness of 22mm could be cut by using an optical fiber which can flexibly propagate laser power, and possibility of application of this laser cutting system to decommissioning nuclear equipments was verified. (author).

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.)

The NEA Co-operative Programme on Decommissioning. A Decade of Progress

International Nuclear Information System (INIS)

2006-01-01

-operative Programme on Decommissioning, and in particular through the information exchange and review within the TAG, it has become evident that: decommissioning can and has been done in a safe, cost-effective and environmentally friendly manner; current technologies have demonstrated their effectiveness and robust performance in numerous decommissioning activities; and feedback of experience on design, construction and operation is a considerable help for reliable planning, cost evaluation and successful realisation of a decommissioning project. Regarding technical challenges, specific trends have been observed over the last decade. Large contaminated components, for example heat exchangers, steam generators, large tanks etc., that have been segmented in situ into smaller pieces, are increasingly removed 'in one piece' and transported outside the contained area into separated facilities for further processing. Regarding the use of robotics, the CPD observed that industrial robots may have a limited applicability in decommissioning, in contrary to earlier expectations that robotic methods would be extensively used in the dismantling of radioactive components, especially in the high radiation areas in fuel facilities. Experience collected within the CPD also pointed to challenges in the release of alpha contaminated areas, where seepage of contamination into cracks and reappearance of activity in walls previously declared as 'clean' posed specific problems. On the side of organisational trends a movement towards sequential licensing has been observed. This is seen as being advantageous for the management of projects, but also increases the efforts needed for documentation. Other challenges for management raise from company reorganisation, privatisation and budgetary difficulties. The lessons learnt by the participants in the CPD have been helpful for individual projects in making project decisions and in many cases have influenced general project directions. Key examples concern

Waste management considerations in nuclear facility decommissioning

International Nuclear Information System (INIS)

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

1981-01-01

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

Decommissioning: the final folly

International Nuclear Information System (INIS)

Dibdin, T.

1990-01-01

The Second International Seminar on Decommissioning of Nuclear Facilities held in London is reviewed. Various solutions to the reactor decommissioning, including isolating the reactor core, and turning the surrounding buildings into a theme park, are mentioned. The International Atomic Energy Agency identifies three decommissioning stages. Stage 1, defuelling; Stage 2 dismounting of non-radioactive plant with isolation of the nuclear island and Stage 3, return to a 'green field' site. The real debate is about waste management and timing of the stages - whether to defer Stage 3 for a century or so, or even whether to attempt Stage 3 at all. Cost estimation is also discussed. In the United Kingdom, the timing of completion of the deep repository for high level waste will affect the timing. (UK)

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

Lessons learned on stakeholder issues in decommissioning

International Nuclear Information System (INIS)

O'Sullivan, P.; Pescatore, C.

2008-01-01

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

Lessons learned on stakeholder issues in decommissioning

Energy Technology Data Exchange (ETDEWEB)

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

2008-07-01

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

Development of the Decommissioning Project Management System, DECOMMIS

International Nuclear Information System (INIS)

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

2007-03-01

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

The decommissioning of nuclear power stations

International Nuclear Information System (INIS)

Barker, F.

1992-01-01

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

Strategic aspects on waste management in decommissioning of nuclear facilities

International Nuclear Information System (INIS)

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

2017-01-01

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

Development of a Preliminary Decommissioning Plan Following the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations - 13361

International Nuclear Information System (INIS)

Moshonas Cole, Katherine; Dinner, Julia; Grey, Mike; Daniska, Vladimir

2013-01-01

The International Structure for Decommissioning Costing (ISDC) of Nuclear Installations, published by OECD/NEA, IAEA and EC is intended to provide a uniform list of cost items for decommissioning projects and provides a standard format that permits international cost estimates to be compared. Candesco and DECOM have used the ISDC format along with two costing codes, OMEGA and ISDCEX, developed from the ISDC by DECOM, in three projects: the development of a preliminary decommissioning plan for a multi-unit CANDU nuclear power station, updating the preliminary decommissioning cost estimates for a prototype CANDU nuclear power station and benchmarking the cost estimates for CANDU against the cost estimates for other reactor types. It was found that the ISDC format provides a well defined and transparent basis for decommissioning planning and cost estimating that assists in identifying gaps and weaknesses and facilitates the benchmarking against international experience. The use of the ISDC can also help build stakeholder confidence in the reliability of the plans and estimates and the adequacy of decommissioning funding. (authors)

Trojan Decommissioning Project Cost Performance

International Nuclear Information System (INIS)

Michael B. Lackey

2000-01-01

The Trojan nuclear plant (Trojan) was an 1160-MW(electric) four-loop pressurized water reactor located in Rainier, Oregon. The plant was permanently shut down in 1993 after ∼17 yr of commercial operation. The early plant closure was an economic decision. The key factors in the closure analysis were escalation of inspection and repair costs associated with steam generator tube cracking and the projected availability of inexpensive replacement power in the Pacific Northwest region of the United States. Since the plant closure, Portland General Electric (PGE) has been actively engaged in decommissioning. The Trojan Decommissioning Project currently has a forecast at completion of $429.7 million (all costs are in millions of 1997 dollars, unless otherwise noted). The cost performance of the Trojan Decommissioning Project to date is addressed, as well as the tools that are in place to provide cost control through completion of decommissioning

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

International Nuclear Information System (INIS)

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

1994-08-01

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

Sensitivity of physics parameters for establishment of a burned CANDU full-core model for decommissioning waste characterization

International Nuclear Information System (INIS)

Cho, Dong-Keun; Sun, Gwang-Min; Choi, Jongwon; Hwang, Dong-Hyun; Hwang, Tae-Won; Yang, Ho-Yeon; Park, Dong-Hwan

2011-01-01

The sensitivity of parameters related with reactor physics on the source terms of decommissioning wastes from a CANDU reactor was investigated in order to find a viable, simplified burned core model of a Monte Carlo simulation for decommissioning waste characterization. First, a sensitivity study was performed for the level of nuclide consideration in an irradiated fuel and implicit geometry modeling, the effects of side structural components of the core, and structural supporters for reactive devices. The overall effects for computation memory, calculation time, and accuracy were then investigated with a full-core model. From the results, it was revealed that the level of nuclide consideration and geometry homogenization are not important factors when the ratio of macroscopic neutron absorption cross section (MNAC) relative to a total value exceeded 0.95. The most important factor affecting the neutron flux of the pressure tube was shown to be the structural supporters for reactivity devices, showing an 10% difference. Finally, it was concluded that a bundle-average homogeneous model considering a MNAC of 0.95, which is the simplest model in this study, could be a viable approximate model, with about 25% lower computation memory, 40% faster simulation time, and reasonable engineering accuracy compared with a model with an explicit geometry employing an MNAC of 0.99. (author)

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

Planning For Armenian NPP Decommissioning

International Nuclear Information System (INIS)

Ghazaryan, K.; Atoyan, V.; Pyuskyulyan, K.

