Decommissioning and radioactive waste management. The European Commission overview

International Nuclear Information System (INIS)

Rehak, M

2010-01-01

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

Germany: Management of decommissioning waste in Germany

International Nuclear Information System (INIS)

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

2007-01-01

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

Radioactive waste management and decommissioning in The United States

International Nuclear Information System (INIS)

Raymont, J.M.

2005-01-01

With their missions and access to disposal sites changing over the last decade, radioactive waste management and decommissioning practice in the U.S. commercial and federal nuclear markets has evolved to keep pace. This paper reviews the changes that have occurred and the differing waste management practices that have resulted depending on whether a nuclear facility is situated on federally owned or privately owned property in the United States, confirming that the cost of disposal generally dictates waste management and decommissioning practices. Of the 123 utility-owned licensed commercial reactors in U.S., 19 are undergoing decomissioning, with the balance of 104 reactors focusing on plant life extension, power upgrades, and power generation. As a result, almost all of the approximately dollar 400 million in annual expenditures on waste processing and disposal comes from waste generated from operations. In contrast, the U.S. Department of Energy (DOE), under its Environmental Management (EM) program, is focused on decommissioning the facilities, tanks, and ground contamination resulting from 50-years of Cold War activities and spending about dollar 7 billion a year on these activities. Other than spent fuel, U.S. federal law precludes disposal of commercial nuclear power plant radioactive wastes at DOE disposal sites. In contrast to the commercial disposal market, which must go through extensive public hearings and decision-making, the DOE has a much freer hand in siting new disposal capacity on federal land. As a result, the DOE has ample disposal capacity, 'routinely' opens new disposal sites, and enjoys disposal pricing well below the commercial market. Waste composition, volume, and activity levels drive disposal costs, which is the key life cycle parameter in determining radioactive waste management practice. Differences in these parameters drive the differences in how radioactive waste management practice is performed in the commercial and DOE markets

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

International Nuclear Information System (INIS)

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

2002-01-01

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

BN-350 decommissioning problems of radioactive waste management

International Nuclear Information System (INIS)

Galkin, A.; Tkachenko, V.

2002-01-01

Pursuant of modern concept on radioactive waste management applied in IAEA Member States all radioactive wastes produced during the BN-350 operation and decommissioning are subject to processing in order to be transformed to a form suitable for long-term storage and final disposal. The first two priority objectives for BN-350 reactor are as follows: cesium cleaning from sodium followed by sodium drain, and processing; processing of liquid and solid radioactive waste accumulated during BN-350 operation. Cesium cleaning from sodium and sodium processing to NaOH will be implemented under USA engineering and financial support. However the outputted product might be only subject to temporary storage under special conditions. Currently the problem is being solved on selection of technology for sodium hydroxide conversion to final product incorporated into cement-like matrix ready for disposal pursuant to existing regulatory requirements. Industrial installation is being designed for liquid radioactive waste processing followed by incorporation to cement matrix subject to further disposal. The next general objective is management of radioactive waste expected from BN-350 decommissioning procedure. Complex of engineering-radiation investigation that is being conducted at BN-350 site will provide estimation of solid and liquid radioactive waste that will be produced during the course of the BN-350 decommission. Radioactive wastes that will be produced may be shared for primary (metal structures of both reactor and reactor plant main and auxiliary systems equipment as well as construction wastes of dismantled biological protection, buildings and structures) and secondary (deactivation solutions, tools, materials, cloth, special accessory, etc.). Processing of produced radioactive wastes (including high activity waste) requires the use of special industrial facilities and construction of special buildings and structures for arrangement of facilities mentioned as well as for

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

International Nuclear Information System (INIS)

2011-01-01

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

The Waste Management Plan integration into Decommissioning Plan of the WWR-S research reactor from Romania

International Nuclear Information System (INIS)

Barariu, Gheorghe; Oprescu, Theodor; Filip, Mihaela; Sociu, Florin

2008-01-01

The paper presents the progress of the Radioactive Waste Management Plan which accompanies the Decommissioning Plan for research reactor WWR-S located in Magurele, Ilfov, near Bucharest, Romania. The new variant of the Decommissioning Plan was elaborated taking into account the IAEA recommendation concerning radioactive waste management. A new feasibility study for WWR-S decommissioning was also developed. The preferred safe management strategy for radioactive wastes produced by reactor decommissioning is outlined. The strategy must account for reactor decommissioning, as well as rehabilitation of the existing Radioactive Waste Treatment Plant and the upgrade of the Radioactive Waste Disposal Facility at Baita-Bihor. Furthermore, the final rehabilitation of the laboratories and reusing of cleaned reactor building is envisaged. An inventory of each type of radioactive waste is presented. The proposed waste management strategy is selected in accordance with the IAEA assistance. Environmental concerns are part of the radioactive waste management strategy. (authors)

Analytical methodology for optimization of waste management scenarios in nuclear installation decommissioning process - 16148

International Nuclear Information System (INIS)

Zachar, Matej; Necas, Vladimir; Daniska, Vladimir; Rehak, Ivan; Vasko, Marek

2009-01-01

The nuclear installation decommissioning process is characterized by production of large amount of various radioactive and non-radioactive waste that has to be managed, taking into account its physical, chemical, toxic and radiological properties. Waste management is considered to be one of the key issues within the frame of the decommissioning process. During the decommissioning planning period, the scenarios covering possible routes of materials release into the environment and radioactive waste disposal, should be discussed and evaluated. Unconditional and conditional release to the environment, long-term storage at the nuclear site, near surface or deep geological disposal and relevant material management techniques for achieving the final status should be taken into account in the analysed scenarios. At the level of the final decommissioning plan, it is desirable to have the waste management scenario optimized for local specific facility conditions taking into account a national decommissioning background. The analytical methodology for the evaluation of decommissioning waste management scenarios, presented in the paper, is based on the materials and radioactivity flow modelling, which starts from waste generation activities like pre-dismantling decontamination, selected methods of dismantling, waste treatment and conditioning, up to materials release or conditioned radioactive waste disposal. The necessary input data for scenarios, e.g. nuclear installation inventory database (physical and radiological data), waste processing technologies parameters or material release and waste disposal limits, have to be considered. The analytical methodology principles are implemented into the standardised decommissioning parameters calculation code OMEGA, developed in the DECOM company. In the paper the examples of the methodology implementation for the scenarios optimization are presented and discussed. (authors)

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

HSE policy on decommissioning and radioactive waste management at licensed nuclear sites

International Nuclear Information System (INIS)

Bacon, M.

1997-01-01

In the UK, radioactive waste management and decommissioning on a licensed nuclear is regulated by the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to radioactive waste management and decommissioning activities. This provides a continuous but flexible safety regime until there is no danger from ionizing radiations. The regulatory policy is discussed, taking into account the implications of the 1995 White Paper reviewing radioactive waste management policy. For both radioactive waste management and decommissioning the key element of HSE policy is the need for strategic planning. This should ensure that problems are not allowed to build up and to demonstrate that, taking into account all factors, the proposed actions are the optimum in terms of safety. There is a presumption in HSE's policy towards disposal of radioactive waste as soon as possible where disposal routes exist. Where long-term storage is necessary passively safe forms are preferred over those requiring continuous monitoring or frequent intervention. (author)

Decommissioning of nuclear facilities: Decontamination, disassembly and waste management

International Nuclear Information System (INIS)

1983-01-01

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

Waste management for Shippingport Station Decommissioning Project: Extended summary

International Nuclear Information System (INIS)

Mullee, G.R.; Schulmeister, A.R.

1987-01-01

The Shippingport Station (SSDP) is demonstrating that the techniques and methodologies of waste management, which are currently employed by the nuclear industry, provide adequate management and control of waste activities for the decommissioning of a large scale nuclear plant. The SSDP has some unique aspects in that as part of the objective to promote technology transfer, multiple subcontractors are being utilized in the project. The interfaces resulting from multiple subcontractors require additional controls. Effective control has been accomplished by the use of a process control and inventory system, coupled with personnel training in waste management activities. This report summarizes the waste management plan and provides a status of waste management activities for SSDP

Standard Guide for Preparing Waste Management Plans for Decommissioning Nuclear Facilities

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

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

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

International Nuclear Information System (INIS)

1985-01-01

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

Reducing market distortions by setting harmonized standards for decommissioning and waste management funds in Europe

International Nuclear Information System (INIS)

Irrek, W.

2002-01-01

There are significant differences in the operation and accessibility of decommissioning and waste management funds in Europe. The diverging standards for these funds cause substantial market distortions and discrimination between competing electricity producers. Although there are different views regarding the question, if provisions for decommissioning and final waste disposal constitute prohibited state aid within the meaning of Article 87 (1) EC Treaty, and although the decommissioning and waste management funds is not a new issue, the liberalisation process across the EU means that this issue is one which must be addressed quickly by EU and national policy. (author)

Waste management, decommissioning and environmental restoration for Canada's nuclear activities: 'Current practices and future needs'

International Nuclear Information System (INIS)

2006-01-01

The Canadian Nuclear Society conference on Waste Management, Decommissioning and Environmental Restoration for Canada's Nuclear Activities was held on May 8-11, 2005 in Ottawa, Ontario, Canada. The objective of this Conference was to provide a forum for discussion and exchange of views on the technical, regulatory and social challenges and opportunities in radioactive waste management, nuclear facility decommissioning and environmental restoration activities in Canada. The Conference was organized into several plenary sessions and eight technical tracks: Low- and intermediate-level wastes; Uranium mining and milling wastes; Used nuclear fuel; Decommissioning; Environmental restoration; Policy, economics and social issues; Licensing and regulatory issues; and, Radioactive materials transportation. The three-day Conference involved waste management, decommissioning and environmental technology practitioners; delegates from industry, academia, and government agencies and regulators; consulting engineers; financial and legal experts; and other specialists working in the field. While the Conference had a primarily Canadian focus, about 10 per cent of the submissions received came from foreign and international organizations, which provided insights into how other countries are dealing with similar issues

UK safety and standards for radioactive waste management and decommissioning on nuclear licensed sites

International Nuclear Information System (INIS)

Mason, D.J.

2001-01-01

This paper discusses the regulation of radioactive waste and decommissioning in the United Kingdom and identifies the factors considered by HM Nuclear Installations Inspectorate in examining the adequacy arrangements for their management on nuclear licensed sites. The principal requirements are for decommissioning to be undertaken as soon as reasonably practicable and that radioactive wastes should be minimised, disposed of or contained and controlled by storage in a passively safe form. However, these requirements have to be considered in the context of major organisational changes in the UK nuclear industry and the non-availability of disposal routes for some decommissioning wastes. The legislative framework used to regulate decommissioning of nuclear facilities in the UK is described. Reference is made to radioactive waste and decommissioning strategies, quinquennial reviews criteria for delicensing and the forthcoming Environmental Impact Assessment Regulations. (author)

Software development to support decommissioning and waste management strategic planning

International Nuclear Information System (INIS)

Williams, John; Warneford, Ian; Harrison, J.

1997-01-01

One of the components of the UKAEA's mission is to care for and, at the appropriate time, safely dismantle its radioactive facilities which are no longer in use. To assist in the development of an optimised strategy, AEA Technology was commissioned to produce decision support software. This paper describes the background to the development of the software, its key features and current status, and the lessons learnt during the development. The software, known as UKAEA SPS (Strategic Planning System), is a unique support software package that has been developed to assist in the planning of decommissioning and radioactive waste management. SPS models linked decommissioning and waste management strategies covering all of UKAEA's nuclear liabilities. It has been developed around the database package ACCESS, and runs on Pentium PCs; however, it has many of the features of project planning systems. Its principal outputs are costs, timings and utilisation data for the waste stores, processing facilities, transport and disposal operations displayed at any level of aggregation. This allows programme managers to see easily the effects of changing key parameters in a strategy under development. (author)

Progress on radiochemical analysis for nuclear waste management in decommissioning

Energy Technology Data Exchange (ETDEWEB)

Hou, X. (Technical Univ. of Denmark. Center for Nuclear Technologies (NuTech), Roskilde (Denmark))

2012-01-15

This report summarized the progress in the development and improvement of radioanalytical methods for decommissioning and waste management completed in the NKS-B RadWaste 2011 project. Based on the overview information of the analytical methods in Nordic laboratories and requirement from the nuclear industry provided in the first phase of the RadWaste project (2010), some methods were improved and developed. A method for efficiently separation of Nb from nuclear waste especially metals for measurement of long-lived 94Nb by gamma spectrometry was developed. By systematic investigation of behaviours of technetium in sample treatment and chromatographic separation process, an effective method was developed for the determination of low level 99Tc in waste samples. An AMS approachment was investigated to measure ultra low level 237Np using 242Pu for AMS normalization, the preliminary results show a high potential of this method. Some progress on characterization of waste for decommissioning of Danish DR3 is also presented. (Author)

Progress on radiochemical analysis for nuclear waste management in decommissioning

International Nuclear Information System (INIS)

Hou, X.

2012-01-01

This report summarized the progress in the development and improvement of radioanalytical methods for decommissioning and waste management completed in the NKS-B RadWaste 2011 project. Based on the overview information of the analytical methods in Nordic laboratories and requirement from the nuclear industry provided in the first phase of the RadWaste project (2010), some methods were improved and developed. A method for efficiently separation of Nb from nuclear waste especially metals for measurement of long-lived 94Nb by gamma spectrometry was developed. By systematic investigation of behaviours of technetium in sample treatment and chromatographic separation process, an effective method was developed for the determination of low level 99Tc in waste samples. An AMS approachment was investigated to measure ultra low level 237Np using 242Pu for AMS normalization, the preliminary results show a high potential of this method. Some progress on characterization of waste for decommissioning of Danish DR3 is also presented. (Author)

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.

Evaluation of cost of radioactive waste management during the Chernobyl NPP decommissioning

International Nuclear Information System (INIS)

Gavrish, V.M.; Tkachev, D.A.

2009-01-01

The article presents the results of calculations on evaluation of radioactive waste volumes, the required financing, and the labor expenses for management of radioactive waste that may arise during the decommissioning of Chernobyl NPP Units 1, 2, 3

Selected problems of minimization and management of radioactive wastes from nuclear power plant decommissioning. Part 2

International Nuclear Information System (INIS)

Kyrs, M.; Moravec, A.

1988-06-01

The processing prior to storage of radioactive wastes produced in nuclear power plant decommissioning is described as are the types of containers employed for waste transport and/or disposal. Data are summarized on exposure of personnel to radioactivity resulting from nuclear power plant decommissioning activities, and accessible data are collected on the costs of nuclear power plant decommissioning and of waste management. Potential directions of research in this field under Czechoslovak conditions are specified. (author)

The Optimization of Radioactive Waste Management in the Nuclear Installation Decommissioning Process

International Nuclear Information System (INIS)

Zachar, Matej; Necas, Vladimir

2008-01-01

The paper presents a basic characterization of nuclear installation decommissioning process especially in the term of radioactive materials management. A large amount of solid materials and secondary waste created after implementation of decommissioning activities have to be managed considering their physical, chemical, toxic and radiological characteristics. Radioactive materials should be, after fulfilling all the conditions defined by the authorities, released to the environment for the further use. Non-releasable materials are considered to be a radioactive waste. Their management includes various procedures starting with pre-treatment activities, continuing with storage, treatment and conditioning procedures. Finally, they are disposed in the near surface or deep geological repositories. Considering the advantages and disadvantages of all possible ways of releasing the material from nuclear installation area, optimization of the material management process should be done. Emphasis is placed on the radiological parameters of materials, availability of waste management technologies, waste repositories and on the radiological limits and conditions for materials release or waste disposal. Appropriate optimization of material flow should lead to the significant savings of money, disposal capacities or raw material resources. Using a suitable calculation code e.g. OMEGA, the evaluation of the various material management scenarios and selection of the best one, based on the multi-criterion analysis, should be done. (authors)

Waste minimization fundamental principles used in radioactive waste management plan for decommissioning of a CANDU - 600 nuclear power plant

International Nuclear Information System (INIS)

Barariu, Gheorghe; Georgescu, Roxana Cristiana; Sociu, Florin

2009-01-01

The objectives of waste minimization are to limit the generation and spread of radioactive contamination and to reduce the amount of wastes for storage and disposal, thereby limiting any consequent environmental impact, as well as the total costs associated with contaminated material management. This objective will be achieved by: reviewing the sources and characteristics of radioactive materials arising from Decontamination and Decommissioning (D and D) activities; reviewing waste minimization principles and current practical applications, together with regulatory, technical, financial and political factors influencing waste minimization practices; and reviewing current trends in improving waste minimization practices during Decontamination and Decommissioning. The main elements of a waste minimization strategy can be grouped into four areas: source reduction, prevention of contamination spread, recycle and reuse, and waste management optimization. For sustaining this objective, the following principles and procedures of wastes management are taken into account: safety and environment protection principles; principles regarding the facility operation; quality assurance procedures; procedures for material classification and releasing. (authors)

Very low level waste disposal in France. A key tool for the management for decommissioning wastes in France

Energy Technology Data Exchange (ETDEWEB)

Duetzer, Michel [Andra - Agence Nationale pour la Gestion des Dechets Radioactives, Chatenay-Malabry (France). Direction Industrielle

2015-07-01

At the end of the 90{sup th}, France had to deal with the emerging issue of the management of wastes resulting from decommissioning operations of nuclear facilities. A specific regulation was issued and Andra, the French National Radioactive Waste Management Agency, developed a dedicated near surface disposal facility to accommodate very low level radioactive wastes. After more than 10 years of operation, this facility demonstrated it can provide efficient and flexible solutions for the management of decomissioning wastes.

Managing LLRW from decommissioning of nuclear facilities - a Canadian perspective

Energy Technology Data Exchange (ETDEWEB)

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

1994-03-01

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

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)

Radiochemical analysis for nuclear waste management in decommissioning

International Nuclear Information System (INIS)

Hou, X.

2010-07-01

The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

Radiochemical analysis for nuclear waste management in decommissioning

Energy Technology Data Exchange (ETDEWEB)

Hou, X. (Technical Univ. of Denmark, Risoe National Lab. for Sustainable Energy. Radiation Research Div., Roskilde (Denmark))

2010-07-15

The NKS-B RadWaste project was launched from June 2009. The on-going decommissioning activities in Nordic countries and current requirements and problems on the radiochemical analysis of decommissioning waste were discussed and overviewed. The radiochemical analytical methods used for determination of various radionuclides in nuclear waste are reviewed, a book was written by the project partners Jukka Lehto and Xiaolin Hou on the chemistry and analysis of radionuclide to be published in 2010. A summary of the methods developed in Nordic laboratories is described in this report. The progresses on the development and optimization of analytical method in the Nordic labs under this project are presented. (author)

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

International Nuclear Information System (INIS)

2005-01-01

self assessments. Current developments in research reactor design criteria. Calculation methods and codes. Regulatory aspects and experience with current research reactor issues. Quality assurance programmes during the various stages of a reactor life. Training and qualification of reactor operating personnel and regulators. Modifications in operating procedures and training and qualification. In-service and special inspections with respect to ageing. c) Fuel cycle issues covering new high-density fuel development. Fuel fabrication and performance. Fuel qualification programmes. Core conversion. Fuel management (including spent fuel storage). Spent fuel transportation. Final disposition. d) Reactor Decommissioning including Preliminary decommissioning planning (long term). Creation of data base for decommissioning (e.g. during refurbishment). Final decommissioning planning. Extensive research and development activities associated with decommissioning of research reactors. On-going/recently completed research reactor decommissioning projects. e) Waste management (operational waste management) and decommissioning waste management

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)

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

In practice, decommissioning waste volume can be estimated appropriately by finding the differences between prediction and actual operation and considering the operational problem or supplementary matters. So in the nuclear developed countries such as U.S. or Japan, the decommissioning waste volume is predicted on the basis of the experience in their own decommissioning projects. Because of the contamination caused by radioactive material, decontamination activity and management of radio-active waste should be considered in decommissioning of nuclear facility unlike the usual plant or facility. As the decommissioning activity is performed repeatedly, data for similar activities are accumulated, and optimal strategy can be achieved by comparison with the predicted strategy. Therefore, a variety of decommissioning experiences are the most important. In Korea, there is no data on the decommissioning of commercial nuclear power plants yet. However, KAERI has accumulated the basis decommissioning data of nuclear facility through decommissioning of research reactor (KRR-2) and uranium conversion plant (UCP). And DECOMMIS(DECOMMissioning Information Management System) was developed to provide and manage the whole data of decommissioning project. Two codes, FAC code and WBS code, were established in this process. FAC code is the one which is classified by decommissioning target of nuclear facility, and WBS code is classified by each decommissioning activity. The reason why two codes where created is that the codes used in DEFACS (Decommissioning Facility Characterization management System) and DEWOCS (Decommissioning Work-unit productivity Calculation System) are different from each other, and they were classified each purpose. DEFACS which manages the facility needs the code that categorizes facility characteristics, and DEWOCS which calculates unit productivity needs the code that categorizes decommissioning waste volume. KAERI has accumulated decommissioning data of KRR

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

International Nuclear Information System (INIS)

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

2001-01-01

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

Knowledge Management Aspects of Decommissioning. Case Study

International Nuclear Information System (INIS)

Pironkov, Lyubomir

2017-01-01

Kozloduy NPP: Units 5&6, type VVER-1000 - in operation. SE RAW SD “Decommissioning of units 1-4” (type VVER-440); SD “Radioactive Waste – Kozloduy”; SD “National Repository for Radioactive Waste“; SD “Permanent Repository for Radioactive Waste – Novi Han”. Decommissioning Strategy: Strategy Target: “Brown Field”. Initial Version: Safe enclosure – completing by 2050. Updated Version: Continuous dismantling of equipment; Completing the process of Decommissioning of Units 1-4 by 2030. Major Phases: 1.Pre-decommissioning activities; 2.Facility shutdown activities; 3.Procurement of equipment; 4.Dismantling activities; 5.Treatment of RAM and RAW and delivery for disposal; 6.Site management and support; 7.Project management and engineering; 8.Management of SNF and activated materials

Decommissioning the Romanian Water-Cooled Water-Moderated Research Reactor: New Environmental Perspective on the Management of Radioactive Waste

International Nuclear Information System (INIS)

Barariu, G.; Giumanca, R.

2006-01-01

Pre-feasibility and feasibility studies were performed for decommissioning of the water-cooled water-moderated research reactor (WWER) located in Bucharest - Magurele, Romania. Using these studies as a starting point, the preferred safe management strategy for radioactive wastes produced by reactor decommissioning is outlined. The strategy must account for reactor decommissioning, as well as for the rehabilitation of the existing Radioactive Waste Treatment Plant and for the upgrade of the Radioactive Waste Disposal Facility at Baita-Bihor. Furthermore, the final rehabilitation of the laboratories and ecological reconstruction of the grounds need to be provided for, in accordance with national and international regulations. In accordance with IAEA recommendations at the time, the pre-feasibility study proposed three stages of decommissioning. However, since then new ideas have surfaced with regard to decommissioning. Thus, taking into account the current IAEA ideology, the feasibility study proposes that decommissioning of the WWER be done in one stage to an unrestricted clearance level of the reactor building in an Immediate Dismantling option. Different options and the corresponding derived preferred option for waste management are discussed taking into account safety measures, but also considering technical, logistical and economic factors. For this purpose, possible types of waste created during each decommissioning stage are reviewed. An approximate inventory of each type of radioactive waste is presented. The proposed waste management strategy is selected in accordance with the recommended international basic safety standards identified in the previous phase of the project. The existing Radioactive Waste Treatment Plant (RWTP) from the Horia Hulubei Institute for Nuclear Physics and Engineering (IFIN-HH), which has been in service with no significant upgrade since 1974, will need refurbishing due to deterioration, as well as upgrading in order to ensure the

Waste management practices in decommissioning nuclear facilities

International Nuclear Information System (INIS)

Dickson, H.W.

1979-01-01

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

Proceedings of the research conference on cementitious composites in decommissioning and waste management (RCWM2017)

International Nuclear Information System (INIS)

Sano, Yuichi; Ashida, Takashi

2017-11-01

Collaborative Laboratories for Advanced Decommissioning Science (CLADS) is responsible to promote international cooperation in the R and D activities on the decommissioning of Fukushima Daiichi Nuclear Power Station and to develop the necessary human resources. CLADS held the Research Conference on Cementitious Composites in Decommissioning and Waste Management (RCWM2017) on 20th and 21st June, 2017. This report compiles the abstracts and the presentation materials in the above conference. (author)

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

International Nuclear Information System (INIS)

Bujoreanu, D.; Bujoreanu, L.

2010-01-01

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

Establishment and Evaluation of Decommissioning Plant Inventory DB and Waste Quantity

International Nuclear Information System (INIS)

Oh, Jae Yong; Moon, Sang-Rae; Yun, Taesik; Kim, Hee-Geun; Sung, Nak-Hoon; Jung, Seung Hyuk

2016-01-01

Korea Hydro and Nuclear Power (KHNP) made a decision for permanent shutdown of Kori-1 and has progressed the strategy determination and R and D for the decommissioning of Kori-1. Decommissioning waste, Structure, System and Components (SSCs) is one of the most important elements. Decommissioning waste quantity is calculated based on Plant Inventory Database (PI DB) with activation and contamination data. Due to the largest portion of waste management and disposal in decommissioning, it is necessary to exactly evaluate waste quantity (applying the regulation, guideline and site-specific characterization) for economic feasibility. In this paper, construction of PI DB and evaluation of waste quantity for Optimized Pressurized Reactor (OPR-1000) are mainly described. Decommissioning waste quantities evaluated are going to be applied to calculation of the project cost. In fact, Ministry of Trade, Industry and Energy (MOTIE) in Korea expected the decommissioning waste quantity in a range of 14,500-18,850 drums, and predicted appropriate liability for decommissioning fund by using waste quantity. The result of this study is also computed by the range of 14,500-18,850 drums. Since there is no site-specific data for the NPP site, this evaluation is the preliminary analysis

Establishment and Evaluation of Decommissioning Plant Inventory DB and Waste Quantity

Energy Technology Data Exchange (ETDEWEB)

Oh, Jae Yong; Moon, Sang-Rae; Yun, Taesik; Kim, Hee-Geun [KHNP CRI, Daejeon (Korea, Republic of); Sung, Nak-Hoon; Jung, Seung Hyuk [KONES Corp., Seoul (Korea, Republic of)

2016-10-15

Korea Hydro and Nuclear Power (KHNP) made a decision for permanent shutdown of Kori-1 and has progressed the strategy determination and R and D for the decommissioning of Kori-1. Decommissioning waste, Structure, System and Components (SSCs) is one of the most important elements. Decommissioning waste quantity is calculated based on Plant Inventory Database (PI DB) with activation and contamination data. Due to the largest portion of waste management and disposal in decommissioning, it is necessary to exactly evaluate waste quantity (applying the regulation, guideline and site-specific characterization) for economic feasibility. In this paper, construction of PI DB and evaluation of waste quantity for Optimized Pressurized Reactor (OPR-1000) are mainly described. Decommissioning waste quantities evaluated are going to be applied to calculation of the project cost. In fact, Ministry of Trade, Industry and Energy (MOTIE) in Korea expected the decommissioning waste quantity in a range of 14,500-18,850 drums, and predicted appropriate liability for decommissioning fund by using waste quantity. The result of this study is also computed by the range of 14,500-18,850 drums. Since there is no site-specific data for the NPP site, this evaluation is the preliminary analysis.

Operating Procedures to Identify Wastes of Decommissioning

International Nuclear Information System (INIS)

Gatea, M.A.

2016-01-01

There are a number of sites in Iraq which have been used for nuclear activities and which contain potentially significant amounts of radioactive material. Many of these sites suffered substantial physical damage during the Gulf Wars as well as the challenging of the difficult security situation in the country.The destruction of the former nuclear facilities during the 1991 Gulf war aggravated the problem. As a result of these events, many of these nuclear facilities have lost their containment of the radioactive material and it now has an increased potential to be dispersed into the environment.Iraqi Decommissioning Directorate (IDD) is one of the Ministry of Science and Technology (MoST) formations. It deals with decommissioning of former Iraqi nuclear sites. It considers a producer of radioactive waste.Therefore, waste management represents the vital requirement to work accomplishment.The work carries out on-site waste pretreatment which considers as a minimization of waste management.W M is necessary to: Segregate 'at source' as much materials as possible to minimize quantities of radioactive waste, clear or exempt as much materials as possible and decontaminate and recycle as much radioactive waste as possible. And in more general terms: to control and account for radioactive waste to protect human health and the environment, to make sure we do not leave unnecessary burdens for future generations, to concentrate, contain and isolate the waste from the environment therefore, this make any releases to the environment to be restricted and subject to regulatory control.This procedure applies on-site waste pretreatment which comprises segregating, characterizing, minimizing, classifying, packaging and relocating of generated wastes during decommissioning of destroyed nuclear facilities. The stationary waste treatment activities are the responsibility of RWTD/MoST.The (RPC/MoE) is the national regulatory body during the whole radioactive waste management

Option managing for radioactive metallic waste from the decommissioning of Kori Unit 1

Energy Technology Data Exchange (ETDEWEB)

Kessel, David S.; Kim, Chagn Lak [KEPCO International Nuclear Graduate School (KINGS), Ulsan (Korea, Republic of)

2017-06-15

The purpose of this paper is to evaluate several leading options for the management of radioactive metallic waste against a set of general criteria including safety, cost effectiveness, radiological dose to workers and volume reduction. Several options for managing metallic waste generated from decommissioning are evaluated in this paper. These options include free release, controlled reuse, and direct disposal of radioactive metallic waste. Each of these options may involve treatment of the metal waste for volume reduction by physical cutting or melting. A multi-criteria decision analysis was performed using the Analytic Hierarchy Process (AHP) to rank the options. Melting radioactive metallic waste to produce metal ingots with controlled reuse or free release is found to be the most effective option.

Organization and management for decommissioning of large nuclear facilities

International Nuclear Information System (INIS)

2000-01-01

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

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

Options for Enhancing Education, Training and Knowledge Management for Decommissioning

International Nuclear Information System (INIS)

Roberts, John

2017-01-01

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

BNFL nuclear decommissioning liabilities management program

International Nuclear Information System (INIS)

Colquhoun, A.P.

1995-01-01

The objective of this paper is to describe BNFL's policy and strategy for decommissioning and also to summarize the overall scope of nuclear liabilities in the wider field of waste retrieval and storage, as well as the dismantling and demolition aspects of decommissioning. BNFL's recently established organisational arrangements for discharging all types of these liabilities are explained, together with a review of practical progress in dealing with them. Organisational changes in recent years have amalgamated decommissioning work with operations covering waste storage and retrieval operations. A strategy of minimising residual activity in shutdown plants is pursued, followed by dismantling and demolition on appropriate time scales to minimise risk and cost. Since April 1995, a new BNFL subsidiary, Nuclear Liabilities Management Company Limited has taken responsibility for discharge of BNFL's Waste Retrieval and Decommissioning liabilities on all BNFL sites. NLM has the objectives of optimal and lowest cost management of liabilities and much clearer segregation of physical operations from project specification and planning. The Ministry of Defense (MoD) policy, strategy, work programmes and progress for the Atomic Weapons Establishment (AWE) are also outlined. MoD/AEA has established an equivalent strategy for dealing with its liabilities. (J.S.). 5 refs., 2 figs., 4 appends

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)

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.)

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 CEC contribution to radioactive waste management, decommissioning and related radiation protection issues

International Nuclear Information System (INIS)

Finzi, S.

1991-01-01

The Commission of the European Communities has, for more than 15 years, supported Research and Development (R and D) programmes on ''Radioactive Waste Management'' (since 1975) as well as on ''Decommissioning of Nuclear Installations'' (since 1979), which are carried out by research laboratories, universities, public organisations and private companies of the EC Member states, under shared-cost contracts. Under these contracts, the Commission of the European Communities generally funds up to 50% of the total cost of a research project. The main objective of the ''Radioactive Waste Management Programme'' is to ensure the safety of the waste management and disposal systems with the goal that the scientific and technological results can be used in practice on industrial scale with full respect for safety and environmental protection requirements. Studies have been performed on three main components of the radioactive waste management system, (i) the waste packages, (ii) the geological repository and (iii) the performance assessment, either through experiments or by theoretical evaluation. The current programme which has two main components, one on waste management, the other on the construction and operation of underground storage facilities, is discussed. (author)

Financial guarantee for decommissioning and nuclear waste management activities at OPG

International Nuclear Information System (INIS)

Van den Hengel, J.

2006-01-01

This paper provides an overview on the establishment and maintenance of a financial guarantee for decommissioning and nuclear waste management activities at Ontario Power Generation (OPG) in accordance with CNSC requirements. The process and timelines are documented leading to the establishment of the guarantee effective July 31, 2003. Reference plans, cost estimates, funding mechanisms and reporting mechanisms are summarized. The renewal process projected at the end of the 5-year initial financial guarantee period is also included. (author)

Blending of Low-Level Radioactive Waste for NPP Decommissioning

International Nuclear Information System (INIS)

Kessel, David S.; Kim, Chang Lak

2016-01-01

Radioactive wastes may are generated throughout the life cycle of a nuclear power plant. These wastes can be categorized as follows: Operational wastes in the form of solids, liquids and gases. Plant components resulting from maintenance, modification or life extension work (e.g. steam generators, pumps, valves, control rods, spent filters, etc.). Materials from the structure of the plant and equipment (e.g. metals and concrete that result in large quantities of waste upon decommissioning Large quantities of materials will be generated during decommissioning and dismantling. A significant proportion of these materials will only be slightly contaminated with radioactivity. Due to economies of scale, recycling and reuse options are more likely to be cost effective for such large quantities of materials than for the relatively smaller quantities arising during operation. These materials also present opportunities to manage waste more effectively by utilizing the approaches to blending discussed in this paper. The NRC uses allows blending based on risk and performance measures for public health and safety. Performance-based regulation means that the blended waste must meet the limits on radiation exposures at the disposal facility and limits on how much the radioactivity concentration may vary or in other words, how homogeneous and well mixed it is. LLW blending is an approach to waste management that can give greater flexibility for disposal options for NPP waste from the entire life cycle of the plant which includes operational wastes such as ion exchange resins and filters, maintenance wastes which include replacement components (discrete items), and large quantities of decommissioning wastes

Blending of Low-Level Radioactive Waste for NPP Decommissioning

Energy Technology Data Exchange (ETDEWEB)

Kessel, David S.; Kim, Chang Lak [KEPCO, Ulsan (Korea, Republic of)

2016-05-15

Radioactive wastes may are generated throughout the life cycle of a nuclear power plant. These wastes can be categorized as follows: Operational wastes in the form of solids, liquids and gases. Plant components resulting from maintenance, modification or life extension work (e.g. steam generators, pumps, valves, control rods, spent filters, etc.). Materials from the structure of the plant and equipment (e.g. metals and concrete that result in large quantities of waste upon decommissioning Large quantities of materials will be generated during decommissioning and dismantling. A significant proportion of these materials will only be slightly contaminated with radioactivity. Due to economies of scale, recycling and reuse options are more likely to be cost effective for such large quantities of materials than for the relatively smaller quantities arising during operation. These materials also present opportunities to manage waste more effectively by utilizing the approaches to blending discussed in this paper. The NRC uses allows blending based on risk and performance measures for public health and safety. Performance-based regulation means that the blended waste must meet the limits on radiation exposures at the disposal facility and limits on how much the radioactivity concentration may vary or in other words, how homogeneous and well mixed it is. LLW blending is an approach to waste management that can give greater flexibility for disposal options for NPP waste from the entire life cycle of the plant which includes operational wastes such as ion exchange resins and filters, maintenance wastes which include replacement components (discrete items), and large quantities of decommissioning wastes.

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

International Nuclear Information System (INIS)

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

2008-01-01

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

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.

A decontamination technique for decommissioning waste

International Nuclear Information System (INIS)

Heki, H.; Hosaka, K.; Kuribayashi, N.; Ishikura, T.

1993-01-01

A large amount of radioactive metallic waste is generated from decommissioned commercial nuclear reactors. It is necessary from the point of environmental protection and resource utilization to decontaminate the contaminated metallic waste. A decommissioning waste processing system has been previously proposed considering such decommissioning waste characteristics as its large quantity, large radioactivity range, and various shapes and materials. The decontamination process in this system was carried out by abrasive blasting as pretreatment, electrochemical decontamination as the main process, and ultrasonic cleaning in water as post-treatment. For electrochemical decontamination, electrolytic decontamination for simple shaped waste and REDOX decontamination for complicated shaped waste were used as effective decontamination processing. This time, various kinds of actual radioactive contaminated samples were taken from operating power plants to simulate the decontamination of decommissioning waste. After analyzing the composition, morphogenesis and surface observation, electrolytic decontamination, REDOX decontamination, and ultrasonic cleaning experiments were carried out by using these samples. As a result, all the samples were decontaminated below the assumed exemption level(=4 x 10 -2 Bq/g). A maximum decontamination factor of over 104 was obtained by both electrolytic and REDOX decontamination. The stainless steel sample was easy to decontaminate in both electrochemical decontaminations because of its thin oxidized layer. The ultrasonic cleaning process after electrochemical decontamination worked effectively for removing adhesive sludge and the contaminated liquid. It has been concluded from the results mentioned above that electrolytic decontamination and REDOX decontamination are effective decontamination process for decontaminating decommissioning waste

Methodology for assessing suitable systems for management of reactor decommissioning wastes

International Nuclear Information System (INIS)

Davis, J.P.; Barraclough, I.M.; Mobbs, S.F.