2008-01-01

Armenian Nuclear Power Plant (ANPP) is situated in Ararat valley near the Metzamor town, approximately 30 km west of Yerevan. The plant consists of two units of WWER-440 Model V-270 that is seismically upgraded version of standard V-230 design. The two units were put in commercial operation in 1976 and 1980 respectively. An earthquake in northern Armenia occurred in December 1988. Although both plants continued to operate after the earthquake, the USSR Council of Ministers ordered the shutdown of both plants for safety reasons. Unit 1 was shutdown in February 1989; Unit 2 was shutdown in March 1989. Shortly after Armenia became an independent republic, the ''energy crisis'' began, leaving the country with virtually no power for five years. The Armenian Government ordered the restart of Unit 2 ANPP. Unit 2 was restarted in November 1995. Unit 1 remains in a long-term shutdown mode. Currently nuclear share in total electricity generation is about 45%. The design life of Unit 2 expires in 2016. As with many older reactors throughout the world the decommissioning issues had not been considered for ANPP at the design stage. The planning activities for ANPP decommissioning were started in 2002 taking into account the IAEA recommendations that early planning will facilitate future decommissioning activities, and the complexity of preparatory and D and D activities as well. (author)

Preliminary plan for decommissioning - repository for spent nuclear fuel

International Nuclear Information System (INIS)

Hallberg, Bengt; Tiberg, Liselotte

2010-06-01

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

In-house developed methodologies and tools for decommissioning projects

International Nuclear Information System (INIS)

Detilleux, Michel; Centner, Baudouin

2007-01-01

, algorithms allow to estimate, on the basis of local inputs, radiological exposures of the operators (collective and individual doses), production of primary, secondary and tertiary waste and their characterization, production of conditioned waste, release of effluents,... and enable the calculation and the presentation (histograms) of the global results for all activities together. An example of application in the frame of the Ignalina decommissioning project is given. (authors)

Simulation studies for quantification of solid waste during decommissioning of nuclear reactors

International Nuclear Information System (INIS)

Sobhan Babu, K.; Gopalakrishnan, R.K.; Gupta, P.C.

2007-01-01

Decommissioning is the final phase in the lifecycle of a nuclear installation and in the area of occupational radiation protection, decommissioning constitute a challenge mainly due to the huge and complex radioactive waste generation. In the context of management and disposal of waste and reuse/recycle of usable materials during decommissioning of reactors, clearance levels for relevant radionuclides are of vital importance. During the process of decommissioning radionuclide-specific clearance levels allow the release of a major quantity of materials to the environment, without regulatory considerations. These levels may also be used to declare the usable materials for reuse or recycle. Assessment of activity concentration in huge quantities of material, for the purpose of clearance, is a challenge in decommissioning process. This paper describes the simulation studies being carried out for the design of a monitoring system for the estimation of activity concentration of the decommissioned materials, especially rubbles/concrete, using mathematical models. Several designs were studied using simulation and it was observed that for the estimation of very low levels of activity concentration, to satisfy the conditions of unrestricted releases, detection system using the principle of Emission Computed Tomography (ECT) is the best suitable method. (author)

The decommissioning plan of the Nuclear Ship MUTSU

International Nuclear Information System (INIS)

Adachi, M.; Matsuo, R.; Fujikawa, S.; Nomura, T.

1995-01-01

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

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

233S Decommissioning Project Environmental Control Plan

International Nuclear Information System (INIS)

Zoric, J.P.

2000-01-01

This Environmental Control Plan is for the 233S Decommissioning activities conducted under the removal action report for the 233S Decontamination and Demolition Project. The purpose of this ECP is to identify environmental requirements for the 233S project. The ECP is a compilation of existing environmental permit conditions, regulatory requirements, and environmental requirements applicable to the specific project or functional activity

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

International Nuclear Information System (INIS)

Umbarger, C.J.

1982-01-01

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

Nuclear decommissioning trusts: A case for convertible bonds

International Nuclear Information System (INIS)

Nichols, R.W.

1992-01-01

Asset-liability management is studied with special emphasis on application of the author's findings to the management of nuclear decommissioning trusts (NDTs). The trust themselves are investment vehicles established to accumulate and build funds to be used to defray future decommissioning costs. Decommissioning, in turn, is the process of dismantling the shell of a nuclear reactor and the surrounding concrete structures, followed by disposal of the radioactive material, the objective being to return the site to a greenfield state i.e. the site is freed up for unrestricted use. Unfortunately, the assets of NDTs are not so easily managed. The liability that the trusts have been established to fund is a highly uncertain moving target for which little historical data is available. This study first develops a framework for selecting portfolios when the investment objective is to invest against a future liability. The challenge then is to build an investment strategy around an uncertain liability, in the presence of taxes and miscellaneous portfolio constraints. The study then explores the viability of convertible bonds for liability-driven investment strategies because of the hybrid debt/equity nature of these instruments

Development of the Decommissioning Project Management System, DECOMMIS

Energy Technology Data Exchange (ETDEWEB)

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

2007-03-15

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

Licensing and decommissioning of nuclear installations in Japan

International Nuclear Information System (INIS)

Shimoyama, Shunji.

1986-01-01

The present report discusses the current status of Japan's licensing system and legislation concerning reactor decommissioning operations. Besides Japan is working to promote worldwide nuclear safety research. However, developing nuclear safety regulations that are uniformely applicable is a difficult job due to big differences in geographical, political, economical, and technological conditions. (CW) [de

Environmental Impact Assessment for the Decommissioning of Nuclear Installations. Vol. 1-3

International Nuclear Information System (INIS)

Bussell, M.J.; Haigh, C.P.; O'Sullivan, P.J.; Mathieson, J.; Braeckeveldt, M.; Deconinck, J.M.; Vidaechea, S.; Beceiro, A.; Ziegenhagen, J.; Biurrun, E.; Codee, H.; Palerm, J.; Bond, A.J.; Warren, L.; Sheate, B.

2001-06-01

This Report presents the results of a study concerned with Environmental Impact Assessment (EIA) for the decommissioning of nuclear installations in European Union Member States and in the Applicant Countries in Central and Eastern Europe. The study, undertaken for the Environment Directorate General of the European Commission, took place between January 2000 and March 2001 under contract number B4-3040/99/136035/MAR/C2 entitled Environmental Impact Assessment for the Decommissioning of nuclear Installations. The study presents an analysis of the current situation in the European Union and in the Applicant Countries, and develops guidance for applying the relevant Directives for EIA to the specific issue of decommissioning nuclear installations although there is also scope for application to other large or controversial projects. The first part of the report (Volume 1) describes the current situation in the EU Member States and Applicant Countries. On the basis of this status, the guidance presented in Volume 2 was developed. Draft versions of these volumes were reviewed by an independent review panel and were then subjected to detailed discussion and debate at a Workshop held in Brussels in January 2001. The Workshop was attended by more than 60 representatives of the nuclear industry, nuclear regulators, public interest groups and EIA experts. Some minor changes were made following the Workshop, a record of which can be found in Volume 3. (author)

Evaluating decommissioning costs for nuclear power plants

International Nuclear Information System (INIS)

MacDonald, R.R.