1990-01-01

This report demonstrates a methodology for comparing quantitatively the options open to decision-makers at various stages of the decommissioning process, taking into account radiological protection and other factors considered to be relevant. In order to compare different decommissioning options, various impacts associated with decommissioning operations and waste disposal were assessed, namely, costs and radiological, environmental and socio-political impact. The post-disposal radiological impact was calculated for four generic concepts (near surface, deep geological, coastal tunnel and deep ocean bed)

SGDes project. Decommissioning management system of Enresa

International Nuclear Information System (INIS)

Fernandez Lopez, M.; Julian, A. de

2013-01-01

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

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)

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)

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

International Nuclear Information System (INIS)

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

2001-01-01

In 1996 the UK Government announced that the Royal Naval College, Greenwich would pass to non-defence use by the millennium. As a consequence of this decision, the decommissioning of the JASON 10 kW Argonaut research reactor and the relocation of the Department of Nuclear Science and Technology (DNST) were approved by the Ministry of Defence. The decommissioning of the reactor commenced in November 1997 while DNST remained operational until October 1998. The DNST was responsible for education and training in support of the UK Naval Nuclear Propulsion Programme and operated academic laboratories for atomic and nuclear physics, health physics, instrument calibration and radiochemistry. Therefore, besides the nuclear reactor, open and sealed sources (alpha, beta and gamma), intense x-ray (sealed tube) and gamma-ray ( 60 CO and 137 Cs) sources and small 241 Am/Be neutron sources had been used in the Department for over 35 years. Decommissioning of all facilities was therefore a relatively complex task and the management of waste streams was challenging. All facilities were successfully decommissioned for unrestricted site release by December 1999 and this paper will describe the methodology used for preparation, storage, characterisation and disposal of all waste streams. The most significant waste management task during this decommissioning programme was that associated with the JASON reactor. It should be noted that the JASON reactor fuel was not designated as nuclear waste, the fuel removal and storage were covered under separate contracts and therefore no high level waste was generated. With respect to other waste streams, a combination of Monte Carlo modelling and selective sampling and analysis of the reactor materials was used to estimate the quantities of waste as follows: LLW - 76 tonnes packed in 4 half height ISO containers; LLW - 6 Tonnes packed in 200litre drums in 1 full height ISO container; ILW - 60 kg packed in approved shielded containers; FRW -121

How it is possible to build a national system for decommissioning waste management without site nor waste liberation: the case of France

International Nuclear Information System (INIS)

Averous, Jeremie; Chapalain, Estelle

2003-01-01

Past experience in decommissioning in France 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 authorization 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 urbanization 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. It is now widely accepted by stakeholders. The French Nuclear Safety Authority is now working to apply this methodology more widely to other nuclear practices like the waste management from medical, research and industrial activities, or from past or remediation activities. (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

The European Community's research and development activities on the management of radioactive waste from decommissioning

International Nuclear Information System (INIS)

Huber, B.

1984-01-01

The Commission of the European Communities is conducting an R and D programme on the decommissioning of nuclear power plants. The activities carried out within this framework that concern, in particular, management of the radioactive waste arising from the decommissioning are outlined. Characterization of the radioactivity inventory of nuclear power plants at the end of their useful life is of fundamental importance in this context. Research in this field comprises analyses of the trace elements in reactor materials which are relevant for the formation of long-lived radionuclides by neutron activation, as well as examinations of samples taken from activated and contaminated plant components. Most of the radioactive plant components are only surface contaminated. Highly efficient decontamination techniques are being developed with the objective of achieving conditions permitting unrestricted release of the material treated. Other activities concern the conditioning of steel and concrete waste for disposal, and the management of graphite waste from gas-cooled reactors. Large containers are being developed for transport and disposal of radioactive components. Finally, the methods of radiological evaluation and measurement are being studied which are required to decide whether material from the dismantling of nuclear power plants has to be disposed of as radioactive waste or not. (author)

Nuclear power plant decommissioning and radioactive waste management in the U.K.. A regulatory perspective

International Nuclear Information System (INIS)

Ross, W.M.

1993-01-01

Effective control of the decommissioning and radioactive waste management of nuclear power plant in United Kingdom are introduced. The Government established the legislative framework and national strategy, operators provided the necessary skills and equipment for implementation, and the regulators used the legislative controls to ensure a safe system of work is achieved and maintained

Enhanced productivity in reactor decommissioning and waste management

International Nuclear Information System (INIS)

Wasinger, Karl

2014-01-01

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

Enhanced productivity in reactor decommissioning and waste management

Energy Technology Data Exchange (ETDEWEB)

Wasinger, Karl [Areva GmbH, Offenbach (Germany)

2014-04-15

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

Waste management experience during all the life cycle of treatment facilities from commissioning till decommissioning. Today's situation and future trends

International Nuclear Information System (INIS)

Decobert, Guy; Devezeaux de Lavergne, Jean-Guy; Maurin, Matthieu

2005-01-01

Over time, the concepts of waste management have deeply evolved. In the case of the earlier generation of treatment plants, on-line conditioning was generally not implemented. In several cases, the strategy was clearly set as promoting storage of 'interim' raw waste, and implementing long-run R and D programs for future conditioning. Thus, one of the main objectives of the last generation of plants was to implement on-line conditioning of all waste, i.e. including waste issued from the used fuel and also those issued from plant operation (technological waste and effluent treatment waste). These strategic issues are naturally part of the core of the design of every new plant, as part of the operating performance. The enormous amount of experience collected from previous generations of plants, and managed by AREVA, allows us to go one step further. Indeed, our target is to rely on a comprehensive vision of waste management best practices, from the plant design through its decommissioning. This will allow AREVA to think about the next plant generation when encompassing the whole life cycle of the plant, including its different steps: Conception and building, Operation, Decommissioning. The first part of the paper will go back to waste management lessons and achievements in the design-construction phase and the operating phases of past and present treatment plants. From the past till today's generation, a factor of reduction of 50 for the volume of HLW-ILW type of waste was achieved leading to a ratio of 0.0012 m 3 /GWhe for a burn-up of 45 000 MWd/t! With regards to the development of the next generation of reactors and associated back-end, future improvements appear still possible in waste volume reduction. The second part of the paper will focus on decommissioning, which is likely to generate significant amount of waste, whose removal, handling, sorting, measurement, treatment and conditioning represent a substantial part of the cost of the program. Starting from

Decommissioning, radioactive waste management and nuclear public information issues in Italy

Energy Technology Data Exchange (ETDEWEB)

Enrico Mainardi [AIN - ENEA (Italy)

2006-07-01

the international level. The site is extremely stable from the geological point of view. It consists of a 10 km{sup 2} rock-salt layer 150 m thick protected by a clay layer 700 m thick. A similar solution has been adopted successfully for the WIPP (Waste Isolation Pilot Plant) in New Mexico (USA) operating from 1999. This paper outlines the main issues and considerations connected with decommissioning, radioactive waste management and site decision within the country together with more details on the quantities and quality of the Italian nuclear waste. The demonstration that decommissioning is feasible at reasonable costs and that wastes can be collected in a national repository with the highest safety levels will certainly further improve public attitude in favour of nuclear power. (author)

Decommissioning, radioactive waste management and nuclear public information issues in Italy

International Nuclear Information System (INIS)

Enrico Mainardi

2006-01-01

the international level. The site is extremely stable from the geological point of view. It consists of a 10 km 2 rock-salt layer 150 m thick protected by a clay layer 700 m thick. A similar solution has been adopted successfully for the WIPP (Waste Isolation Pilot Plant) in New Mexico (USA) operating from 1999. This paper outlines the main issues and considerations connected with decommissioning, radioactive waste management and site decision within the country together with more details on the quantities and quality of the Italian nuclear waste. The demonstration that decommissioning is feasible at reasonable costs and that wastes can be collected in a national repository with the highest safety levels will certainly further improve public attitude in favour of nuclear power. (author)

Principles and practices in managing the wastes resulting from decommissioning

International Nuclear Information System (INIS)

Vladescu, Gabriela; Oprescu, Theodor; Niculae, Ortenzia; Stan, Camelia

2004-01-01

The main objective in the management of radioactive wastes is the population and environment protection now and for the future without burdening the next generation with tasks other than their own. Achieving this objective is feasible if one takes into account the general principles internationally adopted and also the practices referring to the radioactive wastes, which can be summarized as: avoiding, minimizing, recovering, recycling, and storing. Minimizing the amount of wastes already produced resides in freeing part of them from the nuclear control by means of a process coined as classification. To implement such a process one must have in mind the premises required by classification and freeing the radioactive wastes from the regulating control, based on the legislation regarding the radioactive waste management and the measuring techniques and the corresponding procedures, as well. The target of this work was elaborating a proposal concerning the kind of classifying the radioactive waste in order to take them out from the nuclear control complying at the same time with the principles of minimizing and re-using as much as possible. The chapter 2.1 presents the frame of policy and regulations governing the process of management radioactive wastes. Here a proposal of classification of radioactive wastes is advanced based on the Romanian excepting levels adopted also by other countries, interpretation of the natural background, and the constraints concerning the radioactive and dangerous wastes. The chapter 2.2 presents the general principles of classifying the radioactive materials, of diluting the non-homogeneous distribution in solid materials as well as of the principles implied in the process of taking out some radioactive materials from the reach of regulating nuclear control. The chapter 2.3 deals with application of the radioactive waste management principles to reach a classification that entails taking these waste out from the reach of nuclear control

The characterization of cement waste form for final disposal of decommissioning concrete wastes

International Nuclear Information System (INIS)

Lee, Yoon-ji; Lee, Ki-Won; Min, Byung-Youn; Hwang, Doo-Seong; Moon, Jei-Kwon

2015-01-01

Highlights: • Decommissioning concrete waste recycling and disposal. • Compressive strength of cement waste form. • Characteristic of thermal resistance and leaching of cement waste form. - Abstract: In Korea, the decontamination and decommissioning of KRR-1, 2 at KAERI have been under way. The decommissioning of the KRR-2 was finished completely by 2011, whereas the decommissioning of KRR-1 is currently underway. A large quantity of slightly contaminated concrete waste has been generated from the decommissioning projects. The concrete wastes, 83ea of 200 L drums, and 41ea of 4 m 3 containers, were generated in the decommissioning projects. The conditioning of concrete waste is needed for final disposal. Concrete waste is conditioned as follows: mortar using coarse and fine aggregates is filled with a void space after concrete rubble pre-placement into 200 L drums. Thus, this research developed an optimizing mixing ratio of concrete waste, water, and cement, and evaluated the characteristics of a cement waste form to meet the requirements specified in the disposal site specific waste acceptance criteria. The results obtained from a compressive strength test, leaching test, and thermal cycling test of cement waste forms conclude that the concrete waste, water, and cement have been suggested as an optimized mixing ratio of 75:15:10. In addition, the compressive strength of the cement waste form was satisfied, including a fine powder up to a maximum of 40 wt% in concrete debris waste of about 75%. According to the scale-up test, the mixing ratio of concrete waste, water, and cement is 75:10:15, which meets the satisfied compressive strength because of an increase in the particle size in the waste

Financing waste management, decommissioning and site rehabilitation in the nuclear industry

International Nuclear Information System (INIS)

1987-01-01

The book on financing waste management, decommissioning and site rehabilitation in the nuclear industry, concerns the findings of a survey carried out by the Uranium Institute on the financing of the fuel cycle and utility industries in seventeen countries. The countries included:- Australia, Belgium, Canada, Finland, France, Gabon, German Federal Republic, Italy, Japan, Namibia, South Africa, Spain, Sweden, Switzerland, Taiwan, United Kingdom and United States of America. The survey revealed that provisions for future environmental management costs are being made for most facilities and operations, in some cases dating back over quite a long period. In the case of electricity, such costs are being, or about to be, included in the cost of a kWh by all of the electrical utilities examined. (U.K.)

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.

Waste processing practices at waste management department from INR

International Nuclear Information System (INIS)

Bujoreanu, D.; Bujoreanu, L.

2010-01-01

The Institute for Nuclear Research Pitesti (INR), subsidiary of the Romanian Authority for Nuclear Activities has its own Radioactive Waste Treatment Plant (STDR). The object of activity of STDR within the INR Pitesti is to treat and condition radioactive waste resulted from the nuclear facility. Also, it will must prepare and manage the decommissioning projects of its own facilities and to upgrade the facilities for the management of the radioactive waste resulting from other decommissioning activities. In according with the National Nuclear Program and the Governmental order no. 11/2003, the Institute for Nuclear Research is the main support for implementation of the methods and technologies for conditioning and disposal of radioactive waste generated by the decommissioning of nuclear facilities. The classes and criteria of classification for radioactive waste generated in operation and decommissioning in Romania are established in compliance with the classification recommended by IAEA and generally valid in EU countries. The general classification takes into consideration the disposal requirements to isolate the radioactive waste from environment. In Romania, waste minimization is considered by Order No. 56/2004 of CNCAN President for approval of Fundamental regulations on the safe management of radioactive waste. According to this regulation, the generation of radioactive waste is to be kept to the minimum practicable level in terms of both its activity and volume through appropriate design measures, facility operation and decommissioning practices. In order to meet this requirement, the operator must ensure: - selection and control of materials; - recycling and reuse of materials, including clearance of materials; - implementing adequate operating procedures, including those referring to the physical, chemical and radiological characterization of the waste and sorting of different type of materials. (orig.)

Securing the long-term financing of decommissioning and radioactive waste management - From cost estimates to a comprehensive financing system

International Nuclear Information System (INIS)

Aebersold, Michael

2003-01-01

One of the most important issues in the area of waste disposal concerns the long-term securing of the necessary financing. Large amounts of money will have to be invested, managed and subsequently spent at the appropriate time, over an extended period of 100 years or more. In an electricity market that is opening up across Europe and is characterised by complicated legal structures, a focus on a handful of major groups and cost pressure due to increased competition, it will be necessary to create the corresponding background conditions. The anticipated costs for decommissioning and disposal will have to be calculated or estimated on the basis of available know-how and criteria. The required funds will then have to be collected and invested on the domestic and international money markets, which given the current situation on the stock markets will by no means be an easy task. But the assurance that enough money will be available is essential for public confidence. Using Switzerland as an example, the author wishes to demonstrate which steps are necessary in order to calculate the potential decommissioning and waste disposal costs based on a defined disposal concept and programme, determine the annual contributions to be paid in by operators, and establish a suitable system for securing the necessary funding. This paper deals with the following issues: 1. Political background and legislative framework in Switzerland; 2. Swiss radioactive waste management policy and programmes; 3. Calculating the decommissioning and waste management costs; 4. Calculating the contributions to the Funds; 5. Financing system

Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

Energy Technology Data Exchange (ETDEWEB)

Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Choi, Y. K.; Cho, J. H. [SunKwang Atomic Energy Safety Co., Seoul (Korea, Republic of)

2014-10-15

A large quantity of radioactive waste was generated during the decommissioning projects. For the purpose of the volume reduction and clearance for decommissioning wastes from decommissioning projects, the incineration and high melting technology has been selected for the decommissioning wastes treatment. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. Incinerator burns waste at high temperature. Incineration of a mixture of chemically hazardous and radioactive materials, known as 'mixed waste,' has two principal goals: to reduce the volume and total chemical toxicity of the waste. Incineration itself does not destroy the metals or reduce the radioactivity of the waste. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. About 16.4 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas.

Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

International Nuclear Information System (INIS)

Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K.; Choi, Y. K.; Cho, J. H.

2014-01-01

A large quantity of radioactive waste was generated during the decommissioning projects. For the purpose of the volume reduction and clearance for decommissioning wastes from decommissioning projects, the incineration and high melting technology has been selected for the decommissioning wastes treatment. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. Incinerator burns waste at high temperature. Incineration of a mixture of chemically hazardous and radioactive materials, known as 'mixed waste,' has two principal goals: to reduce the volume and total chemical toxicity of the waste. Incineration itself does not destroy the metals or reduce the radioactivity of the waste. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. About 16.4 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas

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

Project management system for the decommissioning of research reactors

International Nuclear Information System (INIS)

Park, J. H.

2006-01-01

KAERI has developed a computer information system, named DECOMMIS, for the project management with the increased effectiveness of the decommissioning projects and the record keeping for a next decommissioning project. The management system consists of three parts, 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 and the system can play roles of daily work reports to minimize the time gap between the dismantling activities and the evaluation of the data for project management. The DDPS provides useful information to the staff for more effective project management and this information include several fields, such as project progress management, man power management, waste management, radiation dose of workers and so on. It is expected that the system would enable to maintain the decommissioning data, to prepare the source data for the R and D for development of planning tools and to give information to the staff for the decision on the progress of the projects. In this paper, the overall system will be briefly explained and several examples of the utilization, focused on the waste and manpower control, for the project management will be introduced

The use of managing agencies in decommissioning

International Nuclear Information System (INIS)

Nelson, R.L.

1994-01-01

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

Decommissioning and waste markets attract new global alliances

Energy Technology Data Exchange (ETDEWEB)

Shepherd, John [nuclear24, London (United Kingdom)

2014-08-15

Renewed global efforts to broaden knowledge and expertise in the field of radwaste management and identify the most promising technologies for clean-up and treatment of nuclear wastes are being led by the International Atomic Energy Agency (IAEA). In its recently-published annual report for 2013, the IAEA has given details of the development of new projects for the management of intermediate-level waste and large amounts of waste. Decommissioning can be a lucrative prospect. The availability of skills will be a key factor. Whatever technological advances are made in the coming years, there needs to be corresponding investment in attracting new recruits to the nuclear industry and equipping them with the skills that the industry will need.

Decommissioning and waste markets attract new global alliances

International Nuclear Information System (INIS)

Shepherd, John

2014-01-01

Renewed global efforts to broaden knowledge and expertise in the field of radwaste management and identify the most promising technologies for clean-up and treatment of nuclear wastes are being led by the International Atomic Energy Agency (IAEA). In its recently-published annual report for 2013, the IAEA has given details of the development of new projects for the management of intermediate-level waste and large amounts of waste. Decommissioning can be a lucrative prospect. The availability of skills will be a key factor. Whatever technological advances are made in the coming years, there needs to be corresponding investment in attracting new recruits to the nuclear industry and equipping them with the skills that the industry will need.

A State of the Art on the Technology for Recycling and Reuse of the Decommissioning Concrete Wastes

Energy Technology Data Exchange (ETDEWEB)

Jung, Chung Hun; Choi, Wang Kyu; Min, Byung Youn; Oh, Won Zin; Lee, Kun Woo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-02-15

This report describes the reduction and recycling technology of decommissioning concrete waste. Decontamination and decommissioning (D and D) becomes one of the most important nuclear markets especially in the developed countries including USA, UK and France where lots of the retired nuclear facilities have been waiting for decommissioning. In our country the KAERI has been carrying out the decommissioning of the retired TRIGA MARK II and III research reactors and an uranium conversion plant as the first national decommissioning project since 1998. One of the most important areas of the decommissioning is a management of a huge amount of a decommissioning waste the cost of which is more than half of the total decommissioning cost. Therefore reduction in decommissioning waste by a reuse or a recycle is an important subject of decommissioning technology development in the world. Recently much countries pay attention to recycle the large amount of concrete dismantling waste resulted from both a nuclear and a non nuclear industries. In our country, much attention was taken in a recycle of concrete dismantling waste as a concrete aggregate, but a little success has been resulted due to the disadvantages such as a weakness of hardness and surface mortar contamination. A recycle in nuclear industry and a self disposal of the radioactively contaminated concrete wastes are main directions of concrete wastes resulted from a nuclear facility decommissioning. In this report it was reviewed the state of art of the related technologies for a reduction and a recycle of concrete wastes from a nuclear decommissioning in the country and abroad. Prior to recycle and reuse in the nuclear sector, however, the regulatory criteria for the recycle and reuse of concrete waste should be established in parallel with the development of the recycling technology.