1980-01-01

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

Document collection of the 28th technical special committee on Fugen decommissioning

International Nuclear Information System (INIS)

Kutsuna, Hideki; Iwai, Hiroki; Mizui, Hiroyuki; Kadowaki, Haruhiko; Nakamura, Yasuyuki

2014-02-01

Fugen Decommissioning Engineering Center, in planning and carrying out our decommissioning technical development, has been establishing “Technical special committee on Fugen decommissioning” which consists of the members well-informed, aiming to make good use of Fugen as a place for technological development which is opened inside and outside the country, as the central point in the energy research and development base making project of Fukui prefecture, and to utilize the outcome in our decommissioning to the technical development effectively. This report compiles presentation materials “The Current Situation of Fugen Decommissioning”, “The Current Status of the Cutting Test toward the Practical Use of Laser Cutting Technology and the Future Plan”, “Study on Radioactive Substance Osmosis for Basis Concrete of Equipment”, “Verification Tests of the Room-Temperature Vacuum Drying and the Evaluation Method of Residual Amount of Heavy Water in the Tritium Removal” and “Report on the FUGEN Efforts of R and D for Decommissioning of the Fukushima Daiichi NPS - Applicability Test of Thermal and Mechanical Cutting Technology for the Dismantlement of the Internal Core of Fukushima Daiichi NPS -”, presented in the 28th Technical special committee on Fugen decommissioning which was held on September 24, 2013. (author)

Optimizing decommissioning strategies

International Nuclear Information System (INIS)

Passant, F.H.

1993-01-01

Many different approaches can be considered for achieving satisfactory decommissioning of nuclear installations. These can embrace several different engineering actions at several stages, with time variations between the stages. Multi-attribute analysis can be used to help in the decision making process and to establish the optimum strategy. It has been used in the Usa and the UK to help in selecting preferred sites for radioactive waste repositories, and also in UK to help with the choice of preferred sites for locating PWR stations, and in selecting optimum decommissioning strategies

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

Scheduling for decommissioning projects

International Nuclear Information System (INIS)

Podmajersky, O.E.

1987-01-01

This paper describes the Project Scheduling system being employed by the Decommissioning Operations Contractor at the Shippingport Station Decommissioning Project (SSDP). Results from the planning system show that the project continues to achieve its cost and schedule goals. An integrated cost and schedule control system (C/SCS) which uses the concept of earned value for measurement of performance was instituted in accordance with DOE orders. The schedule and cost variances generated by the C/SCS system are used to confirm management's assessment of project status. This paper describes the types of schedules and tools used on the SSDP project to plan and monitor the work, and identifies factors that are unique to a decommissioning project that make scheduling critical to the achievement of the project's goals. 1 fig

Decommissioning Study of Oskarshamn NPP

International Nuclear Information System (INIS)

Larsson, Helena; Anunti, Aake; Edelborg, Mathias

2013-06-01

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

Decommissioning study of Forsmark NPP

International Nuclear Information System (INIS)

Anunti, Aake; Larsson, Helena; Edelborg, Mathias

2013-06-01

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

Decommissioning Study of Oskarshamn NPP

Energy Technology Data Exchange (ETDEWEB)

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

2013-06-15

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

Decommissioning study of Forsmark NPP

Energy Technology Data Exchange (ETDEWEB)

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

2013-06-15

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

Decommissioning and dismantling of the Rossendorf Isotope Production

International Nuclear Information System (INIS)

Grahnert, Thomas

2016-01-01

After just over 40 years of production operation 2000, the operation of the Rossendorf Isotope Production was finally stopped. In the last few years of production already sections of the Rossendorf Isotope Production have been decommissioned. With the end of the isotope production the decommissioning of the entire complex started. In the two-part report, the decommissioning and dismantling of the Rossendorf Isotope production is presented. In part 1 (atw 5/2016) mainly the authorisation procedures and the realised decommissioning concept are presented. Part 2 (atw 6/2016) deals with special selected aspects of the implementation of the decommissioning programme.

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

Influence of accounting concepts and regulatory rules on the funding of power reactor decommissioning costs

International Nuclear Information System (INIS)

Ferguson, J.S.

1985-01-01

Under normal circumstances, an evaluation of nuclear plant decommissioning costs by an engineering analyst will not produce the same results as an evaluation by a financial analyst. These analysts should understand evaluations based on each other's bases to ensure that their evaluation techniques are appropriate for the circumstances. The intent of this discussion is to enhance that understanding by describing the accounting and regulatory framework that is applicable to the decommissioning costs of U.S. nuclear power plants, and by explaining why evaluations of decommissioning costs prepared by engineering analysts often look different from evaluations prepared by financial analysts. Of major importance are the financial implications of several methods of funding the decommissioning costs. Since many owners of nuclear plants are subject to revenue rate regulation, financial implications often translate directly to regulatory implications

Investigation Study on Gamma Ray Imaging Technology for Nuclear Power Plant Decommissioning

Energy Technology Data Exchange (ETDEWEB)

Lee, Sang Guk; Jeong, Woo Tae [Machinery and Materials Laboratory, Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

2014-10-15

The gamma ray imaging system provides an estimated dose-rate of the source at 30 cm above. The gamma detector is a terbium activated glass scintillator. The system is capable of producing a color two dimensional image of a radiation field superimposed on a black and white visual image. The system used in US power plants consists of a portable sensor head that contains both gamma ray and visual imaging systems and a portable control computer. The gamma ray imaging system has been successfully used as an ALARA tool for identifying source terms and determining the adequacy of existing shielding. Because the control system can be positioned away from the camera, the radiation exposure to personnel can be reduced without extensive shielding requirements. The gamma ray imaging system has been used to date in the decommissioning of Maine Yankee, Big Rock point,Trojan, San Onofre1, and Millstone 1. The equipment has also been used at normal refueling outages at a number of commercial nuclear power plants and at several Department of Energy Decommissioning sites. This paper is intended to review the applicability of gamma ray imaging system as decommissioning tool. In order to review the actual applicability, we are going to introduce applications for US power plants.

Decommissioning activities for Salaspils research reactor - 59055

International Nuclear Information System (INIS)

Abramenkovs, A.; Malnacs, J.

2012-01-01

In May 1995, the Latvian government decided to shut down the Salaspils Research Reactor (SRR). The reactor is out of operation since July 1998. A conceptual study for the decommissioning of SRR has been carried out by Noell-KRC-Energie- und Umwelttechnik GmbH at 1998-1999. The Latvian government decided to start the direct dismantling to 'green field' in October 26, 1999. The upgrade of decommissioning and dismantling plan was performed in 2003-2004 years, which change the main goal of decommissioning to the 'brown field'. The paper deals with the SRR decommissioning experience during 1999-2010. The main decommissioning stages are discussed including spent fuel and radioactive wastes management. The legal aspects and procedures for decommissioning of SRR are described in the paper. It was found, that the involvement of stakeholders at the early stages significantly promotes the decommissioning of nuclear facility. Radioactive waste management's main efforts were devoted to collecting and conditioning of 'historical' radioactive wastes from different storages outside and inside of reactor hall. All radioactive materials (more than 96 tons) were conditioned in concrete containers for disposal in the radioactive wastes repository 'Radons' at Baldone site. The dismantling of contaminated and activated components of SRR systems is discussed in paper. The cementation of dismantled radioactive wastes in concrete containers is discussed. Infrastructure of SRR, including personal protective and radiation measurement equipment, for decommissioning purposes was upgraded significantly. Additional attention was devoted to the free release measurement's technique. The certified laboratory was installed for supporting of all decommissioning activities. All non-radioactive equipments and materials outside of reactor buildings were released for clearance and dismantled for reusing or conventional disposing. Weakly contaminated materials from reactor hall were collected

The development of the strategy and plan for the decommissioning and abandonment of 36'' offshore oil export pipelines

Energy Technology Data Exchange (ETDEWEB)

Matthews, Richard J. [PIMS of London Ltd, London, (United Kingdom); Galvez Reyes, Marco Antonio [PEMEX Refinacion, Veracruz, (Mexico)

2010-07-01

The decommissioning and abandonment of platforms and pipelines are big challenges for the pipeline industry. This paper presents a review of the decommissioning and abandonment processes based on a study case, the Rabon Grande pipeline system. First, the applicable international codes, standards and regulations associated with the decommissioning of pipelines are discussed. Next, this paper presents a review of the decommissioning and abandonment options and considerations available for the study case. The Rabon Grande pipeline system, which was shut down and isolated in 1990 pending decommissioning, is used as an example of applying decommissioning and abandonment best practice and establishing a realistic scope of work. A decommissioning plan is developed in light of these previous studies, followed by an environmental impact assessment. It is found that contrary to what was done in the case of the Rabon Grande pipeline, when a pipeline is to be shutdown, the best practice methodology is to temporally or fully decommission the system as soon as possible.

The Importance of Experience Based Decommissioning Planning

International Nuclear Information System (INIS)

Larsson, Arne; Lidar, Per; Hedin, Gunnar; Bergh, Niklas

2016-01-01

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

Development of telerobotic systems for reactor decommissioning, (3)

International Nuclear Information System (INIS)

Usui, Hozumi; Fujii, Yoshio; Shinohara, Yoshikuni

1991-01-01

This paper describes the telerobotic system for reactor decommissioning in the scope of engineering demonstration of dismantling radioactive reactor internals of an experimental boiling water power reactor JPDR. The total system consists of a telerobotic manipulator system equipped with a multi-functional amphibious slave manipulator with a load capacity of 25 daN, a chain-driven transport system, and a computer-assisted monitoring and control system. Preceding to the application of the telerobotic system to actual dismantling operation, a mockup test was performed of dismantling the simulated reactor internals of actual-size by the method of underwater plasma arc cutting in order to study the performance of the telerobotic system in a realistic environment. The system was then successfully applied to dismantling the actual reactor internals according to the JPDR decommissioning program. (author)

Technical and cost aspects of radioactive wastes from decommissioning

International Nuclear Information System (INIS)

Claes, J.; Menon, S.

2001-01-01

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

Progress of JPDR decommissioning project

International Nuclear Information System (INIS)

Kiyota, M.; Yanagihara, S.

1995-01-01

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

Prospective needs for decommissioning commercial nuclear facilities

International Nuclear Information System (INIS)

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

1992-01-01

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

Decommissioning considerations at a time of nuclear renaissance

International Nuclear Information System (INIS)

Devgun, Jas S.

2007-01-01

At a time of renaissance in the nuclear power industry, when it is estimated that anywhere between 60 to 130 new power reactors may be built worldwide over the next 15 years, why should we focus on decommissioning? Yet it is precisely the time to examine what decommissioning considerations should be taken into account as the industry proceeds with developing final designs for new reactors and the construction on the new build begins. One of the lessons learned from decommissioning of existing reactors has been that decommissioning was not given much thought when these reactors were designed three or four decades ago. Even though decommissioning may be sixty years down the road from the time they go on line, eventually all reactors will be decommissioned. It is only prudent that new designs be optimized for eventual decommissioning, along with the other major considerations. The overall objective in this regard is that when the time comes for decommissioning, it can be completed in shorter time frames, with minimum generation of radioactive waste, and with better radiological safety. This will ensure that the tail end costs of the power reactors are manageable and that the public confidence in the nuclear power is sustained through the renaissance and beyond. (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)

2007-02-15

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

Experience Practices on Decontamination Activity in NPP Decommissioning

Energy Technology Data Exchange (ETDEWEB)

Yoon, Suk Bon; Kim, Jeongju; Sohn, Wook [Korea Hydro and Nuclear Power Co., Daejeon (Korea, Republic of)

2016-10-15

Decommissioning of a nuclear power plant (NPP) involves various technical and administrative activities for a utility to terminate its license, which allows the plant site to be released from the regulatory control (site release). Decontamination activity in NPP decommissioning is one of the main technical activities to be performed during the decommissioning. The decontamination at decommissioning sites is usually performed due to several reasons such as reducing personnel dose and disposal costs, and cleanup to meet license termination requirements by using physical or chemical removal techniques proven through the previous experience practices. This paper introduces the best and worst practices for the decontamination activities collected from the decommissioning operational experiences through the implementation of nuclear decommissioning projects around the world. Review of the experiences of decontamination shows that it is important to conduct an advanced planning for optimized implementation of decontamination taking into considering site specific conditions such as operating time, reactor type, system, and so on. Also, a review of newer decontamination methods is necessary to safely and economically decommission the nuclear facility.

Decommissioning of nuclear power plants: policies, strategies and costs

International Nuclear Information System (INIS)

Lund, I.

2004-01-01

As many nuclear power plants will reach the end of their lifetime during the next 20 years or so, decommissioning is an increasingly important topic for governments, regulators and industries. From a governmental viewpoint, particularly in a deregulated market, one essential aspect is to ensure that money for the decommissioning of nuclear installations will be available at the time it is needed, and that no 'stranded' liabilities will be left to be financed by the taxpayers rather than by the electricity consumers. For this reason, there is governmental interest in understanding decommissioning costs, and in periodically reviewing decommissioning cost estimates from nuclear installation owners. Robust cost estimates are key elements in designing and implementing a coherent and comprehensive national decommissioning policy including the legal and regulatory bases for the collection, saving and use of decommissioning funds. From the industry viewpoint, it is essential to assess and monitor decommissioning costs in order to develop a coherent decommissioning strategy that reflects national policy and assures worker and public safety, whilst also being cost effective. For these reasons, nuclear power plant owners are interested in understanding decommissioning costs as best as possible and in identifying major cost drivers, whether they be policy, strategy or 'physical' in nature. National policy considerations will guide the development of national regulations that are relevant for decommissioning activities. Following these policies and regulations, industrial managers responsible for decommissioning activities will develop strategies which best suit their needs, while appropriately meeting all government requirements. Decommissioning costs will be determined by technical and economic conditions, as well as by the strategy adopted. Against this backdrop, the study analyses the relationships among decommissioning policy as developed by governments, decommissioning

Research reactor utilization, safety, decommissioning, fuel and waste management. Posters of an international conference

International Nuclear Information System (INIS)