A State of the Art on the Technology for Recycling and Reuse of the Decommissioning Concrete Wastes

International Nuclear Information System (INIS)

Jung, Chung Hun; Choi, Wang Kyu; Min, Byung Youn; Oh, Won Zin; Lee, Kun Woo

2008-02-01

This report describes the reduction and recycling technology of decommissioning concrete waste. Decontamination and decommissioning (D and D) becomes one of the most important nuclear markets especially in the developed countries including USA, UK and France where lots of the retired nuclear facilities have been waiting for decommissioning. In our country the KAERI has been carrying out the decommissioning of the retired TRIGA MARK II and III research reactors and an uranium conversion plant as the first national decommissioning project since 1998. One of the most important areas of the decommissioning is a management of a huge amount of a decommissioning waste the cost of which is more than half of the total decommissioning cost. Therefore reduction in decommissioning waste by a reuse or a recycle is an important subject of decommissioning technology development in the world. Recently much countries pay attention to recycle the large amount of concrete dismantling waste resulted from both a nuclear and a non nuclear industries. In our country, much attention was taken in a recycle of concrete dismantling waste as a concrete aggregate, but a little success has been resulted due to the disadvantages such as a weakness of hardness and surface mortar contamination. A recycle in nuclear industry and a self disposal of the radioactively contaminated concrete wastes are main directions of concrete wastes resulted from a nuclear facility decommissioning. In this report it was reviewed the state of art of the related technologies for a reduction and a recycle of concrete wastes from a nuclear decommissioning in the country and abroad. Prior to recycle and reuse in the nuclear sector, however, the regulatory criteria for the recycle and reuse of concrete waste should be established in parallel with the development of the recycling technology

Decommissioning Planning during the Operation of the Loviisa NPP. Planning, Management and Organizational Aspects

Energy Technology Data Exchange (ETDEWEB)

Tuunanen, J. P.; Eurajoki, T. E.E., [Fortum Power and Heat Ltd, Nuclear Waste Espoo (Finland)

2013-08-15

The first decommissioning plan for Loviisa nuclear power plant was written already in 1980's, when the plant had just started operation. The plan has been updated in 5-6 years intervals and this work still continues towards the final decommissioning plan. The decommissioning plan is based on immediate dismantling option and final disposal of decommissioning waste to the extension of the on site final disposal facility for low and intermediate level waste. The decommissioning planning has been organized as an independent project, which is realised in close cooperation with Fortum's research programme on radioactive waste management. The plant personnel are involved in the planning work through providing operating experience on contamination and activation of systems, structures and components. Later in the decommissioning phase the plant personnel will form the main part of the decommissioning organization. (author)

Decommissioning Combustible Waste Treatment using Oxygen-Enriched Incinerator

Energy Technology Data Exchange (ETDEWEB)

Min, Byungyoun; Lee, Yoonji; Yun, Gyoungsu; Lee, Kiwon; Moon, Jeikwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

The aim of the paper is current status of treatment for the decommissioning combustible waste in KAERI and for the purpose of the volume reduction and clearance for decommissioning combustible wastes generated by the decommissioning projects. The incineration technology has been selected for the treatment of combustible wastes. About 34 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. Temperature, pressure of major components, stack gas concentration, i. e., SOx, NOx, CO, CO{sub 2} and HCl, and the residual oxygen were measured. Measured major parameters during normal operation were sustained on a stable status within a criteria operation condition. Oxygen enriched air, 22vol. % (dry basis) was used for stable incineration. The volume reduction ratio has achieved about 1/117. The incineration with decommissioning radioactive combustible waste is possible with moderate oxygen enrichment of 22 vol.% (dry basis) into the supply air. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas. The pressure, off-gas flow and temperature of major components remained constant within the range specified. The measures gases and particulate materials in stack were considerably below the regulatory limits. The achieved volume reduction ratio through incineration is about 1/117.

Decommissioning Work Modeling System for Nuclear Facility Decommissioning Design

International Nuclear Information System (INIS)

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

2012-01-01

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

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

International Nuclear Information System (INIS)

Anon

2004-01-01

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

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

International Nuclear Information System (INIS)

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

2001-07-01

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

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

International Nuclear Information System (INIS)

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

1994-01-01

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

Project No. 7 - Decommissioning unit at Ignalina NPP. (Engineering and project management)

International Nuclear Information System (INIS)

2000-01-01

In order to manage decommissioning process at Ignalina NPP, a new unit should be established in the framework of the Ignalina NPP organizational structure. The on-site Engineering Project Management Unit (PMU) will adopt an integrated approach to project management , engineering design, planning, procurement, safety and licensing activities at Ignalina NPP site. The PMU will assist the Ignalina NPP management in the development of an integrated decommissioning and waste management strategy

Experience gained in the management of radioactive waste from maintenance, decontamination and partial decommissioning of a reprocessing plant and conclusions resulting for the management of radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

Hild, W.

1983-01-01

After a short description of the historical background of Eurochemic, its main tasks and the various operational phases, a detailed description of the waste management principles applied is presented. The practical experience in the waste treatment is reported for both the operational phase of the reprocessing plant and its decontamination and partial decommissioning after shutdown. Based on this experience and the presented data, an assessment of the practical operations is made and conclusions are drawn. Finally, recommendations are formulated both for the general waste management policy and the practical waste treatment processes in nuclear power reactors. (author)

Remediation and decommissioning of radioactive waste facilities in Estonia

International Nuclear Information System (INIS)

Putnik, H.; Realo, E.

2001-01-01

Full text: The nuclear training facility at Paldiski was constructed in the early 1960's by the former USSR Navy. The hull sections of Delta and Echo class submarines each housing a full-sized ship reactor were installed in the main building of the site for training of navy personnel in safe operation of the submarine nuclear reactor systems. The first reactor was commissioned in 1968 and the second in 1982, while both was shut down in 1989. After Estonia's reproclamation of independence in 1991 the responsibility for the clean up and decommissioning of the Paldiski site became a subject of negotiations between Russia and Estonia. As the result Estonia took the ownership and control of the site in September 1995. Before the take over the Russian authorities defuelled the reactors and transported the spent fuel to Russia, dismantled the hull sections not related with reactor systems, seal-welded the hull sections housing the reactor vessels with their primary circuitry and enclosed those in reinforced concrete sarcophagi. The auxiliary facilities and radioactive waste were left intact. Main goals of the Conceptual Decommissioning Plan for the Paldiski facilities, developed under the auspices of the Paldiski International Expert Reference Group (Pier, a group established at the request of the Estonian government to advise local authorities to maintain the decommissioning and waste management at Paldiski) were defined as following: Establishing the waste management system and a long term monitored interim storage, corresponding to internationally accepted safety standards and capable to condition, receive and store all the waste generated during decommissioning of the facility; Reductions of the extent of radiologically controlled areas as much as possible, in order to minimise maintenance requirements. To achieve these goals the following main tasks were addressed in the short and medium term site management action plans: Rearrangement of site for the needs of

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

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)

Potential of the non-waste concept under NPP decommissioning

International Nuclear Information System (INIS)

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

2001-01-01

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

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.

Hinkley Point 'C' power station public inquiry: proof of evidence on on-site radioactive waste management and decommissioning

International Nuclear Information System (INIS)

Passant, F.H.

1988-09-01

A public inquiry has been set up to examine the planning application made by the Central Electricity Generating Board (CEGB) for the construction of a 1200 MW Pressurized Water Reactor power station at Hinkley Point (Hinkley Point ''C'') in the United Kingdom. The CEGB evidence to the Inquiry presented here provides information on the on-site management of solid, liquid and gaseous radioactive wastes both during station operation and during decommissioning. Estimates are given of current and projected future discharges of liquid and gaseous wastes from the site and packaging and transport arrangements for solid radioactive wastes are described. The framework of waste management policy, disposal strategy and legislation in the United Kingdom which will determine procedure at Hinkley Point ''C'' is given. (UK)

The Importance of Building and Enhancing Worldwide Industry Cooperation in the Areas of Radiological Protection, Waste Management and Decommissioning

International Nuclear Information System (INIS)

Saint-Pierre, S.

2006-01-01

The slow or stagnant rate of nuclear power generation development in many developed countries over the last two decades has resulted in a significant shortage in the population of mid-career nuclear industry professionals. This shortage is even more pronounced in some specific areas of expertise such as radiological protection, waste management and decommissioning. This situation has occurred at a time when the renaissance of nuclear power and the globalization of the nuclear industry are steadily gaining momentum and when the industry's involvement in international and national debates in these three fields of expertise (and the industry's impact on these debates) is of vital importance. This paper presents the World Nuclear Association (WNA) approach to building and enhancing worldwide industry cooperation in radiological protection, waste management and decommissioning, which is manifested through the activities of the two WNA working groups on radiological protection (RPWG) and on waste management and decommissioning (WM and DWG). This paper also briefly describes the WNA's participatory role, as of summer 2005, in the International Atomic Energy Agency (IAEA) standard development committees on radiation safety (RASSC), waste safety (WASSC) and nuclear safety (NUSSC). This participation provides the worldwide nuclear industry with an opportunity to be part of IAEA's discussions on shaping changes to the control regime of IAEA safety standards. The review (and the prospect of a revision) of IAEA safety standards, which began in October 2005, makes this WNA participation and the industry ' s involvement at the national level timely and important. All of this excellent industry cooperation and team effort is done through 'collegial' exchanges between key industry experts, which help tackle important issues more effectively. The WNA is continuously looking to enhance its worldwide industry representation in these fields of expertise through the RPWG and WM and DWG

The importance of building and enhancing worldwide industry cooperation in the areas of radiological protection, waste management and decommissioning

International Nuclear Information System (INIS)

Saint-Pierre, S.

2006-01-01

The slow or stagnant rate of nuclear power generation development in many developed countries over the last two decades has resulted in a significant shortage in the population of mid-career nuclear industry professionals. This shortage is even more pronounced in some specific areas of expertise such as radiological protection, waste management and decommissioning. This situation has occurred at a time when the renaissance of nuclear power and the globalization of the nuclear industry are steadily gaining momentum and when the industry's involvement in international and national debates in these three fields of expertise (and the industry's impact on these debates) is of vital importance. This paper presents the World Nuclear Association (WNA) approach to building and enhancing worldwide industry cooperation in radiological protection, waste management and decommissioning, which is manifested through the activities of the two WNA working groups on radiological protection (RPWG) and on waste management and decommissioning (WM and DWG). This paper also briefly describes the WNA's participatory role, as of Summer 2005, in the International Atomic Energy Agency (IAEA) standard development committees on radiation safety (RASSC), waste safety (WASSC) and nuclear safety (NUSSC). This participation provides the worldwide nuclear industry with an opportunity to be part of IAEA's discussions on shaping changes to the control regime of IAEA safety standards. The review (and the prospect of a revision) of IAEA safety standards, which began in October 2005, makes this WNA participation and the industry's involvement at the national level timely and important. All of this excellent industry cooperation and team effort is done through 'collegial' exchanges between key industry experts, which help tackle important issues more effectively. The WNA is continuously looking to enhance its worldwide industry representation in these fields of expertise through the RPWG and WM and DWG

The Belgoprocess Strategy Relating to the Management of Materials from Decommissioning

International Nuclear Information System (INIS)

Teunckens, L.; Lewandowski, P.; Walthery, R.; Ooms, B.

2003-01-01

Belgium started its nuclear program quite early. The first installations were constructed in the fifties, and presently, more than 55 % of the Belgian electricity production is provided by nuclear power plants. After 30 years of nuclear experience, Belgium started decommissioning of nuclear facilities in the eighties with two main projects: the BR3-PWR plant and the Eurochemic reprocessing plant. The BR3-decommissioning project is carried out at the Belgian Nuclear Research Centre, while the decommissioning of the former Eurochemic reprocessing plant is managed and operated by Belgoprocess n.v., which is also operating the centralized waste treatment facilities and the interim storage for Belgian radioactive waste. Some fundamental principles have to be considered for the management of materials resulting from the decommissioning of nuclear installations, equipment and/or components, mainly based on the guidelines of the ''IAEA-Safety Fundamentals. The Principles of Radioactive Waste Management. Safety Series No. 111-F, IAEA, Vienna, 1995'' with respect to radioactive waste management. Two of the fundamental principles indicated in this document are specifically dealing with the strategy for the management of materials from decommissioning, ''Generation of radioactive waste shall be kept to the minimum practicable'' (seventh principle), and ''Radioactive waste shall be managed in such a way that it will not impose undue burdens on future generations'' (fifth principle). Based on these fundamental principles, Belgoprocess has made a straightforward choice for a strategy with minimization of the amount of materials to be managed as radioactive waste. This objective is obtained through the use of advanced decontamination techniques and the unconditional release of decontaminated materials. Unconditionally released materials are recycled, such as i.e., metal materials that are removed to conventional melting facilities, or are removed to conventional industrial

Proven approaches to organise a large decommissioning project, including the management of local stakeholder interests

International Nuclear Information System (INIS)

Rodriguez, A.

2005-01-01

Full text: Spanish experience holds a relatively important position in the field of the decommissioning of nuclear and radioactive facilities. Decommissioning projects of uranium concentrate mill facilities are near completion; some old uranium mine sites have already been restored; several projects for the dismantling of various small research nuclear reactors and a few pilot plants are at various phases of the dismantling process, with some already completed. The most notable Spanish project in this field is undoubtedly the decommissioning of the Vandellos 1 nuclear power plant that is currently ready to enter a safe enclosure, or dormancy, period. The management of radioactive wastes in Spain is undertaken by 'Empresa Nacional de Residuos Radioactivos, S.A.' (ENRESA), the Spanish national radioactive waste company, constituted in 1984. ENRESA operates as a management company, whose role is to develop radioactive waste management programmes in accordance with the policy and strategy approved by the Spanish Government. Its responsibilities include the decommissioning and dismantling of nuclear installations. Decommissioning and dismantling nuclear installations is an increasingly important topic for governments, regulators, industries and civil society. There are many aspects that have to be carefully considered, planned and organised in many cases well in advance of when they really need to be implemented. The goal of this paper is describe proven approaches relevant to organizing and managing large decommissioning projects, in particular in the case of Vandellos-1 NPP decommissioning. (author)

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

International Nuclear Information System (INIS)

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

2004-01-01

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

Approaches of Knowledge Management System for the Decommissioning of Nuclear Facilities

International Nuclear Information System (INIS)

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

2016-01-01

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

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 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)

Taking into account dismantling and decommissioning waste management in conception and operation phases

International Nuclear Information System (INIS)

Poncet, Philippe

2016-01-01

Managing waste during the Dismantling and Decommissioning (D and D) phase is quite specific and different from what it was during the operation phase. Indeed, waste generated during dismantling could present some analogy especially with regards to the radionuclides spectrum and contents. However waste from dismantling and cleanup could actually presents a lower level of radiologic activity but produced in much larger quantities, which requires new solutions. Moreover the characteristics and quantities of waste to be managed during D and D are highly depending on the way the facility was designed and also how it was actually operated during its life time. Taking future D and D into consideration in the early design as well as during the operation of new facilities is becoming more and more mandatory. It is now an explicit requirement set by safety authorities, to provide - in the license application for news plants - a description of design provisions and future plans for D and D as well as anticipated technical and financial impacts,. Two major aspects are driving the cost and complexity of future D and D operations: waste volumes by categories and occupational exposure while performing the work. To reduce such impacts, key approaches are to maintain areas clean, segregate the waste types and provide appropriate provisions in the design. The paper's first part describes the related design and operation concepts derived from lessons learned, and illustrations by examples are presented in a second part. (author)

Decommissioning of evaporation technology for processing liquid radioactive waste in UJV Rez, a. s

International Nuclear Information System (INIS)

Tous, M.; Otcovsky, T.; Podlaha, J.

2015-01-01

The UJV Rez, a. s. is the main leader in processing institutional radioactive waste (RAW) in the Czech Republic and the Waste Management Department has been established since the research reactor VVR-S (now LVR-15) was put in operation. Due to the large activities in nuclear research and engineering in the past, a big capacity of waste management technologies was needed. The low pressure compactor for volume reduction of solid RAW, as well as chemical pre-treatment technology of liquid RAW were installed and later the evaporation technology for effective processing the liquid RAW with the cementation and bituminization unit for final conditioning of concentrated liquid RAW were used. During the years of research reactor operation and research activities in UJV Rez, a. s. there were two installed evaporation technologies in row. After the latest evaporator lifetime, changes in liquid RAW production and together with higher decontamination factor requirements, this technology was decided to be decommissioned. The decommissioned evaporation technology was installed and put in operation in 1991. This technology was used for processing liquid aqueous RAW produced from internal research activities and of course for external producers and institutions (e.g. universities, medicine, research institutes, industry). The approved decommissioning plan was prepared and the licence for immediate decommissioning was obtained in 2012. Then the decommissioning project started. The preparing stages as dosimetric survey, expected material balance and of course initial decontamination activities were performed. Evaporation technology dismantling and processing the arising RAW were done by the internal staff of Waste Management Department. The total volume of produced RAW was 49,5 m 3 of RAW. The secondary liquid RAW (from decontamination) of amount 1,4 m 3 , contaminated sludge of amount 0,5 m 3 , solid RAW (construction steel) of amount 39,1 m 3 , solid compressible RAW (protective

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

Waste minimization value engineering workshop for the Los Alamos National Laboratory Omega West Reactor Decommissioning Project

International Nuclear Information System (INIS)

Hartnett, S.; Seguin, N.; Burns, M.