2005-01-01

For more than 50 years research reactors have played an important role in the development of nuclear science and technology. They have made significant contributions to a large number of disciplines as well as to the educational and research programmes of about 70 countries world wide. About 675 research reactors have been built to date, of which some 278 are now operating in 59 countries (86 of them in 38 developing Member States). Altogether over 13,000 reactor-years of cumulative operational experience has been gained during this remarkable period. The objective of this conference was to foster the exchange of information on current research reactor concerns related to safety, operation, utilization, decommissioning and to provide a forum for reactor operators, designers, managers, users and regulators to share experience, exchange opinions and to discuss options and priorities. The topical areas covered were: a) Utilization, including new trends and directions for utilization of research reactors. Effective management of research reactors and associated facilities. Engineering considerations and experience related to refurbishment and modifications. Strategic planning and marketing. Classical applications (nuclear activation analysis, isotope production, neutron beam applications, industrial irradiations, medical applications). Training for operators. Educational programmes using a reactor. Current developments in design and fabrication of experimental facilities. Irradiation facilities. Projects for regional uses of facilities. Core management and calculation tools. Future trends for reactors. Use of simulators for training and educational programmes. b) Safety, including experience with the preparation and review of safety analysis reports. Human factors in safety analysis. Management of extended shutdown periods. Modifications: safety analysis, regulatory aspects, commissioning programmes. Engineering safety features. Safety culture. Safety peer reviews and

Generic Overview of the Status of Characterization Surveys and Guidance for Decommissioning

International Nuclear Information System (INIS)

Abu Eid, Rateb Boby

2012-01-01

This paper presents an overview of several topical areas pertaining to characterization and survey for decommissioning, including: U.S. NRC regulatory requirements for decommissioning and survey; a description of the decommissioning processes particularly role of characterization and survey; characterization survey types and NRC categorization of decommissioning groups; status of U.S. characterization survey guidance; and overview of key characterization and survey Issues. The specific topical areas are briefly discussed below: - The paper addresses the U.S. NRC requirements under 10 CFR Part 20, Subpart E - 'Radiological Criteria for License Termination', and final status surveys requirements under 10 CFR 20.1501(a). Other requirements under 10CFR Parts 50.75, 50.82, 51.53, and 51.95) as well as, reporting and record keeping for decommissioning planning will be outlined. The paper also discusses NRC general decommissioning process for materials and fuel cycle facilities, as well as, for power reactor facilities. - Strategy and planning for decommissioning using the data quality objectives (DQO) approach and its seven step process will be presented in some detail. - The US NRC 'Surveys and Site Investigation Process' as described in NUREG 1757 and categorization of 'Decommissioning Groups' in the context of characterization and survey needs will be addressed. - The paper briefly outlines methodologies, approaches, and status of U.S. multi-agency key guidance documents such as MARSSIM (NUREG-1575), MARSAME (NUREG- 1575, Supp.1), and more recently, the NRC Subsurface Guidance NUREG/CR 7021. - Dose modeling and software development/update in support of radiological survey and characterization for derivation of derived concentration guideline levels. - Lessons Learned from Regulatory 'Reviews of Survey Plans' particularly attributes of survey plans, common survey issues, and key aspects for decommissioning success are discussed in the paper. (author)

The brief introduction to decommissioning of nuclear reactor projects

International Nuclear Information System (INIS)

Zhao Shixin

1991-01-01

The basic concept and procedure of the decommissioning of nuclear reactor project and the three stages of decommissioning defined by IAEA are introduced. The main work of decommissioning of nuclear reactor are as following: (1) the documentary and technological preparation; (2) the site preparation of decommissioning project; (3) the dismantling of equipment piping system and components; (4) the decontamination of the piping system before and after decomminssioning; (5) the storage and disposal of the operational and decommissioning waste

The brief introduction to decommissioning of nuclear reactor projects

Energy Technology Data Exchange (ETDEWEB)

Shixin, Zhao [Beijing Inst. of Nuclear Engineering (China)

1991-08-01

The basic concept and procedure of the decommissioning of nuclear reactor project and the three stages of decommissioning defined by IAEA are introduced. The main work of decommissioning of nuclear reactor are as following: (1) the documentary and technological preparation; (2) the site preparation of decommissioning project; (3) the dismantling of equipment piping system and components; (4) the decontamination of the piping system before and after decomminssioning; (5) the storage and disposal of the operational and decommissioning waste.

Intelligent systems for remote decommissioning in hazardous environments

International Nuclear Information System (INIS)

Drotning, W.D.; Bennett, P.C.

1991-01-01

This paper reports on investigation of advanced handling technologies utilizing intelligent machines being supported jointly by the U.S. Department of Energy Offices of Civilian Radioactive Waste Management and Environmental Restoration and Waste Management for automation of transportation package handling operations at nuclear facilities and of nuclear waste site remediation efforts. Handling operation requirements include identification, location, and health physics operations, followed by bolting/unbolting operations and package disassembly. To accommodate these operations and the diversity of packages, fast model-based automated programming and force feedback control of a robotic control has been demonstrated for application to hazardous material cleanup. In this application, a graphical interface is used to simulate and evaluate operator-controlled motions and provide telerobotic control of the system. Remote automated handling technologies developed through these programs have the potential to decrease worker exposure and increase efficiency during decommissioning activities in hazardous environments

Methodology and technology of decommissioning nuclear facilities

International Nuclear Information System (INIS)

1986-01-01

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

Radiological Impacts Assessment during Normal Decommissioning Operation for EU-APR

Energy Technology Data Exchange (ETDEWEB)

Hwang, Do Hyun; Lee, Keun Sung [KHNP CRI, Daejeon (Korea, Republic of); Lee, ChongHui [KEPCO Engineering and Construction, Gimcheon (Korea, Republic of)

2016-10-15

In this paper, radiological impacts on human beings during normal execution of the decommissioning operations from the current standard design of EU-APR which has been modified and improved from its original design of APR1400 to comply with EUR, are evaluated. Decommissioning is the final phase in the life cycle of a nuclear installation, covering all activities from shutdown and removal of fissile material to environmental restoration of the site. According to article 5.4 specified in chapter 2.20 of European Utility Requirements (EUR), all relevant radiological impacts on human being should be considered during the environmental assessment of decommissioning, including external exposure from direct radiation of plant and other radiation sources, and internal exposure due to inhalation and ingestion. In this paper, radiological impacts on human beings during normal circumstances of the decommissioning operation were evaluated from the current standard design of EU-APR based on the simple transport model and practical generic methodology for assessing the radiological impact provided by IAEA. The results of dose assessment fulfilled the dose limit for all scenarios.

Platform decommissioning. Environmental challenges and practical solutions

International Nuclear Information System (INIS)

Kvalvik, Inge

1998-01-01

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

Radiation protection aspects of dismantling and decommissioning of Uranium Mining of Andujar (Spain)

International Nuclear Information System (INIS)

Ortiz Ramis, M.T.; Garcia-Bermejo Fernandez, R.; Martin Palomo, N.

1995-01-01

This study analyzes the radiation protection aspects during the decommissioning and dismantling of uranium mining in Andujar (Spain). The application during dismantling's mining, the transfer factor of natural radioactive isotopes and the application during the sterile movements are presented

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

A study of a decommissioning activities classification structure for decommissioning of the project management of a nuclear power plant

International Nuclear Information System (INIS)

Park, Hee Seong; Park, Seung Kook; Jin, Hyung Gon; Song, Chan Ho; Ha, Jei Hyun; Moon, Jei kwon

2015-01-01

Decommissioning activities and requirements that was established in the planning stage should be organized systematically in the course of dismantling the NPP. The work breakdown structure is essential to ensuring that all the project scope is identified, estimated and executed. The project manager needs to ensure that a WBS is established early in the project and maintained throughout the project life cycle. A project management system is ongoing under the circumstance of having no experience dismantling the NPP. The system related to the NPP decommissioning should have technical criteria as well as regulatory requirements in the full scale of decommissioning stage. In the dismantling stage, decommissioning plan document should include the results of radiation/radioactivity characterization, evaluation of the amount of dismantled waste, calculation of the expose dose rate, evaluation of decommissioning cost and schedule after shutdown

A study of a decommissioning activities classification structure for decommissioning of the project management of a nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

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

2015-05-15

Decommissioning activities and requirements that was established in the planning stage should be organized systematically in the course of dismantling the NPP. The work breakdown structure is essential to ensuring that all the project scope is identified, estimated and executed. The project manager needs to ensure that a WBS is established early in the project and maintained throughout the project life cycle. A project management system is ongoing under the circumstance of having no experience dismantling the NPP. The system related to the NPP decommissioning should have technical criteria as well as regulatory requirements in the full scale of decommissioning stage. In the dismantling stage, decommissioning plan document should include the results of radiation/radioactivity characterization, evaluation of the amount of dismantled waste, calculation of the expose dose rate, evaluation of decommissioning cost and schedule after shutdown.

78 FR 64028 - Decommissioning of Nuclear Power Reactors

Science.gov (United States)

2013-10-25

... NUCLEAR REGULATORY COMMISSION [NRC-2012-0035] Decommissioning of Nuclear Power Reactors AGENCY... the NRC's regulations relating to the decommissioning process for nuclear power reactors. The revision... Commission (NRC) is issuing Revision 1 of regulatory guide (RG) 1.184 ``Decommissioning of Nuclear Power...

Development of a Decommissioning Certificate Program

International Nuclear Information System (INIS)

Morton, M. R.

1999-01-01

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

The Importance of Decommissioning Planning for African Countries

International Nuclear Information System (INIS)

Reisenweaver, D.W.

2011-01-01

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

Decommissioning of excess nuclear facilities

International Nuclear Information System (INIS)

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

1978-01-01

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

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.

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 experience at UKAEA Winfrith

International Nuclear Information System (INIS)

Miller, K.

2008-01-01

The Winfrith Site was used for development of nuclear reactors, particularly the 100 MW(e) Steam Generating Heavy Water Reactor (SGHWR) and the 30 MW gas-cooled DRAGON reactor. Following the closure of the SGHWR reactor in 1990 the site has run down nuclear operations by removing from site most of the high level hazards from both reactors and then commencing the decommissioning of major items of plant and other site facilities. After the SGHWR was shut down, UKAEA prepared a decommissioning programme for this plant comprising a multistage process, each to be subjected to a competitive tendering operation. The recently completed Stage 1 decommissioning contract, awarded to Nuvia in 2005, involved decommissioning and removal of all the ancillary plant and equipment in the secondary containment and non-containment areas of the plant. The decommissioning processes involved with these large and heavy plant items will be described with some emphasis of the establishment of multiple work-fronts for the production, recovery, treatment and disposal of mainly tritium contaminated waste arising from its contact with the direct cycle reactor coolant. The means of size reduction of a variety of large, heavy and complex items of plant made from a range of materials will also be described with some emphasis on the control of fumes during hot cutting operations. Over the past 18 years Nuvia has gained vast experience with decommissioning operations on redundant nuclear plant and facilities on the Winfrith Site and has been extremely successful in meeting its contractual obligations in a safe and efficient manner. The final section of the paper will dwell upon the key issues that have made a difference in achieving these objectives for the benefit of others involved in similar operations. (author)

BNFL decommissioning strategy and techniques

International Nuclear Information System (INIS)

Taylor, D.

2002-01-01

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

Waste management strategy for cost effective and environmentally friendly NPP decommissioning

Energy Technology Data Exchange (ETDEWEB)

Per Lidar; Arne Larsson [Studsvik Nuclear AB (ndcon partner), Nykoping (Sweden); Niklas Bergh; Gunnar Hedin [Westinghouse Electric Sweden AB (ndcon partner), Vasteraas (Sweden)

2013-07-01

Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named ndcon to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

Waste management strategy for cost effective and environmentally friendly NPP decommissioning

International Nuclear Information System (INIS)

Per Lidar; Arne Larsson; Niklas Bergh; Gunnar Hedin

2013-01-01

Decommissioning of nuclear power plants generates large volumes of radioactive or potentially radioactive waste. The proper management of the dismantling waste plays an important role for the time needed for the dismantling phase and thus is critical to the decommissioning cost. An efficient and thorough process for inventorying, characterization and categorization of the waste provides a sound basis for the planning process. As part of comprehensive decommissioning studies for Nordic NPPs, Westinghouse has developed the decommissioning inventories that have been used for estimations of the duration of specific work packages and the corresponding costs. As part of creating the design basis for a national repository for decommissioning waste, the total production of different categories of waste packages has also been predicted. Studsvik has developed a risk based concept for categorization and handling of the generated waste using six different categories with a span from extremely small risk for radiological contamination to high level waste. The two companies have recently joined their skills in the area of decommissioning on selected market in a consortium named ndcon to further strengthen the proposed process. Depending on the risk for radiological contamination or the radiological properties and other properties of importance for waste management, treatment routes are proposed with well-defined and proven methods for on-site or off-site treatment, activity determination and conditioning. The system is based on a graded approach philosophy aiming for high confidence and sustainability, aiming for re-use and recycling where found applicable. The objective is to establish a process where all dismantled material has a pre-determined treatment route. These routes should through measurements, categorization, treatment, conditioning, intermediate storage and final disposal be designed to provide a steady, un-disturbed flow of material to avoid interruptions. Bottle

Treatment of Decommissioning Combustible Wastes with Incineration Technology

Energy Technology Data Exchange (ETDEWEB)

Min, B. Y. Min; Yang, D. S.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

The aim of the paper is current status of management for the decommissioning radioactive combustible and metal waste in KAERI. In Korea, two decommissioning projects were carried out for nuclear research facilities (KRR-1 and KRR-2) and a uranium conversion plant (UCP). Through the two decommissioning projects, lots of decommissioning wastes were generated. Decommissioning waste can be divided into radioactive waste and releasable waste. The negative pressure of the incineration chamber remained constant within the specified range. Off-gas flow and temperature were maintained constant or within the desired range. The measures gases and particulate materials in the stack were considerably below the regulatory limits. The achieved average volume reduction ratio during facility operation is about 1/65.

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

Decommissioning Challenges, strategy and programme development

Energy Technology Data Exchange (ETDEWEB)

Potier, J.M.; Laraie, M.; Dinner, P. [Waste Technology Section, Dept. of Nuclear Energy, International Atomic Energy Agency (IAEA), Vienna (Austria); Pescatore, C.; O' Sullivan [Organisation for Economic Co-Operation and Development, Nuclear Energy Agency, 75 - Paris (France); Dupuis, M.C. [Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA), 92 - Chatenay Malabry (France); Szilagyi, A.; Collazo, Y.; Negin, Ch. [U.S. Department of Energy, Washington, DC (United States)

2008-11-15

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

Platform decommissioning: Socio-economic impacts

International Nuclear Information System (INIS)

Scheelhaase, Janina D.