1995-01-01

The Los Alamos National Laboratory Pollution Prevention Program Office sponsored a Value Engineering (VE) Workshop to evaluate recycling options and other pollution prevention and waste minimization (PP/WMin) practices to incorporate into the decommissioning of the Omega West Reactor (OWR) at the laboratory. The VE process is an organized, systematic approach for evaluating a process or design to identify cost saving opportunities, or in this application, waste reduction opportunities. This VE Workshop was a facilitated process that included a team of specialists in the areas of decontamination, decommissioning, PP/WMin, cost estimating, construction, waste management, recycling, Department of Energy representatives, and others. The uniqueness of this VE Workshop was that it used an interdisciplinary approach to focus on PP/WMin practices that could be included in the OWR Decommissioning Project Plans and specifications to provide waste reduction. This report discusses the VE workshop objectives, summarizes the OWR decommissioning project, and describes the VE workshop activities, results, and lessons learned

Waste minimization value engineering workshop for the Los Alamos National Laboratory Omega West Reactor Decommissioning Project

Energy Technology Data Exchange (ETDEWEB)

Hartnett, S.; Seguin, N. [Benchmark Environmental Corp., Albuquerque, NM (United States); Burns, M. [Los Alamos National Lab., NM (United States)

1995-12-31

The Los Alamos National Laboratory Pollution Prevention Program Office sponsored a Value Engineering (VE) Workshop to evaluate recycling options and other pollution prevention and waste minimization (PP/WMin) practices to incorporate into the decommissioning of the Omega West Reactor (OWR) at the laboratory. The VE process is an organized, systematic approach for evaluating a process or design to identify cost saving opportunities, or in this application, waste reduction opportunities. This VE Workshop was a facilitated process that included a team of specialists in the areas of decontamination, decommissioning, PP/WMin, cost estimating, construction, waste management, recycling, Department of Energy representatives, and others. The uniqueness of this VE Workshop was that it used an interdisciplinary approach to focus on PP/WMin practices that could be included in the OWR Decommissioning Project Plans and specifications to provide waste reduction. This report discusses the VE workshop objectives, summarizes the OWR decommissioning project, and describes the VE workshop activities, results, and lessons learned.

Classifying decommissioning wastes for allocation to appropriate final repositories

International Nuclear Information System (INIS)

Alder, J.C.; Tunaboylu, K.

1982-01-01

For the safe disposal of radioactive wastes in different repositories, it is of advantage to classify them in well-defined conditioned categories, appropriate for final disposal. These categories, the so-called waste sorts are characterized by similar radionuclide distribution, similar nuclide-specific activity concentrations and similar waste matrix. A methodology is presented for classifying decommissioning wastes and is applied to the decommissioning wastes arising from a Swiss program of 6 GWe. The amounts and nuclide-specific activity inventories of the decommissioning waste sorts have been estimated. A first allocation into two different repository types has been performed. Such a classification enables one to define the source parameters for repository safety analysis and allows one to allocate the different waste categories into appropriate final repositories. This work presents a first iteration to determine which waste sorts belong to which repository type. The characteristics of waste sorts have to be better defined and the protective strength of the repository barriers has to be optimized. 7 references, 2 figures, 4 tables

The Importance of Enhancing Worldwide Industry Cooperation in Radiological Protection, Waste Management and Decommissioning - Views from the Global Nuclear Industry

International Nuclear Information System (INIS)

Saint-Pierre, S.

2008-01-01

The slow or stagnant rate of nuclear power generation development in many developed countries over the last two decades has resulted in a significant shortage in the population of mid-career nuclear industry professionals. This shortage is even more pronounced in some specific areas of expertise such as radiological protection, waste management and decommissioning. This situation has occurred at a time when the renaissance of nuclear power and the globalization of the nuclear industry are steadily gaining momentum and when the industry's involvement in international and national debates in these three fields of expertise (and the industry's impact on these debates) is of great relevance.This paper presents the World Nuclear Association (WNA) approach to building and enhancing worldwide industry cooperation in radiological protection, waste management and decommissioning, which is manifested through the activities of the two WNA working groups on radiological protection (RPWG) and on waste management and decommissioning (WM and DWG). This paper also briefly describes the WNA's participatory role, as of Summer 2005, in the International Atomic Energy Agency (IAEA) standard development committees on radiation safety (RASSC), waste safety (WASSC) and nuclear safety (NUSSC). This participation provides the worldwide nuclear industry with an opportunity to be part of IAEA's discussions on shaping changes to the control regime of IAEA safety standards. The review (and the prospect of a revision) of IAEA safety standards, which began in October 2005, makes this WNA participation and the industry's involvement at the national level timely and important. All of this excellent industry cooperation and team effort is done through 'collegial' exchanges between key industry experts, which help tackle important issues more effectively. The WNA is continuously looking to enhance its worldwide industry representation in these fields of expertise through the RPWG and WM and DWG

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

Energy Technology Data Exchange (ETDEWEB)

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

1999-04-01

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

Review of decommissioning, spent fuel and radwaste management in Slovakia

International Nuclear Information System (INIS)

Jamrich, J.

2000-01-01

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

Present status of technology development on decommissioning and waste management in Nuclear Cycle Backend Directorate. Progress in 2009

International Nuclear Information System (INIS)

Takahashi, Kuniaki; Ishigami, Tsutomu; Funabashi, Hideyuki; Meguro, Yoshihiro; Tachibana, Mitsuo

2010-11-01

It is an important issue to take measures against the matters on decommissioning of retired nuclear facilities and management of low-level radioactive waste arising from research activities and operation of nuclear facilities, and the measures must be taken with rational way by ensuring the safety. As the development, improvement, and proper deployment of technologies will be key factors, a technology development program is under way in Nuclear Cycle Backend Directorate taking account of these matters in cooperation with research and development institutes/centers in Japan Atomic Energy Agency. The technology development items are selected from the viewpoints of systematic implementation of measures and cost reduction; these include the development of computer systems for planning and evaluation of decommissioning programs, supercritical CO 2 fluid leaching method for decontamination, nitrate-ion degradation method, simple and rapid determination method for radioactivity of radioactive waste, safety assessment for waste disposal and so on. This report describes outline and progress of the technology development program conducted in FY2009 by the research and development unit. (author)

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

International Nuclear Information System (INIS)

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

2015-01-01

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

Hands on versus remote techniques in waste management and decommissioning

International Nuclear Information System (INIS)

Asquith, J.D.

1994-01-01

The nuclear industry has many requirements for planned and uplanned physical interactions with radioactive materials or their environment. In each case a choice must be made as to whether the interaction should be made directly by the operator using a 'hands on' technique, wearing any necessary protective clothing, or by entirely remote techniques. In facilities where remote handling equipment has already been provided and planned for, remote techniques are usually the obvious choice. However in radioactive waste management and decommissioning there are many cases where unexpected requirements emerge, often for relatively short term activities, where the choice is more complex. This paper takes a look at the various factors which should be considered in order to make these decisions, an overview of the types of remote equipment available in the UK and some examples of the benefits which have resulted when remote techniques have been adopted in Britain

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

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

International Nuclear Information System (INIS)

2015-01-01

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

77 FR 64361 - Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level...

Science.gov (United States)

2012-10-19

... Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities AGENCY: Nuclear Regulatory Commission... 15, ``Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level... for low-level waste. DATES: Submit comments by November 15, 2012. Comments received after this date...

CEA's waste management policy and strategy. Lessons learned - 59201

International Nuclear Information System (INIS)

Dall'ava, Didier

2012-01-01

Document available in abstract form only. Full text of publication follows: Radioactive wastes are generated during operation as well as during the decontamination and dismantling of CEA's nuclear facility/installation. The safe and responsible management of radioactive wastes at all stages is an essential requirement of the regulatory system. The management covers the whole sequence of operations starting with the generation of waste and ending with its disposal. The disposal here means discarding of waste with no intention for retrieval. It is important to note here that the safety principles and practices that are applicable during the operational phase are also applicable during the decommissioning phase. As the radioactive waste arising is an inevitable outcome of decommissioning work, all the regulatory requirements associated with decommissioning remain in force in waste management. This presentation deals initially with the regulatory standards related to the management of wastes. As the management of radioactive wastes inevitably includes treatment and conditioning of wastes, following treatment and conditioning of wastes, storage, transportation and eventual disposal are the logical outcome of the radioactive wastes, processes are at any time improved based on the feedback experience and the lessons learned. (author)

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

Status of decommissioning and waste management in the Nuclear Science Research Institute of JAEA

International Nuclear Information System (INIS)

Okoshi, Minoru; Yamashita, Toshiyuki

2007-01-01

The Nuclear Science Research Institute (NSRI) of JAEA has some experiences of the decommissioning of research reactors and research laboratories including a reprocessing test facility. In order to dismantle those facilities safely, we paid much attention for the radiological protection of radiation workers taking into consideration of characteristics of each facility, especially to protect internal exposures. As the results of decommissioning activities, several thousands tons of solid radioactive wastes were generated. In the near future, we will start the treatment of these stored wastes by a super compactor, metal melting furnace and non-metal waste melting furnace to gain high volume reduction and to prepare stable waste forms for final disposal. In Japan, the clearance system was established in 2005 by amending the Nuclear Regulatory Law. The NSRI plans to release very slightly contaminated concrete debris for recycling, which was generated from the replacement of reactor core of research reactor (JRR-3), according to the clearance system. (author)

Strategy on radioactive waste management in Lithuania

International Nuclear Information System (INIS)

Poskas, P.; Adomaitis, J.E.

2003-01-01

In Lithuania about 70-80% of all electricity is generated at a single power station, Ignalian NPP which has two non-upgradable RBMK-1500 type reactors. The unit 1 will be closed by 2005. The decision on unit 2 should be made in Lithuanian Parliament very soon taking into consideration substantial long-term financial assistance from the EU, G7 and other states as well as international institutions. The Government approved the Strategy on Radioactive Waste Management in 2002. Objectives of this strategy are to develop the radioactive waste management infrastructure based on modern technologies and provide for the set of practical actions that shall bring management of radioactive waste in Lithuania in compliance with radioactive waste management principles of IAEA and with good practices in force in EU Member States. Ignalina NPP is undertaking a program of decommissioning support projects, financed by grants from the International Ignalina Decommissioning Support Fund, administered by the European Bank for Reconstruction and Development. This program comprises also the implementation of investment projects in a number of pre-decommissioning facilities including the management of radioactive waste and spent nuclear fuel. (orig.)

International trends of radioactive waste management

International Nuclear Information System (INIS)

Luo Shanggeng

1989-01-01

The new trends of radioactive waste management in the world such as focusing on decreasing the amount of radioactive wastes, developing decontamination and decommissioning technology, conscientious solution for radiactive waste disposal, carrying out social services of waste treatment and quality assurance are reviewed. Besides, comments and suggestions are presented. Key words Radioactive waste management, Radioactive waste treatment, Radioactive waste disposal

Progress on Radiochemical Analysis for Nuclear Waste Management in Decommissioning

DEFF Research Database (Denmark)

Hou, Xiaolin; Qiao, Jixin; Shi, Keliang

With the increaed numbers of nuclear facilities have been closed and are being or are going to be decommissioned, it is required to characterise the produced nuclear waste for its treatment by identification of the radionuclides and qualitatively determine them. Of the radionuclides related...... separation of radionuclides. In order to improve and maintain the Nodic competence in analysis of radionculides in waste samples, a NKS B project on this topic was launched in 2009. During the first phase of the NKS-B RadWaste project (2009-2010), a good achivement has been reached on establishment...... of collaboration, identifing the requirements from the Nordic nuclear industries and optimizing and development of some analytical methods (Hou et al. NKS-222, 2010). In the year 2011, this project (NKS-B RadWaste2011) continued. The major achievements of this project in 2011 include: (1) development of a method...

Decommissioning and radwaste management in Spain

International Nuclear Information System (INIS)

Colino, A.

2004-01-01

The management of radioactive wastes in Spain is undertaken by 'Empresa Nacional de Residuos Radioactivos, S.A.' (ENRESA), the Spanish national radioactive waste company, constituted in 1984. ENRESA operates as a management company, whose role is to develop radioactive waste management programs in accordance with the policy and strategy approved by the Spanish government. Its responsibilities include the decommissioning and dismantling of nuclear installations. ENRESA is a state company whose shareholders are CIEMAT (Centre for Energy-Related, Environmental and Technological Research), previously known as the 'Junta de Energia Nuclear' (Nuclear Energy Council) and SEPI (State Industrial Holding Company). Both of them are governmental institutions with an eighty and twenty percent of the company respectively. In 1980 the Spanish Nuclear Safety Council (CSN) was constituted as the sole competent organisation in the field of nuclear safety and radiological protection, and in general is responsible for regulating and supervising nuclear installations. This organisation, governed by a legal statute, is independent from the administration and reports directly to parliament. (author)

Radioactive waste management

International Nuclear Information System (INIS)

Kawakami, Yutaka

2008-01-01

Radioactive waste generated from utilization of radioisotopes and each step of the nuclear fuel cycle and decommissioning of nuclear facilities are presented. On the safe management of radioactive waste management, international safety standards are established such as ''The Principles of Radioactive Waste Management (IAEA)'' and T he Joint Convention on the Safety of Radioactive Waste Management . Basic steps of radioactive waste management consist of treatment, conditioning and disposal. Disposal is the final step of radioactive waste management and its safety is confirmed by safety assessment in the licensing process. Safety assessment means evaluation of radiation dose rate caused by radioactive materials contained in disposed radioactive waste. The results of the safety assessment are compared with dose limits. The key issues of radioactive waste disposal are establishment of long term national strategies and regulations for safe management of radioactive waste, siting of repository, continuity of management activities and financial bases for long term, and security of human resources. (Author)

National perspective on waste management

International Nuclear Information System (INIS)

Crandall, J.L.

1980-01-01

Sources of nuclear wastes are listed and the quantities of these wastes per year are given. Methods of processing and disposing of mining and milling wastes, low-level wastes, decommissioning wastes, high-level wastes, reprocessing wastes, spent fuels, and transuranic wastes are discussed. The costs and safeguards involved in the management of this radioactive wastes are briefly covered in this presentation

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

International Nuclear Information System (INIS)

2007-01-01

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

Perspectives concerning radioactive waste management

International Nuclear Information System (INIS)

Noynaert, L.

2013-01-01

The article presents a general overview of the principles of radioactive waste management as established by the International Atomic Energy Agency. Subsequently, research and development related to radioactive waste management at the Belgian Nuclear Research Center SCK·CEN is discussed. Different topical areas are treated including radioactive waste characterisation, decontamination and the long-term management of radioactive waste. The decommissioning of the BR3 reactor and the construction and the exploitation of the underground research laboratory HADES are cited as examples of the pioneering role that SCK·CEN has played in radioactive waste management.

Decommissioning and Waste Disposal Programme of NPP Krsko - How to Proceed in the Future

International Nuclear Information System (INIS)

Mele, I.; Zeleznik, N.; Levanat, I.; Lokner, V.

2006-01-01

By the agreement between Slovenia and Croatia on the ownership and exploitation of the NPP Krsko, which is effective since March 2003, the decommissioning and the disposal of spent fuel and low and intermediate level waste from NPP Krsko is the responsibility of both countries. In article 10 the agreement requires that within a year after putting it into force both parties jointly prepare a decommissioning and waste disposal programme with more detailed elaboration of these issues. According to these requirements such a programme was prepared by the waste management organisations from both countries - APO from Croatia and ARAO from Slovenia - and in March 2004 submitted to the Intergovernmental Commission for adoption. Later in 2004 the document was accepted also by both Governments and in Croatia also by the Parliament. By the agreement it is also anticipated that the decommissioning and waste disposal programmes be revised at least every 5 years. Such an approach is quite common and practiced in many countries, and some countries prepare revisions even more frequently. The purpose of these new revisions is two folded: on one hand to improve the technical solutions for the decommissioning as well as for waste disposal by including new or better known data and new technological developments and experience, and on the other hand to update the cost calculation of these future nuclear liabilities. Having in mind that these cost estimations are made for the rather distant future it is extremely important that regular updating and adjustment of estimates be performed in order to meet the future needs. Although the Decommissioning and Waste Disposal Programme has just recently passed the adoption procedure and its implementation has not yet been fully achieved, the time of the next revision is approaching fast. To make good progress in the next revision serious preparations including some strategic decisions should start immediately. The programme from 2004 was prepared

Decommissioning a nuclear reactor

International Nuclear Information System (INIS)

Montoya, G.M.

1991-01-01

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

Integration of knowledge management system for the decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Iguchi, Yukihiro; Yanagihara, Satoshi

2016-01-01

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

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)

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

International Nuclear Information System (INIS)

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

2010-01-01

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

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

International Nuclear Information System (INIS)

Kerr, Robert W.; Murdo Murray; Hunter Common

2008-01-01

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

Treatment of organic radioactive waste in decommissioning project

International Nuclear Information System (INIS)

Dimovic, S.; Plecas, I.

2003-01-01

This paper describes methods of treatment of organic radioactive waste in the aspect of its integral part of radioactive waste which will arise during decommissioning process of nuclear power reactor RA (author)

Assessment, evaluation, and testing of technologies for environmental restoration, decontamination, and decommissioning and high level waste management. Progress report

International Nuclear Information System (INIS)

Uzochukwu, G.A.

1997-01-01

Nuclear and commercial non-nuclear technologies that have the potential of meeting the environmental restoration, decontamination and decommissioning, and high-level waste management objectives are being assessed and evaluated. A detailed comparison of innovative technologies available will be performed to determine the safest and most economical technology for meeting these objectives. Information derived from this effort will be matched with the multi-objectives of the environmental restoration, decontamination and decommissioning, and high-level waste management effort to ensure that the best, most economical, and the safest technologies are used in decision making at USDOE-SRS. Technology-related variables will be developed and the resulting data formatted and computerized for multimedia systems. The multimedia system will be made available to technology developers and evaluators to ensure that the best, most economical, and the safest technologies are used in decision making at USDOE-SRS. Technology-related variables will be developed and the resulting data formatted and computerized for multimedia systems. The multimedia system will be made available to technology developers and evaluators to ensure that the safest and most economical technologies are developed for use at SRS and other DOE sites

Assessment, evaluation, and testing of technologies for environmental restoration, decontamination, and decommissioning and high level waste management. Progress report

Energy Technology Data Exchange (ETDEWEB)

Uzochukwu, G.A.

1997-12-31

Nuclear and commercial non-nuclear technologies that have the potential of meeting the environmental restoration, decontamination and decommissioning, and high-level waste management objectives are being assessed and evaluated. A detailed comparison of innovative technologies available will be performed to determine the safest and most economical technology for meeting these objectives. Information derived from this effort will be matched with the multi-objectives of the environmental restoration, decontamination and decommissioning, and high-level waste management effort to ensure that the best, most economical, and the safest technologies are used in decision making at USDOE-SRS. Technology-related variables will be developed and the resulting data formatted and computerized for multimedia systems. The multimedia system will be made available to technology developers and evaluators to ensure that the best, most economical, and the safest technologies are used in decision making at USDOE-SRS. Technology-related variables will be developed and the resulting data formatted and computerized for multimedia systems. The multimedia system will be made available to technology developers and evaluators to ensure that the safest and most economical technologies are developed for use at SRS and other DOE sites.

Radioactive waste management at AECL

International Nuclear Information System (INIS)

Gadsby, R.D.; Allan, C.J.