1998-01-01

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

Approaches to estimating decommissioning costs

International Nuclear Information System (INIS)

Smith, R.I.

1990-07-01

The chronological development of methodology for estimating the cost of nuclear reactor power station decommissioning is traced from the mid-1970s through 1990. Three techniques for developing decommissioning cost estimates are described. The two viable techniques are compared by examining estimates developed for the same nuclear power station using both methods. The comparison shows that the differences between the estimates are due largely to differing assumptions regarding the size of the utility and operating contractor overhead staffs. It is concluded that the two methods provide bounding estimates on a range of manageable costs, and provide reasonable bases for the utility rate adjustments necessary to pay for future decommissioning costs. 6 refs

Contingency Cost estimation for Research reactor Decommissioning

International Nuclear Information System (INIS)

Jin, Hyung Gon; Hong, Yun Jeong

2016-01-01

There are many types of cost items in decommissioning cost estimation, however, contingencies are for unforeseen elements of cost within the defined project scope. Regulatory body wants to reasonable quantification for this issue. Many countries have adopted the breakdown of activity dependent and period-dependent costs to structure their estimates. Period-dependent costs could be broken down into defined time frames to reduce overall uncertainties. Several countries apply this notion by having different contingency factors for different phases of the project. This study is a compilation of contingency cost of research reactor and for each country. Simulation techniques using TRIM, MATLAB, and PSpice can be useful tools for designing detector channels. Thus far TRIM, MATLAB and PSpice have been used to calculate the detector current output pulse for SiC semiconductor detectors and to model the pulses that propagate through potential detector channels. This model is useful for optimizing the detector and the resolution for application to neutron monitoring in the Generation IV power reactors

Contingency Cost estimation for Research reactor Decommissioning

Energy Technology Data Exchange (ETDEWEB)

Jin, Hyung Gon; Hong, Yun Jeong [KAERI, Daejeon (Korea, Republic of)

2016-05-15

There are many types of cost items in decommissioning cost estimation, however, contingencies are for unforeseen elements of cost within the defined project scope. Regulatory body wants to reasonable quantification for this issue. Many countries have adopted the breakdown of activity dependent and period-dependent costs to structure their estimates. Period-dependent costs could be broken down into defined time frames to reduce overall uncertainties. Several countries apply this notion by having different contingency factors for different phases of the project. This study is a compilation of contingency cost of research reactor and for each country. Simulation techniques using TRIM, MATLAB, and PSpice can be useful tools for designing detector channels. Thus far TRIM, MATLAB and PSpice have been used to calculate the detector current output pulse for SiC semiconductor detectors and to model the pulses that propagate through potential detector channels. This model is useful for optimizing the detector and the resolution for application to neutron monitoring in the Generation IV power reactors.

Global solutions through simulation for better decommissioning

International Nuclear Information System (INIS)

Scoto Di Suoccio, Ines; Testard, Vincent

2016-01-01

Decommissioning is a new activity in sense that it only exists a limited experience. Moreover, each facility is different due to their own history and there is no rule about choosing a decommissioning strategy. There are three major decommissioning strategies. First, 'immediate dismantling', which means the action of decommissioning begins immediately after the transfer of waste and nuclear material. Second, 'deferred dismantling strategy', which means that the facility is maintained into a containment zone from thirty to one hundred years before being decommissioned. Finally, 'entombment', means the facility is placed into a reinforced containment until the radionuclides decay and reach a level allowing the site release. When a strategy is decided many factors have to be taken into account. Into a major project such as a reactor decommissioning, there are many smaller projects. The decommissioning strategy can be different among these smaller projects. For some reasons, some entry data are not perfectly known. For example, dosimetric activity has not been updated through time or after specific events. Indeed, because of uncertainties and/or hypothesis existing around projects and their high level of interdependency, global solutions are a good way to choose the best decommissioning strategy. Actually, each entry data has consequences on output results whether it is on costs, cumulated dose, waste or delays. These output data are interdependent and cannot be taken apart from each other. Whether the dose, delays or waste management, all have impact on costs. To obtain an optimal scenario into a special environment, it is necessary to deal with all these items together. This global solution can be implemented thanks to simulation in dedicated software which helps to define the global strategy, to optimize the scenario, and to prevent contingencies. As a complete scenario simulation can be done quickly and efficiently, many strategies can

An overview of U.S. decommissioning experience -- A basic introduction

International Nuclear Information System (INIS)

Boing, L.E.

1998-01-01

This paper presents an overview of the US experiences in the decommissioning technical area. Sections included are: (1) an overview of the magnitude of the problem, (2) a review of the US decommissioning process, (3) regulation of decommissioning, (4) regulatory and funding requirements for decommissioning, and (5) a general overview of all on-going and completed decommissioning projects to date in the US. The final section presents a review of some issues in the decommissioning area currently being debated in the technical specialists community

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

Deactivation, Decontamination and Decommissioning Project Summaries

Energy Technology Data Exchange (ETDEWEB)

Peterson, David Shane; Webber, Frank Laverne

2001-07-01

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

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)

Decommissioning of the CANDU-PHW reactor

International Nuclear Information System (INIS)

Unsworth, G.N.

1977-04-01

This report contains the results of a study of various aspects of decommissioning of reactors. The study places in perspective the size of the job, the hazards involved, the cost and the environmental impact. The three internationally agreed ''stages'' of decommissioning, namely, mothballing, entombment, and dismantling are defined and discussed. The single unit 600 MW(e) CANDU is chosen as the type of reactor on which the discussion is focussed but the conclusions reached will provide a basis for judgement of the costs and problems associated with decommissioning reactors of other sizes and types. (author)

Regulatory aspects of nuclear reactor decommissioning

International Nuclear Information System (INIS)

Ross, W.M.

1990-01-01

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

Some studies related to decommissioning of nuclear reactors

International Nuclear Information System (INIS)

Bergman, C.; Menon, S.

1990-02-01

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

Decommissioning alternatives, process and work activities

International Nuclear Information System (INIS)

Anon.

1986-01-01

The following outlines the topics discussed under Decommissioning Alternatives, Process and Work Activities: (1) decommissioning alternatives, (2) work activities for prompt removal/dismantling, (3) work activities for entombment with delayed dismantling, and (4) work activities for mothballing with delayed dismantling

International Decommissioning Symposium 2000 (IDS 2000). Final Report

International Nuclear Information System (INIS)

Ebadian, M.A.

2001-01-01

The purpose of IDS 2000 was to deliver a world-class conference on applicable global environmental issues. The objective of this conference was to publicize environmental progress of individual countries, to provide a forum for technology developer and problem-holder interaction, to facilitate environmental and technology discussions between the commercial and financial communities, and to accommodate information and education exchange between governments, industries, universities, and scientists. The scope of this project included the planning and execution of an international conference on the decommissioning of nuclear facilities, and the providing of a business forum for vendors and participants sufficient to attract service providers, technology developers, and the business and financial communities. These groups, when working together with attendees from regulatory organizations and government decision-maker groups, provide an opportunity to more effectively and efficiently expedite the decommissioning projects

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

International Nuclear Information System (INIS)

2017-01-01

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

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

International Nuclear Information System (INIS)

2015-01-01

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

Cost estimation for decommissioning of research reactors

International Nuclear Information System (INIS)

Grossi, Pablo Andrade; Tello, Cledola Cassia Oliveira de; Segabinaze, Roberto de Oliveira; Daniska, Vladimir

2013-01-01

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

The regulation and deregulation requirements for the decommissioning of nuclear installations

International Nuclear Information System (INIS)

Wagner, H.