2003-01-01

AECL has maintained an active program in radioactive waste management since 1945, when the Canadian nuclear program commenced activities at the Chalk River Laboratories (CRL). Waste management activities have included operation of waste management storage and processing facilities at AECL's CRL and Whiteshell Laboratories (WL); operation of the Low Level Radioactive Waste Management Office on behalf of Natural Resources Canada to resolve historic radioactive waste problems (largely associated with radioactive ore recovery, transport and processing operations) that are the responsibility of the Federal Government; development of the concept and related technology for geological disposal of Canada's nuclear fuel waste; development of the Intrusion-Resistant Underground Structure (IRUS) disposal concept for low-level nuclear waste; development of dry storage technology for the interim storage of used fuel; and development and assessment of waste processing technology for application in CANDU nuclear power plants and at CRL and WL. Today these activities are continuing. In addition, AECL is: preparing to decommission the nuclear facilities at WL; carrying out a number of smaller decommissioning projects at CRL; putting in place projects to upgrade the low-level liquid waste processing capabilities of the CRL Waste Treatment Centre, recover and process highly active liquid wastes currently in storage, and recover, condition and improve the storage of selected fuel wastes currently stored in below-ground standpipes in the CRL waste management areas; and assessing options for additional remediation projects to improve the management of other wastes currently in storage and to address environmental contamination from past practices. (author)

Development of recycling techniques on decommissioning concrete waste

International Nuclear Information System (INIS)

Ishikura, Takeshi; Oguri, Daiichiro; Sukekiyo, Mitsuaki

2000-01-01

Nuclear Power Engineering Corporation (NUPEC) has been developing decommissioning techniques, implemented under a contract with the Ministry of International Trade and Industry (MITI), to verify and improve the performance of the key decommissioning techniques. One of main themes is on concrete recycling techniques, which deals with high quality aggregate retrieval from concrete waste, high efficient usage of the by-product powder to recycling products, and effective usage of radioactive concrete to filling material for waste form. This paper describes progress and accomplishment on the concrete recycling technique development which started in 1996. (author)

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

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)

Prospects of nuclear waste management and radioactive waste management

International Nuclear Information System (INIS)

Koprda, V.

2015-01-01

The policy of radioactive waste management in the Slovak Republic is based on the principles defined by law on the National Nuclear Fund (NJF) and sets basic objectives: 1 Safe and reliable nuclear decommissioning; 2 The minimization of radioactive waste; 3. Selection of a suitable fuel cycle; 4 Safe storage of radioactive waste (RAW) 5 Security chain management of radioactive waste and spent nuclear fuel (SNF); 6 Nuclear safety; 7 The application of a graduated approach; 8 Respect of the principle 'a polluter pays'; 9 Objective decision-making process; 10 Responsibility. In connection with the above objectives, it appears necessary to build required facilities that are listed in this article.

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

International Nuclear Information System (INIS)

2003-01-01

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

Volume Reduction of Decommissioning Burnable Waste with Oxygen Enrich Incinerator

International Nuclear Information System (INIS)

Min, B. Y.; Yang, D. S.; Lee, K. W.; Choi, J. W.

2016-01-01

The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. This paper covers the general facility operation of an oxygen-enriched incinerator for the treatment of decommissioning wastes generated from a decommissioning project. The combustible wastes have been treated by the utilization of incinerator the capacity of the average 20 kg/hr. The decommissioning combustible waste of about 31 tons has been treated using Oxygen Enriched incinerator by at the end of 2016. The off-gas flow and temperature were maintained constant or within the desired range. The measured gases and particulate materials in the stack were considerably below the regulatory limits.

Volume Reduction of Decommissioning Burnable Waste with Oxygen Enrich Incinerator

Energy Technology Data Exchange (ETDEWEB)

Min, B. Y.; Yang, D. S.; Lee, K. W.; Choi, J. W. [KAERI, Daejeon (Korea, Republic of)

2016-05-15

The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. This paper covers the general facility operation of an oxygen-enriched incinerator for the treatment of decommissioning wastes generated from a decommissioning project. The combustible wastes have been treated by the utilization of incinerator the capacity of the average 20 kg/hr. The decommissioning combustible waste of about 31 tons has been treated using Oxygen Enriched incinerator by at the end of 2016. The off-gas flow and temperature were maintained constant or within the desired range. The measured gases and particulate materials in the stack were considerably below the regulatory limits.

Management of solid wastes during decommissioning of research reactors. Evaluation of gross clearance levels and mathematical simulation of solid waste assay techniques

International Nuclear Information System (INIS)

Gopalakrishnan, R.K.; Sobhan Babu, K.; Sharma, D.N.

2008-01-01

Full text: Decommissioning of nuclear facilities constitute a challenge mainly due to the huge and complex nature of radioactive waste generated during this process. In the context of management and disposal of waste and reuse/recycle of usable materials during decommissioning of reactors, clearance levels for relevant radio nuclides are of vital importance. Radionuclide specific clearance levels are developed by IAEA and such levels allow the facility for free release of materials to the environment without further regulatory consideration. An effort has been made in this paper to establish clearance levels for radionuclides associated with various system and structural components of a research reactor and rather than radionuclide specific clearance levels, these values are derived for gross activity concentration, which is more practical for radioactive waste categorization, disposal and reuse or recycle of usable materials. The first step towards the derivation of clearance levels is the calculation of annual doses relating to unit activity concentration for each nuclide using various enveloping scenarios. After the estimation of doses, the limiting enveloping scenario (the one that gives the highest dose) is identified. The clearance levels are then derived by dividing the reference dose level (10 μSv/y) by the annual dose calculated per unit activity concentration for the limiting enveloping scenario The clearance level for gross beta-gamma activity concentration is then evaluated as the product of the limiting clearance level and the number of radionuclides characterized for the structural components. Simulation studies were also carried out for the design of a monitoring system for estimation of activity concentration of the decommissioned materials, especially rubbles/ concrete, using mathematical models. Conventional solid waste assay techniques would not suffice to the requirement of decommissioning waste categorization since very low level activity

The Canadian approach to nuclear codes and standards. A CSA forum for development of standards for CANDU: radioactive waste management and decommissioning

International Nuclear Information System (INIS)

Shin, T.; Azeez, S.; Dua, S.

2006-01-01

Together with the Canadian Standards Association (CSA), industry stakeholders, governments, and the public have developed a suite of standards for CANDU nuclear power plants that generate electricity in Canada and abroad. In this paper, we will describe: CSA's role in national and international nuclear standards development; the key issues and priority projects that the nuclear standards program has addressed; the new CSA nuclear committees and projects being established, particularly those related to waste management and decommissioning; the hierarchy of nuclear regulations, nuclear, and other standards in Canada, and how they are applied by AECL; the standards management activities; and the future trends and challenges for CSA and the nuclear community. CSA is an accredited Standards Development Organization (SDO) and part of the international standards system. CSA's Nuclear Strategic Steering Committee (NSSC) provides leadership, direction, and support for a standards committee hierarchy comprised of members from a balanced matrix of interests. The NSSC strategically focuses on industry challenges; a new nuclear regulatory system, deregulated energy markets, and industry restructuring. As the first phase of priority projects is nearing completion, the next phase of priorities is being identified. These priorities address radioactive waste management, environmental radiation management, decommissioning, structural, and seismic issues. As the CSA committees get established in the coming year, members and input will be solicited for the technical committees, subcommittees, and task forces for the following related subjects: Radioactive Waste Management; a) Dry Storage of Irradiated Fuel; b) Short-Term Radioactive Waste Management; c) Long-Term Storage and Disposal of Radioactive Waste. 2. Decommissioning Nuclear Power is highly regulated, and public scrutiny has focused Codes and Standards on public and worker safety. Licensing and regulation serves to control

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

Change-management. From commercial power operation to post power operation and decommissioning

International Nuclear Information System (INIS)

Wasinger, Karl

2015-01-01

Transition from power generation to decommissioning challenges utilities. Power generation is mainly characterized by a stable working environment and constant workload, decommissioning and dismantling, however, by transformation and change. Also, changing requirements for the workforce's skills challenge the organization and its senior management. Ensuring effective and efficient performance, while maintaining motivation of staff, requires adjustment of management processes as well as of operational organization and human resources management. AREVA has more than 20 years of experience in decommissioning of own nuclear fuel cycle plants in France, as well as of other large plants and power reactors in Germany, the United Kingdom and the US. Therefore, the group has developed and successfully implemented integrated change management processes. The implementation of well-established and proven methods, developed by the productive industry and adjusted to the nuclear regulatory requirements, significantly improves the performance and efficiency of means and methods in use. The AREVA Performance Improvement Process defines concrete approaches to identify and improve potential deficits of productivity in six main areas (decommissioning scenarios and stra-tegies, waste treatment and logistics, operations management, supply chain, regulatory monitoring and controls as well as dismantling operation). Nuclear plant and facility owners around the world benefit from AREVA experts well experienced in execution of large and complex decommissioning projects.

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)

Development for recycle of dismantled metal wastes by decommissioning of NPP

International Nuclear Information System (INIS)

Asami, Tomohiro; Sato, Hiroshi; Hatakeyama, Mutsuo

2007-01-01

For recycle of dismantled metal wastes generated by the decommissioning of nuclear power plant, we examined a melting test for melting characterization of stainless steel scrap, designed the conceptual process to produce the recycle products, and developed a recycle cost evaluation code which is useful to make a rational planning for the waste management program (cost, determination of process, etc.) of these metal wastes. This report gives the summary of these development carried out from 2001 to 2005. This work was performed under the sponsorship of Ministry of Education, Culture, Sports, Science and Technology of Japan. (author)

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

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).

Study on decommissioning

International Nuclear Information System (INIS)

2012-01-01

This project consists of researches on (1) establishment of review plan on application of decommissioning, (2) establishment of specific method to confirm decommissioning completion, of decommissioning and (3) establishment of radioactive waste management guideline during dismantling and (4) development of the regulatory system on decommissioning in response to Fukushima Daiichi NPP accident. About researches on establishment of review plan on application of decommissioning. 'Planning of the Commercial Power Reactor Decommissioning:2001' which was published by Atomic Energy Society of Japan, was evaluated whether it suited the requirement for the decommissioning stipulated in the law, and the draft evaluation report was prepared. About researches on establishment of specific method to confirm decommissioning completion, technical information of practical procedures on the confirmation in U.S.A. were organized based on MARSSIM (Multi-Agency Radiation Survey and Site Investigation Manual, NUREG-1575) and applicability of MARSSIM on the confirmation in Japan was examined. Exposed doses for public during decommissioning period were estimated to study dose criterion of the confirmation. Radioactive concentrations in the soil of Tokai and Hamaoka NPP caused by the Fukushima Daiichi NPP accident were also investigated. About researches on establishment of radioactive waste management guideline during dismantling, one concrete core was sampled in biological shield of the Tokai NPP and radioactive concentrations were investigated. About researches on development of the regulatory system on decommissioning in response to Fukushima Daiichi NPP accident, present status of Three Mile Island Unit 2 and Chernobyl NPP Unit 4 were investigated. Present status of regulatory systems for decommissioning in foreign countries taken in consideration of the accident was also researched. (author)

CEGB's radioactive waste management strategy

International Nuclear Information System (INIS)

Passant, F.H.; Maul, P.R.

1989-01-01

The Central Electricity Generating Board (CEGB) produces low-level and intermediate-level radioactive wastes in the process of operating its eight Magnox and five Advanced Gas Cooled Reactor (AGR) nuclear power stations. Future wastes will also arise from a programme of Pressurised Water Reactors (PWRs) and the decommissioning of existing reactors. The paper gives details of how the UK waste management strategy is put into practice by the CEGB, and how general waste management principles are developed into strategies for particular waste streams. (author)

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

Decommissioning Programme Management: reducing risk and cost while accelerating schedules through improved planning, Earned Value Management and safe work execution

International Nuclear Information System (INIS)

Hansen, S.E.

2008-01-01

CH2M HILL experience includes more than two decades of managing nuclear facilities and providing clean-up and operations support for commercial and government facilities worldwide. Our expertise ranges from decommissioning and defence sector businesses to nuclear technology development and innovation. Our approach places top priority on the safe execution of work while reducing both risk and cost. Our nuclear services include: programme management, nuclear safety analysis, radiological protection, radioactive waste management, nuclear remediation, nuclear materials and waste transportation management, nuclear safeguards and security services, and nuclear decontamination and decommissioning. This paper will discuss our approach which has resulted in a strong track record of accelerating schedules and reducing costs of major nuclear programmes, including Rocky Flats, Idaho, and our work at UKAEA sites. (author)

Proceedings of the 1991 Joint International Waste Management Conference

International Nuclear Information System (INIS)

1991-01-01

This proceedings contains articles of 1991 joint international waste management conference. It was held on October 21-23, 1991 in Seoul, Korea. The main subject titles are as follows: national waste management programs, waste management in developing countries, incineration - development and experience, site characterization and performance assessment, waste disposal, decontamination and decommissioning, waste solidification and waste form, radioactive waste processing, mixed waste and others (Yi, J. H.)

A necessity for research in the recycling of concrete waste from the decommissioning

International Nuclear Information System (INIS)

Seo, Ha Na; Whang, Joo Ho

2009-01-01

Construction of the I/LLW disposal site is now underway in Gyeongju. When completed it will be able to store 100,000 radioactive waste drums in a geologically deep disposal site; hence, a method for disposing of another 700,000 drums will be discussed. Kori-1 is continuously being safely operated even after passing its 30 years designated life span. However, because 12 more nuclear power plants will operate past their designated life span by 2030, the necessity for research about their decommissioning will increase. Approximately 6,200 tons of radioactive waste will be generated from each decommissioned plant. It will be difficult to store all of the waste in Gyeongju due to cost and efficiency issues. For these reasons it is needed to discuss recycling methods for minimizing radioactive waste during decommissioning. This study suggests a scenario for recycling concrete waste of a decommissioned disposal site as crushed rock and also presents prior research for concrete waste recycling

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

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.

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)

Economic challenges of radioactive waste management

International Nuclear Information System (INIS)

Soderberg, O.

1996-01-01

The management of long lived waste, and the decommissioning of nuclear power plants represent major economic challenges. Power production is an activity that produces benefits now, but considerable costs will appear up to one or two generations later. Who should pay for such inevitable costs? How do you guarantee a lifetime ahead that money will be available when needed? The issues of inter-generational equity and management of the uncertainties involved in estimating future costs decommissioning and waste management, the development of the concept of trust funds and the overseeing of long-term financial liabilities in this field are discussed. The paper contains an overview of how such challenges are met in different countries. Information for the general public about economics in connection with nuclear waste management needs to combine the conflicting demands of accuracy and simplification. Systems for financing future costs are discussed, together with proposed guarantees and suggestions for the efficient organisation of such funding. The present Swedish system is explained. This basically requires license holders to pay a yearly fee to cover the costs of the safe handling and final disposal of nuclear fuel used in the reactor, the safe decommissioning and dismantling of the reactor, and the R and D activities required to achieve this. With recent suggestions for improving the reliability of the 1981 Swedish nuclear waste management funding system as a basis, five information messages rom the Government and responsible authorities are discussed. (author)

Radioactive Waste Management Program Activities in Croatia

International Nuclear Information System (INIS)

Matanic, R.

2000-01-01

The concept of radioactive waste management in Croatia comprises three major areas: management of low and intermediate level radioactive waste (LILRW), spent fuel management and decommissioning. All the work regarding radioactive waste management program is coordinated by Hazardous Waste Management Agency (APO) and Croatian Power Utility (HEP) in cooperation with other relevant institutions. Since the majority of work has been done in developing low and intermediate level radioactive waste management program, the paper will focus on this part of radioactive waste management, mainly on issues of site selection and characterization, repository design, safety assessment and public acceptance. A short description of national radioactive waste management infrastructure will also be presented. (author)

Large transport packages for decommissioning waste

International Nuclear Information System (INIS)

Price, M.S.T.

1988-03-01

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

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

The Research Status for Decommissioning and Radioactive Waste Minimization of HTR-PM

International Nuclear Information System (INIS)

Li Wenqian; Li Hong; Cao Jianzhu; Tong Jiejuan

2014-01-01

Decommissioning of the high-temperature gas-cooled reactor-pebble bed module (HTR-PM) as a part of the nuclear power plant, is very important during the early design stage of the construction, and it is under study and research currently. This article gives a thorough description of the current decommissioning study status of HTR-PM. Since HTR-PM has its features such as adopting a large amount of graphite, the waste inventory and characterization will be quite different from other type of reactors, new researches should be carried out and good lessons of practices and experiences should be learned from international other reactors, especially the AVR. Based on the new international regulations and Chinese laws, a comprehensive decommissioning program should be proposed to guarantee the HTR-PM will succeed in every stage of the decommissioning, such as defueling, decontamination, dismantling, demolition, waste classification and disposal, etc. In the meantime, the minimization of the radioactive waste should be taken into account during the whole process - before construction, during operation and after shut down. In this article, the decommissioning strategy and program conception of HTR-PM will be introduced, the radiation protection consideration during the decommissioning activities will be discussed, and the research on the activation problem of the decommissioning graphite will be introduced. (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.)

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

The characterization of cement waste form for final disposal of decommissioned concrete waste

International Nuclear Information System (INIS)

Lee, K.W.; Lee, Y.J.; Hwang, D.S.; Moon, J.K.

2015-01-01

Since the decommissioning of nuclear plants and facilities, large quantities of slightly contaminated concrete waste have been generated. In Korea, the decontamination and decommissioning of the KRR-1, 2 at the KAERI have been under way. In addition, 83 drums of 200 l, and 41 containers of 4 m 3 of concrete waste were generated. Conditioning of concrete waste is needed for final disposal. Concrete waste is conditioned as follows: mortar using coarse and fine aggregates is filled into a void space after concrete rubble pre-placement into 200 l drums. Thus, this research developed an optimizing mixing ratio of concrete waste, water, and cement, and evaluated the characteristics of a cement waste form to meet the requirements specified in the disposal site specific waste acceptance criteria. The results obtained from compressive strength test, leaching test, and thermal cycling test of cement waste forms conclude that the concrete waste, water, and cement have been suggested to have 75:15:10 as the optimized mixing ratio. In addition, the compressive strength of cement waste form was satisfied, including fine powder up to a maximum 40 wt% in concrete debris waste of about 75%. (authors)

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.

Optimizing decommissioning and waste management

International Nuclear Information System (INIS)

McKeown, J.

2000-01-01

UKAEA has clarified its future purpose. It is a nuclear environmental restoration business. Its proud history of being at the forefront of nuclear research now provides decommissioning challenges of unique breadth. The methods employed, and in some cases developed, by UKAEA to assist in the optimization of its overall work programme are identified. (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

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

The 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

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

ITER waste management

International Nuclear Information System (INIS)

Rosanvallon, S.; Na, B.C.; Benchikhoune, M.; Uzan, J. Elbez; Gastaldi, O.; Taylor, N.; Rodriguez, L.

2010-01-01

ITER will produce solid radioactive waste during its operation (arising from the replacement of components and from process and housekeeping waste) and during decommissioning (de-activation phase and dismantling). The waste will be activated by neutrons of energies up to 14 MeV and potentially contaminated by activated corrosion products, activated dust and tritium. This paper describes the waste origin, the waste classification as a function of the French national agency for radioactive waste management (ANDRA), the optimization process put in place to reduce the waste radiotoxicity and volumes, the estimated waste amount based on the current design and maintenance procedure, and the overall strategy from component removal to final disposal anticipated at this stage of the project.

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

Management routes for materials arising from the decommissioning of a PWR reactor

International Nuclear Information System (INIS)

Klein, M.; Demeulemeester, Y.; Moers, S.; Ponnet, M.

2001-01-01

The management of wastes from decommissioning is described for the on-going dismantling of the BR3 PWR small reactor. The incentive is put on the radionuclides characterization, the description of the various waste streams, the conditioning techniques for low radioactive waste (LAW) to high radioactive waste (RAW), the alternative evacuation routes (recycling in the nuclear, free release by decontamination) and the minimization of secondary wastes during dismantling. Finally, some considerations are given on the overall dismantling cost and on the relative costs of the various evacuation routes. (author)

SGDes project. Decommissioning management system of Enresa; Proyecto SGDes. Sistema de Gestion de Desmantelamiento de Enresa

Energy Technology Data Exchange (ETDEWEB)

Fernandez Lopez, M.; Julian, A. de

2013-03-01

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

Radioactive waste management

International Nuclear Information System (INIS)

Tsoulfanidis, N.

1991-01-01

The management of radioactive waste is a very important part of the nuclear industry. The future of the nuclear power industry depends to a large extent on the successful solution of the perceived or real problems associated with the disposal of both low-level waste (LLW) and high-level waste (HLW). All the activities surrounding the management of radioactive waste are reviewed. The federal government and the individual states are working toward the implementation of the Nuclear Waste Policy Act and the Low-Level Waste Policy Act. The two congressional acts are reviewed and progress made as of early 1990 is presented. Spent-fuel storage and transportation are discussed in detail as are the concepts of repositories for HLW. The status of state compacts for LLW is also discussed. Finally, activities related to the decommissioning of nuclear facilities are also described

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.)

Development of recycling techniques for nuclear power plant decommissioning waste

International Nuclear Information System (INIS)

Ishikura, Takeshi; Oguri, Daiichiro; Abe, Seiji; Ohnishi, Kazuhiko

2003-01-01

Recycling of concrete and metal waste will provide solution to reduce waste volume, contributing to save the natural resources and to protect the environment. Nuclear Power Engineering Corporation has developed techniques of concrete and metal recycling for decommissioning waste of commercial nuclear power plants. A process of radioactive concrete usage for mortar solidification was seen to reduce concrete waste volume by 2/3. A concrete reclamation process for high quality aggregate was confirmed that the reclaimed aggregate concrete is equivalent to ordinary concrete. Its byproduct powder was seen to be utilized various usage. A process of waste metal casting to use radioactive metal as filler could substantially decrease the waste metal volume when thinner containers are applied. A pyro-metallurgical separation process was seen to decrease cobalt concentration by 1/100. Some of these techniques are finished of demonstration tests for future decommissioning activity. (author)

Argentina: Disposal aspects of RA-1 research reactor decommissioning waste

Energy Technology Data Exchange (ETDEWEB)

Harriague, S; Barberis, C; Cinat, E; Grizutti, C; Scolari, H [Comision Nacional de Energia Atomica, Buenos Aires (Argentina)

2007-12-15

The objective of the project is to analyze disposal aspects of waste from total dismantling of Argentinean research reactors, starting with the oldest one, 48 years old RA-1. In order to estimate decommissioning waste, data was collected from files, area monitoring, measurements, sampling to measure activity and composition, operational history and tracing of operational incidents. Measurements were complemented with neutron activation calculations. Decommissioning waste for RA-1 is estimated to be 71.5 metric tons, most of it concrete (57 tons), the rest being steels, lead and reflector graphite (4.8 tons). Due to their low specific activities, no disposal problems are foreseen in the case of metals and concrete. Disposal of aluminium, steel, lead and concrete is analyzed. On the contrary, as the country has no experience in managing graphite radioactive waste, work was concentrated on that material. Stored (Wigner) energy may exist in RA-1 graphite reflectors irradiated at room temperature. Evaluation of stored energy by calorimetric methods is proposed, and its annealing by inductive heating; HEPA filters should be used to deal with gaseous activity emissions, mainly Cl-36 and C-14. Galvanic corrosion, dust explosion, ignition and oxidation can be addressed and should not become disposal problems. Care must be taken with graphite dust generation and disposal, due to wetting and flotation problems. Lessons learned from the project are presented, and the benefits of sharing international experience are stressed. (author)

Preliminary study on recycling of metallic waste from decommissioning of nuclear power plant for cask

International Nuclear Information System (INIS)

Ohe, Koichiro; Kato, Osamu; Saegusa, Toshiari

1999-01-01

Preliminary study was made on technology required to recycle of metallic waste from decommissioning for spent fuel storage cask and on quantity of the cask which can be produced by the metallic waste. The technical and institutional issues for the recycling were studied. The metallic waste from decommissioning may be technically used to a certain degree for manufacturing the casks. However, there were some technical issues to be solved. For example, the manufacturing factories should be established. The radioactive waste from the factories with radiation control should be handled and treated carefully. Quality of the cask should be properly controlled. The 'Clearance Levels' which allows to recycle decommissioning waste have been hardly enacted in Japan. Technical and economic evaluation on recycling of metallic waste from decommissioning for spent fuel storage cask should be conducted again after progress in recycling of radioactive waste of which radioactivity is below the 'Clearance Levels' in Japan. (author)

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 and demolition of the Greifswald nuclear power station

International Nuclear Information System (INIS)

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

1995-01-01

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

Gas cooled reactor decommissioning. Packaging of waste for disposal in the United Kingdom deep repository

International Nuclear Information System (INIS)

Barlow, S.V.; Wisbey, S.J.; Wood, P.

1998-01-01

United Kingdom Nirex Limited has been established to develop and operate a deep underground repository for the disposal of the UK's intermediate and certain low level radioactive waste. The UK has a significant Gas Cooled Reactor (GCR) programme, including both Magnox and AGR (Advanced Gas-cooled Reactor) capacity, amounting to 26 Magnox reactors, 15 AGR reactors as well as research and prototype reactor units such as the Windscale AGR and the Windscale Piles. Some of these units are already undergoing decommissioning and Nirex has estimated that some 15,000 m 3 (conditioned volume) will come forward for disposal from GCR decommissioning before 2060. This volume does not include final stage (Stage 3) decommissioning arisings from commercial reactors since the generating utilities in the UK are proposing to adopt a deferred safe store strategy for these units. Intermediate level wastes arising from GCR decommissioning needs to be packaged in a form suitable for on-site interim storage and eventual deep disposal in the planned repository. In the absence of Conditions for Acceptance for a repository in the UK, the dimensions, key features and minimum performance requirements for waste packages are defined in Waste Package Specifications. These form the basis for all assessments of the suitability of wastes for disposal, including GCR wastes. This paper will describe the nature and characteristics of GCR decommissioning wastes which are intended for disposal in a UK repository. The Nirex Waste Package Specifications and the key technical issues, which have been identified when considering GCR decommissioning waste against the performance requirements within the specifications, are discussed. (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.)

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

International Nuclear Information System (INIS)

Destrait, L.

1998-01-01

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

Study on archive management for nuclear facility decommissioning projects

International Nuclear Information System (INIS)

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

2011-01-01

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

Decommissioning of the NPP A-1 heavy water management system

International Nuclear Information System (INIS)

Medved, J.; Rezbarik, J.; Vargovcik, L.; Vykukel, I.

2015-01-01

The paper deals with experience and techniques in the application of decontamination technology and remotely controlled robotic devices for the decontamination and dismantling of the heavy water management system during undergoing decommissioning process of the A-1 NPP as well as treatment of arising liquid waste All of these activities are characterized by high level of radioactivity and contamination. (authors)

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

International Nuclear Information System (INIS)

1994-03-01

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

Decommissioning of the ICI TRIGA Mark I reactor

International Nuclear Information System (INIS)

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

2000-01-01

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

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

Developing and initiating a public engagement process for a nuclear decommissioning and waste management program

International Nuclear Information System (INIS)

Badke, C.; Johnson, C.; Brooks, S.; MacCafferty, M.

2011-01-01

Public consultation is key to any major nuclear initiative, but how do you engage the public in a complex multi-site nuclear decommissioning and environmental restoration program that will last 70 years? A clear message of sound environmental stewardship throughout the process is critical to building the trust required to attract public interest and support. The Nuclear Legacy Liabilities Program (NLLP) manages Canada's nuclear legacy liabilities at Atomic Energy of Canada Limited (AECL) sites and is funded by the Government of Canada through Natural Resources Canada (NRCan). The objective of the NLLP is to safely and cost-effectively reduce the federal legacy liabilities and associated risks, based on sound waste management and environmental principles, in the best interest of Canadians. An important area of focus for the NLLP in both the short- and long-term is to inform the public, stakeholders and Aboriginal people about the Program, and to gather input on the long-term strategy for site restoration and waste management. This paper describes progress made to date on developing and initiating a public engagement process for the NLLP in the initial phase of the Program. Furthermore, it examines general best practices for public participation, specific challenges and opportunities which have been identified, as well as the next steps for communications activities related to the Program. (author)

Management of radioactive wastes from nuclear power plants

International Nuclear Information System (INIS)

1985-01-01

This Code of Practice defines the minimum requirements for the design and operation of structures, systems and components important for the management of radioactive wastes from thermal neutron nuclear power plants. The topics covered include design and operation of gaseous, liquid and solid waste systems, waste transport, storage and disposal, decommissioning wastes and wastes from unplanned events

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

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)

The effect of proposed changes to the IAEA transport regulations on decommissioning and other low level waste transportation

International Nuclear Information System (INIS)

Shetler, A.P.; Jayawardene, N.

1986-01-01

Ontario Hydro has studied the proposed changes to the IAEA Transport Regulations contained in the 1985 4th draft edition. The study shows that these proposed changes will have significant strategic and economic effects on the transportation of radioactive decommissioning and other low-level wastes. Under the 1985 4th draft edition, the definition of Low Specific Activity (LSA) material is revised and a new regulation is proposed which restricts the quantity of LSA material or Surface Contaminated Object (SCO) in a single package to that which would have an unshielded dose rate of 10 mSv/h (1 rem/h) at 3 m. The objective of this paper is to highlight the implications of the proposed regulatory changes. An example of the impact of these changes is presented by considering the transportation of typical CANDU decommissioning wastes which arise through piece-by-piece removal of a reactor assembly. The potential effect of the changes is that less decommissioning waste can be shipped in a single low-level waste package. This results in the requirement for so many small, low-level waste packages that Type B shipments are strategically and economically more attractive. However, use of Type B shipments would also result in higher dose uptake and waste management costs than under the 1973 Regulations

Waste management research abstracts vols. 23/24. Information on radioactive waste management research in progress or planned

International Nuclear Information System (INIS)

1999-01-01

The research abstracts contained in this issue have been collected during recent months and cover the period between March 1994 - June 1998. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. This issue contains 678 abstracts that present ongoing work in 33 countries and an international organization

Waste management research abstracts vols. 23/24. Information on radioactive waste management research in progress or planned

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

The research abstracts contained in this issue have been collected during recent months and cover the period between March 1994 - June 1998. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. This issue contains 678 abstracts that present ongoing work in 33 countries and an international organization.

Radioactive waste management: International peer reviews

International Nuclear Information System (INIS)

Warnecke, E.; Bonne, A.

1995-01-01

The Agency's peer review service for radioactive waste management - known as the Waste Management Assessment and Technical Review Programme (WATRP) - started in 1989, building upon earlier types of advisory programmes. WATRP's international experts today provide advice and guidance on proposed or ongoing radioactive waste management programmes; planning, operation, or decommissioning of waste facilities; or on legislative, organizational, and regulatory matters. Specific topics often cover waste conditioning, storage, and disposal concepts or facilities; or technical and other aspects of ongoing or planned research and development programmes. The missions can thus contributed to improving waste management systems and plans, and in raising levels of public confidence in them, as part of IAEA efforts to assist countries in the safe management of radioactive wastes. This article presents a brief overview of recent WATRP missions in Norway, Slovak Republic, Czech Republic and Finland

Direction in charge of the management of wastes. 1998 activity report

International Nuclear Information System (INIS)

1998-01-01

This document is the 1998 activity report of the direction in charge of the management of radioactive wastes (DGD) of the French atomic energy commission (CEA). The role of the DGD is the elimination of radioactive wastes, the management of spent fuels, the cleansing and dismantling of shut-down and decommissioned installations at the CEA. This report summarizes the highlights of the 1998 year: the cleansing plan of the CEA (current policy, plan scheme, quality assurance, financing, public relation); the radioactive wastes (general considerations, management of liquid and solid effluents, management of sealed sources, modernization of equipments and new projects, relations with the Andra, studies in progress); the spent fuels (general considerations, solutions, long-term storage); the dismantling of shut-down installations (general considerations about decommissioning, dismantling actions at the CEA, main works performed, dismantling actions in progress); the management of wastes at the CEA-direction for military applications (DAM); the cleansing of the CEA-Marcoule site; 1998 status of the management of wastes (appendix). (J.S.)

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 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..

Radioactive waste management in France

International Nuclear Information System (INIS)

Antonioli, S.; Manet, M.

1985-01-01

The experience acquired over forty years through an extensive nuclear power program has enabled France to develop a corresponding comprehensive waste management policy, covering rules and regulations, health and safety aspects for both the short and the long term, technologies from the design of installations to their decommissioning and the conditioning, transport and disposal of the entailed wastes. The various partners, their role and responsibilities, specially those involved in industrial activities, are briefly introduced. The principles and objectives of French waste management policy, the techniques adopted and the long term disposal program are then presented [fr

Radioactive waste management in France

International Nuclear Information System (INIS)

Lefevre, J.; Brignon, P.

1986-01-01

The experience acquired over forty years through an extensive nuclear power program has enabled FRANCE to develop a corresponding comprehensive waste management policy, covering rules and regulations, health and safety aspects for both the short and the long term, technologies from the design of installations to their decommissioning, and the conditioning, transport and disposal of the entailed wastes. The various partners, their role and responsabilities, specially those involved in industrial activities, are briefly introduced. The principles and objectives of French waste management policy, the techniques adopted and the long term disposal program are then presented [fr

47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key Topics / Enhanced safety and operation excellence and decommissioning experience and Waste management solutions

Energy Technology Data Exchange (ETDEWEB)

Salnikova, Tatiana [AREVA GmbH, Erlangen (Germany); Schaffrath, Andreas [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany)

2016-10-15

Summary report on the Key Topics ''Enhanced Safety and Operation Excellence'' and ''Decommissioning Experience and Waste Management Solutions'' of the 47{sup th} Annual Conference on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016. Other Sessions of AMNT 2016 have been and will be covered in further issues of atw.

Management of Radioactive Waste after a Nuclear Power Plant Accident

International Nuclear Information System (INIS)

Strand, Per; Laurent, Gerard; Rindo, Hiroshi; Georges, Christine; Ito, Eiichiro; Yamada, Norikazu; Iablokov, Iuri; Kilochytska, Tatiana; Jefferies, Nick; Byrne, Jim; Siemann, Michael; Koganeya, Toshiyuki; Aoki, Hiroomi

2016-01-01

The NEA Expert Group on Fukushima Waste Management and Decommissioning R and D (EGFWMD) was established in 2014 to offer advice to the authorities in Japan on the management of large quantities of on-site waste with complex properties and to share experiences with the international community and NEA member countries on ongoing work at the Fukushima Daiichi site. The group was formed with specialists from around the world who had gained experience in waste management, radiological contamination or decommissioning and waste management R and D after the Three Mile Island and Chernobyl accidents. This report provides technical opinions and ideas from these experts on post-accident waste management and R and D at the Fukushima Daiichi site, as well as information on decommissioning challenges. Chapter 1 provides general descriptions and a short introduction to nuclear accidents or radiological contaminations; for instance the Chernobyl NPP accident, the Three Mile Island Unit 2 accident and the Windscale fire accident. Chapter 2 provides experiences on regulator-implementer interaction in both normal and abnormal situations, including after a nuclear accident. Chapter 3 provides experiences on stakeholder involvement after accidents. These two chapters focus on human aspects after an accident and provide recommendations on how to improve communication between stakeholders so as to resolve issues arising after unexpected nuclear accidents. Chapters 4, 5 and 6 provide information on technical issues related to waste management after accidents. Chapter 4 focuses on the physical and chemical nature of the waste, Chapter 5 on radiological characterisation, and Chapter 6 on waste classification and categorisation. The persons involved in waste management after an accident should address these issues as soon as possible after the accident. Chapters 7 and 8 also focus on technical issues but with a long-term perspective of the waste direction in the future. Chapter 7 relates

Large packages for reactor decommissioning waste

International Nuclear Information System (INIS)

Price, M.S.T.

1991-01-01

This study was carried out jointly by the Atomic Energy Establishment at Winfrith (now called the Winfrith Technology Centre), Windscale Laboratory and Ove Arup and Partners. The work involved the investigation of the design of large transport containers for intermediate level reactor decommissioning waste, ie waste which requires shielding, and is aimed at European requirements (ie for both LWR and gas cooled reactors). It proposes a design methodology for such containers covering the whole lifetime of a waste disposal package. The design methodology presented takes account of various relevant constraints. Both large self shielded and returnable shielded concepts were developed. The work was generic, rather than specific; the results obtained, and the lessons learned, remain to be applied in practice

5th International scientific-research conference Radioactive waste management. Collection of abstracts

International Nuclear Information System (INIS)

2005-01-01

Materials of the 5-th International scientific-research conference Radioactive waste management are represented. Reports illustrate such problems as experience of nuclear power plant exploitation connected with radioactive waste management, technologies and actions on decrease of radioactive waste volumes, decontamination of equipment and nuclear power plant units, management with radioactive wastes during nuclear power plant decommission [ru

Proceedings of the international topical meeting on nuclear and hazardous waste management

International Nuclear Information System (INIS)

Anon.

1988-01-01

This book contains the proceedings of the 1988 International Topical Meeting on Nuclear and Hazardous Waste Management. Included are the following articles: Defense radioactive waste management: status and challenges, Secrets of successful siting legislation for low-level radioactive waste disposal facilities, A generic hazardous waste management training program, Status of industry standards for decommissioning of nuclear facilities

Hanford Site Waste Management Plan

International Nuclear Information System (INIS)

1988-12-01

The Hanford Site Waste Management Plan (HWMP) was prepared in accordance with the outline and format described in the US Department of Energy Orders. The HWMP presents the actions, schedules, and projected costs associated with the management and disposal of Hanford defense wastes, both radioactive and hazardous. The HWMP addresses the Waste Management Program. It does not include the Environmental Restoration Program, itself divided into the Environmental Restoration Remedial Action Program and the Decontamination and Decommissioning Program. The executive summary provides the basis for the plans, schedules, and costs within the scope of the Waste Management Program at Hanford. It summarizes fiscal year (FY) 1988 including the principal issues and the degree to which planned activities were accomplished. It further provides a forecast of FY 1989 including significant milestones. Section 1 provides general information for the Hanford Site including the organization and administration associated with the Waste Management Program and a description of the Site focusing on waste management operations. Section 2 and Section 3 describe radioactive and mixed waste management operations and hazardous waste management, respectively. Each section includes descriptions of the waste management systems and facilities, the characteristics of the wastes managed, and a discussion of the future direction of operations

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

decommissioning job. We gained the decommissioning license in May 2012. We also prepared the software tool allowing managing the decommissioning project by updating the inventory and recording the progress, the characterization measurements and the material and waste production. This software allows also to trace all the material streams and to report to the Authorities. This software is a simplified release of the ones developed by SCK-CEN in the framework of other decommissioning projects like BR3 and Belgonucleaire. The dismantling of the reactor i.e. reactor pool, circuits and rabbit system, will be performed in 2013. In 2014, it is planned to map all the surfaces of the infrastructure to highlight residual contamination of floor, walls and ceiling. The contaminated surfaces will be decontaminated and controlled. The objective is to reach the free release of the reactor building and laboratories by the end of 2014. (authors)

Croatian radioactive waste management program: Current status

International Nuclear Information System (INIS)

Matanic, R.; Lebegner, J.