1993-01-01

On the basis of a brief outline of the starting point in terms of technical conditions and status, and of the main aspects of application and interpretation of the law, the regulation and deregulation requirements are elaborated in the light of suggestions for change and with regard to their possible concretization in laws and subordinate laws; the strongest need for change undoubtedly is in the field of the technical codes and regulations, which hitherto have been established primarily for the construction and operation of nuclear installations and hence are not necessarily applicable to the activities to be performed for decommissioning. Practice so far has shown, however, that these regulations are applied not analogously, as would be adequate, but in direct manner. The required review and modification of the existing regulatory codes for the purpose of decommissioning will have to concentrate on the following aspects: - Scope and level of specification of application documents; - definition of important, safety-related events (as e.g. accidents); - scope and level of specification of expert opinions, taking into account the reduced risk level. As a long-term objective, it would be desirable to harmonize existing German regulatory provisions for the decommissioning of industrial plants with an environmental impact (as e.g, the Waste Management Act, Atomic Energy Act, mining law, Federal Emission Control Act), and to seek an approach of national regulatory systems and technical codes in this field under the roof of the EC. (orig./HSCH) [de

Cost estimation for decommissioning: a review of current practice

International Nuclear Information System (INIS)

O'Sullivan, P.; Pescatore, C.

2009-01-01

It is now common practice for decommissioning plans and associated cost estimates to be prepared for all nuclear installations. Specific requirements are generally set out in regulations that have their basis in national legislation. These estimates are important for ensuring that the necessary funds are being collected to cover the actual costs of decommissioning the facility. The long time horizon for both amassing and disbursing these funds is a particular concern for national authorities. It is thus important to maintain a realistic estimate of the liabilities involved and to confirm the adequacy of the provisions to discharge them over time. Estimates of decommissioning costs have been performed and published by many organisations for many different purposes and applications. The results often vary because of differences in basic assumptions such as the choice of the decommissioning strategy (immediate vs. deferred), the availability of waste management pathways, the assumed end states of installations, the detailed definition of cost items, technical uncertainties, unforeseen events, the evolution of regulation and requirements. Many of these differences may be unavoidable since a reasonable degree of reliability and accuracy can only be achieved by developing decommissioning cost estimates on a case-by-case, site-specific basis. Moreover, even if considerable efforts are made to obtain reliable estimates, unforeseen events may cause estimates to go wrong. The issue of how to deal with uncertainties is therefore an important one, leading in turn to the need for risk management in terms of making adequate funding provisions. In March 2008, a questionnaire was circulated among the organisations participating in the NEA Decommissioning and Cost Estimation Group (DCEG). Information was collected on legal requirements and the responsibilities of the main parties concerned with the preparation and oversight of cost estimates, the main cost elements and associated

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

International Nuclear Information System (INIS)

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

2014-01-01

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

Risk Management of Large Component in Decommissioning

International Nuclear Information System (INIS)

Nah, Kyung Ku; Kim, Tae Ryong

2014-01-01

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

Risk Management of Large Component in Decommissioning

Energy Technology Data Exchange (ETDEWEB)

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

2014-10-15

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

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

Comparing nuclear decommissioning in the UK and France

International Nuclear Information System (INIS)

Walls, J.; Garcier, R.

2008-01-01

In this paper we will compare the decommissioning policies in the UK and France. Both countries have a long nuclear history and decommissioning has taken place since the 1960. However, the proposed decommissioning of Magnox and AGR sites in the UK and of UNGG sites in France brings decommissioning efforts to a new level. Whilst we explore in detail the approaches and methodologies adopted in each country we remain sensitive to the effects that political and economic history play in shaping the policy response. In this paper we draw upon interviews conducted with a range of key stakeholders including: national regulators, companies involved in decommissioning, local politicians and community representatives. We also analyse key academic and non academic literature. (authors)

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)

Nuclear power plant decommissioning costs in perspective

International Nuclear Information System (INIS)

Rothwell, Geoffrey; Deffrennes, Marc; Weber, Inge

2016-01-01

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

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)

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

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

Reactor decommissioning

International Nuclear Information System (INIS)

Lawton, H.

1984-01-01

A pioneering project on the decommissioning of the Windscale Advanced Gas-cooled Reactor, by the UKAEA, is described. Reactor data; policy; waste management; remote handling equipment; development; and recording and timescales, are all briefly discussed. (U.K.)

Decommissioning wind energy projects: An economic and political analysis

International Nuclear Information System (INIS)

Ferrell, Shannon L.; DeVuyst, Eric A.

2013-01-01

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

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

Decommissioning of DR 1, Final report

Energy Technology Data Exchange (ETDEWEB)

Lauridsen, Kurt

2006-01-15

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

Decommissioning of DR 1, Final report

International Nuclear Information System (INIS)

Lauridsen, Kurt

2006-01-01

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

NMSS handbook for decommissioning fuel cycle and materials licensees

International Nuclear Information System (INIS)

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

1997-03-01

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

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)

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

Several issues of uranium geology exploration facilities decommissioning

International Nuclear Information System (INIS)

Zhang Lu; Lu Caixia; Sheng Qing; Zhuang Jingqi; Xie Shujun; Liao Yunxuan

2013-01-01

The environmental protection completion acceptance review work of uranium geology exploration facilities 'llth five-year plan' decommissioned and remediation projects is introduced. Some questions related to norms and standards for uranium geology exploration facilities decommissioning and remediation, scheme of decommissioning and remediation, process inspection and acceptance of project and so on are discussed, and corresponding countermeasures and suggestions are put forward, Some references can be provided for the later development of uranium geological exploration facility '12th five-year plan' decommissioning and remediation projects. (authors)

Shippingport Station Decommissioning Project

International Nuclear Information System (INIS)

McKernan, M.L.

1989-01-01

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

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)

Unrestricted re-use of decommissioned nuclear laboratories

Energy Technology Data Exchange (ETDEWEB)

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

1996-09-18

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

Discussion on management of decommissioning funds for nuclear power plants

International Nuclear Information System (INIS)

Wang Hailiang

2013-01-01

Decommissioning funding is one of the major issues with regard to the policy and management of nuclear power. This paper describes current status of decommissioning of nuclear power plants in some foreign countries and narrates the practices in these countries on the estimation of decommissioning cost, the retrieval and management of decommissioning funds, and the guarantee of fund sufficiency. Based on a brief analysis of the status of decommissioning funding management for nuclear power plants in China, suggestions on tasks or activities needed to be carried out at present in the field of decommissioning funding are proposed. (authors)

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)

Study on archive management for nuclear facility decommissioning projects

International Nuclear Information System (INIS)

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