2001-01-01

Croatia has a responsibility to develop a radioactive waste management program partly due to co-ownership of Krsko nuclear power plant (Slovenia) and partly because of its own medical and industrial radioactive waste. The total amount of generated radioactive waste in Croatia is stored in temporary storages located at two national research institutes, while radioactive waste from Krsko remains in temporary storage on site. National power utility Hrvatska Elektroprivreda (HEP) and Hazardous Waste Management Agency (APO) coordinate the work regarding decommissioning, spent fuel management and low and intermediate level radioactive waste (LILRW) management in Croatia. Since the majority of work has been done in developing the LILRW management program, the paper focuses on this part of radioactive waste management. Issues of site selection, repository design, safety assessment and public acceptance are being discussed. A short description of the national radioactive waste management infrastructure has also been presented. (author)

The reuse of scrap and decontamination waste water from decommissioning

International Nuclear Information System (INIS)

Deng Junxian; Li Xin; Xie Xiaolong

2010-01-01

Huge amount of radioactive scrap with low activity will be generated from reactor decommissioning; the decontamination is concentrated in the surface layer of the scrap. The decontaminated substance can be removed by high pressure water jet to appear the base metal and to reuse the metal. Big amount of radioactive waste water will be generated by this decontamination technology; the radioactive of the waste water is mainly caused by the solid particle from decontamination. To remove the solid particle as clean as possible, the waste water can be reused. Different possible technology to remove the solid particle from the water had been investigated, such as the gravity deposit separation, the filtration and the centrifugal separation etc. The centrifugal separation technology is selected; it includes the hydraulic vortex, the centrifugal filtration and the centrifugal deposit. After the cost benefit analysis at last the centrifugal deposit used butterfly type separator is selected. To reuse the waste water the fresh water consumption and the cost for waste water treatment can be reduced. To reuse the radioactive scrap and the waste water from decommissioning will minimize the radioactive waste. (authors)

Aspects of nuclear waste management

International Nuclear Information System (INIS)

Moberg, L.

1990-10-01

Six areas of concern in nuclear waste management have been dealt with in a four-year Nordic research programme. They include work in two international projects, Hydrocoin dealing with modelling of groundwater flow in crystalline rock, and Biomovs, concerned with biosphere models. Geologic questions of importance to the prediction of future behaviour are examined. Waste quantities from the decommissioning of nuclear power stations are estimated, and total amounts of waste to be transported in the Nordic countries are evaluated. Waste amounts from a hypothetical reactor accident are also calculated. (au)

Radiation-protection standards and waste management

International Nuclear Information System (INIS)

Rowe, W.D.

1976-01-01

This paper reviews some of the difficult questions to be addressed in the development of fundamental environmental criteria and standards for radioactive waste management. A short discussion is included of the need to develop more precise definitions of terminology, better conceptualization of long-term problems, and new concepts to express risks from waste management and to evaluate the ability of proposed technical alternatives to control such risks. EPA's plans to develop fundamental environmental criteria and generally applicable environmental radiation-protection standards for waste disposal are summarized. Finally, the principal projects in EPA's planned near-future programs are reviewed in the areas of high-level waste, transuranic solid waste, low-level waste, residual decommissioning waste, ocean disposal, and wastes containing natural radioactivity

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

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

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

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

Automated methodology for estimating waste streams generated from decommissioning contaminated facilities

International Nuclear Information System (INIS)

Toth, J.J.; King, D.A.; Humphreys, K.K.; Haffner, D.R.

1994-01-01

As part of the DOE Programmatic Environmental Impact Statement (PEIS), a viable way to determine aggregate waste volumes, cost, and direct labor hours for decommissioning and decontaminating facilities is required. In this paper, a methodology is provided for determining waste streams, cost and direct labor hours from remediation of contaminated facilities. The method is developed utilizing U.S. facility remediation data and information from several decommissioning programs, including reactor decommissioning projects. The method provides for rapid, consistent analysis for many facility types. Three remediation scenarios are considered for facility D ampersand D: unrestricted land use, semi-restricted land use, and restricted land use. Unrestricted land use involves removing radioactive components, decontaminating the building surfaces, and demolishing the remaining structure. Semi-restricted land use involves removing transuranic contamination and immobilizing the contamination on-site. Restricted land use involves removing the transuranic contamination and leaving the building standing. In both semi-restricted and restricted land use scenarios, verification of containment with environmental monitoring is required. To use the methodology, facilities are placed in a building category depending upon the level of contamination, construction design, and function of the building. Unit volume and unit area waste generation factors are used to calculate waste volumes and estimate the amount of waste generated in each of the following classifications: low-level, transuranic, and hazardous waste. Unit factors for cost and labor hours are also applied to the result to estimate D ampersand D cost and labor hours

Progress of decommissioning of Rikkyo reactor in FY2014

International Nuclear Information System (INIS)

Suzuki, M.; Kato, M.; Tanzawa, T.; Kawaguchi, K.; Terasawa, T.; Yamada, Shigeru; Nakai, Masaru

2015-01-01

Institute for Atomic Energy, Rikkyo University, applied in 2012 for changes in the decommissioning plan toward the abolition of the reactor facilities, and received approval. It promoted the decommissioning work of the research reactors in a plan for two years from 2012, conducted the removal of the structure installed in the reactor tank and storage management measures, and implemented the function stop of the disposal facility of liquid waste and the removal of part of them. These procedures achieved the safe storage condition of core internal structure / equipment with relatively high radioactivity due to neutron irradiation. In addition, the maintenance management of partial facilities and equipment that had been maintained in operational conditions had come to be unnecessary. Based on these results, the implementation plan for decommissioning scheduled for 2015-2016 was prepared. The contents of main works are as follows: (1) dismantling and removal of disposal facilities for liquid waste and storage management of subsequently generated radioactive waste in the reactor building control area, (2) storage management of radioactive solid waste of solid waste storage facilities in the reactor building control area, (3) dismantling and removal of solid waste storage facilities that become unnecessary, and (4) release of part of the controlled area associated with the above actions. (A.O.)

Solid Waste from the Operation and Decommissioning of Power Plants

Energy Technology Data Exchange (ETDEWEB)

Brown, Marilyn Ann [Georgia Inst. of Technology, Atlanta, GA (United States); D' Arcy, Daniel [Georgia Inst. of Technology, Atlanta, GA (United States); Lapsa, Melissa Voss [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Sharma, Isha [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Li, Yufei [Georgia Inst. of Technology, Atlanta, GA (United States)

2017-01-05

This baseline report examines the solid waste generated by the U.S. electric power industry, including both waste streams resulting from electricity generation and wastes resulting from the decommissioning of power plants. Coal and nuclear plants produce large volumes of waste during electricity generation, and this report describes the policies and procedures for handling these materials. Natural gas and oil-fired power plants face similar waste challenges. Renewables considered in this baseline report include hydropower, wind and solar.

Implementation of the II. Stage decommissioning of A1 NPP

International Nuclear Information System (INIS)

Ficher, T.

2015-01-01

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

Estimation and characterization of decontamination and decommissioning solid waste expected from the Plutonium Finishing Plant

International Nuclear Information System (INIS)

Millar, J.S.; Pottmeyer, J.A.; Stratton, T.J.

1995-01-01

Purpose of the study was to estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the Hanford Plutonium Finishing Plant is decontaminated and decommissioned. (Building structure and soil are not covered.) Results indicate that ∼5,500 m 3 of solid waste is expected to result from the decontamination and decommissioning of the Pu Finishing Plant. The breakdown of the volumes and percentages of waste by category is 1% dangerous solid waste, 71% low-level waste, 21% transuranic waste, 7% transuranic mixed waste

Activities of Knowledge Management for Decommissioning of FUGEN Nuclear Power Station

International Nuclear Information System (INIS)

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

2016-01-01

Full text: The Fugen nuclear power station is a 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 last at least until 2034. In this situation, as the transfer of knowledge and education to the next generation is a crucial issue, integration and implementation of a system for knowledge management is necessary to solve it. For this purpose, a total of knowledge management system (KMS) for decommissioning was proposed. In this system, we have to arrange, organize and systematize the data and information of the plant design, maintenance history, waste management records etc. The collected data, information and records should be organized by computer support system, e.g., data base system, as well as advanced information technologies such as 3D-CAD (Computer Aided Design), VR (Virtual Reality) and AR (Augmented Reality). It will become a base of the explicit knowledge. Moreover, measures for extracting tacit knowledge from retiring employees are necessary. The experience of the retirees should be documented as much as possible through effective questionnaire or interview process. The integrated knowledge mentioned above should be used for the planning, implementation of dismantlement or education for the future generation. (author

The radioactive waste management programme in Spain

International Nuclear Information System (INIS)

Beceiro, Alvaro R.; Vico, Elena

2002-01-01

In 1984 the Empresa Nacional de Residuos Radiactivos (ENRESA) was set up in order to be responsible for all radioactive waste management activities in the country. ENRESA is a state-owned company, the shareholders of which are CIEMAT (Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, formerly (JEN) and SEPI (Sociedad Estatal de Participaciones Industriales), both institutions dependent on the Spanish Government. ENRESA has a broad scope of responsibilities, including not only the management of L/ILW, HLW and spent fuel but also the decommissioning of nuclear installations, as well as the rehabilitation of uranium mining and milling facilities when required. The policy on radioactive waste management is defined by the Government, and the strategies are developed by ENRESA in accordance with the General Radioactive Waste Management Plan. This Plan is a strategic document which must be submitted yearly by ENRESA to the Government, for its approval when the Ministry of Economy decided so. The plan, in general terms, contains the main aspects related to waste generation and forecasts, as well as the strategies and technical solutions to be prepared, along with the associated economic and financial aspects. ENRESA's activities are financed by the waste producers. On the one hand the nucleoelectric sector pays a percentage fee on all the electricity sales, while small producers pay tariffs according to the services provided, both are approved by the Government. The Fifth General Radioactive Waste Plan, approved by the Government in July 1999, is currently in force and contains the strategies for the management of radioactive wastes and decommissioning of nuclear installations in Spain. (author)

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)

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)

Waste management research abstracts no. 16. Information on radioactive waste programmes in progress

Energy Technology Data Exchange (ETDEWEB)

NONE

1985-11-01

The research abstracts contained in this issue have been collected during recent months ending August 1985. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. The abstracts have been printed in the language and in the form of submittal and without any changes other than minor editorial ones.

Waste management research abstracts no. 16. Information on radioactive waste programmes in progress

International Nuclear Information System (INIS)

1985-11-01

The research abstracts contained in this issue have been collected during recent months ending August 1985. The abstracts reflect research currently in progress in the field of radioactive waste management: environmental impacts, site selection, decontamination and decommissioning, environmental restoration and legal aspects of radioactive waste management. The abstracts have been printed in the language and in the form of submittal and without any changes other than minor editorial ones

Safety Assessment for Decommissioning

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-06-15

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

Regulatory experience in nuclear power station decommissioning

International Nuclear Information System (INIS)

Ross, W.M.; Waters, R.E.; Taylor, F.E.; Burrows, P.I.

1995-01-01

In the UK, decommissioning on a licensed nuclear site is regulated and controlled by HM Nuclear Installations Inspectorate on behalf of the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to decommissioning activities and provides a continuous but flexible safety regime until there is no danger from ionising radiations. The regulatory strategy is discussed, taking into account Government policy and international guidance for decommissioning and the implications of the recent white paper reviewing radioactive waste management policy. Although each site is treated on a case by case basis as regulatory experience is gained from decommissioning commercial nuclear power stations in the UK, generic issues have been identified and current regulatory thinking on them is indicated. Overall it is concluded that decommissioning is an evolving process where dismantling and waste disposal should be carried out as soon as reasonably practicable. Waste stored on site should, where it is practical and cost effective, be in a state of passive safety. (Author)

Basis for criteria for exemption of decommissioning waste

International Nuclear Information System (INIS)

Elert, M.; Wiborgh, M.; Bengtsson, A.

1992-02-01

The purpose of this study was to provide the Swedish Radiation Protection Institute (SSI) with technical background material to be used as a basis for future decisions concerning exemption levels for decommissioning waste. Simple models have been developed for evaluating the individual doses that may arise from steel waste, concrete waste and non-burnable waste exempted from regulatory control. Two alternatives were studied for the exempted wastes: recycling and disposal in different types of near-surface repositories. The example calculations for the recycling scenarios show that the individual dose obtained is strongly dependent on the exposure time. Thus, the storage of the waste at a scrap yard will give rise to a higher dose than the melting, due to the longer storage time. (28 refs.)

The Preliminary Decommissioning Plan of the Dalat Nuclear Research Reactor

Energy Technology Data Exchange (ETDEWEB)

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

2013-08-15

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

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 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.

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)

A Decommissioning Information Management System

Energy Technology Data Exchange (ETDEWEB)

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

2007-07-01

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

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)

Methodology for evaluating radiological consequences of the management of very low-level solide waste arising from decommissioning of nuclear power plants

International Nuclear Information System (INIS)

Smith, G.M.; Hemming, C.R.; Clark, J.M.; Chapuis, A.M.; Garbay, H.

1985-01-01

In this report a methodology is described, and illustrated by examples, for the evaluation of individual doses and collective dose commitments arising as a result of various management modes for very low-level solid wastes arising from the decommissioning of nuclear power plants. Estimates have been made of the masses of materials activated and contaminated to within three concentration limits, 0.37, 3.7 and 37 Bq g-1, at three times after reactor shutdown, 5 y, 25 y and 100 y. The disposal options considered are shallow land burial, at a municipal landfill site or at the reactor site, and disposal on the seabed in coastal waters or the deep ocean. It is assumed that there is no special treatment to reduce or eliminate the potential radiological hazard. Consideration has also been given to the radiological impact of recycling of contaminated steel. The radiological impacts of all the management options for the wastes considered were found to be small. It may therefore be acceptable to allow such very low-level wastes to be disposal of without special restrictions provided that the level and type of activity of the wastes can be verified. In addition the health detriment cost associated with all the management options is small, so it is likely that other factors such as transport and engineering costs will be more important in final decisions about the management of these wastes

Windscale advanced gas-cooled reactor (WAGR) decommissioning project overview

International Nuclear Information System (INIS)

Pattinson, A.

2003-01-01

The current BNFL reactor decommissioning projects are presented. The projects concern power reactor sites at Berkely, Trawsfynydd, Hunterstone, Bradwell, Hinkley Point; UKAEA Windscale Pile 1; Research reactors within UK Scottish Universities at East Kilbride and ICI (both complete); WAGR. The BNFL environmental role include contract management; effective dismantling strategy development; implementation and operation; sentencing, encapsulation and transportation of waste. In addition for the own sites it includes strategy development; baseline decommissioning planning; site management and regulator interface. The project objectives for the Windscale Advanced Gas-Cooled Reactor (WAGR) are 1) Safe and efficient decommissioning; 2) Building of good relationships with customer; 3) Completion of reactor decommissioning in 2005. The completed WAGR decommissioning campaigns are: Operational Waste; Hot Box; Loop Tubes; Neutron Shield; Graphite Core and Restrain System; Thermal Shield. The current campaign is Lower Structures and the remaining are: Pressure vessel and Insulation; Thermal Columns and Outer Vault Membrane. An overview of each campaign is presented

Overview assessment of nuclear-waste management

International Nuclear Information System (INIS)

Burton, B.W.; Gutschick, V.P.; Perkins, B.A.

1982-08-01

After reviewing the environmental control technologies associated with Department of Energy nuclear waste management programs, we have identified the most urgent problems requiring further action or follow-up. They are in order of decreasing importance: (1) shallow land disposal technology development; (2) active uranium mill tailings piles; (3) uranium mine dewatering; (4) site decommissioning; (5) exhumation/treatment of transuranic waste at Idaho National Engineering Laboratory; (6) uranium mine spoils; and (7) medical/institutional wastes. 7 figures, 33 tables

System approach for the management of radioactive waste

International Nuclear Information System (INIS)

Fearnley, I.G.

1997-01-01

An integrated approach to Waste Management and Decommissioning, which takes account of the lifetime implications (safety, dose uptake, discharges and cost) is an important strategic process in forward planning. This type of approach is particularly relevant when making decisions concerning waste minimisation and segregation, packaging and surface storage of high and intermediate level waste in advance of the existence of disposal facilities. Such a systematic approach forms an integral part of a process which enable progress to be assessed and plans to be updated in response to changing demands upon business operations and can continually be applied to waste management policy and to optimise the detailed waste management plans. (author)

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.)

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.

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.

Safety analysis of disposal of decommissioning waste from the Olkiluoto nuclear power plant - PURKU-93

International Nuclear Information System (INIS)

Vieno, T.; Meszaros, F.; Nordman, H.; Taivassalo, V.

1993-12-01

Decommissioning waste from the Olkiluoto nuclear power plant will be disposed of at the depth between 60 and 100 meters in the bedrock at the power plant site. The existing VLJ repository for low and medium level operating waste will be extended with three new silos for the decommissioning waste of the TVO I and II reactors and the spent fuel interim store at the Olkiluoto site. Besides dismantling waste also used fuel boxes, control rods and other activated metal components accumulated during the operation of the reactors will be disposed of in the repository. The safety analysis is based on the detailed decommissioning plan of the Olkiluoto power plants and the comprehensive safety analysis carried out for the Final Safety Analysis Report of the VLJ repository. (58 refs., 31 figs., 38 tabs.)

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.)

Waste management (Truck and rail shipments to Hanford)

International Nuclear Information System (INIS)

O'Donnell, J.P.; Culbertson, R.C.

1988-01-01

As part of the physical decommissioning of the Shippingport Atomic Power Station, Shippingport, PA, a large volume of Low Specific Activity (LSA) radioactive waste was accumulated. The waste, which consisted primarily of radioactive reactor plant components, piping, contaminated asbestos, tanks, building rubble, sludge and ion exchange resins was packaged and prepared for shipment. The waste was transported by truck and rail from Shippingport, PA, to the Department of Energy burial ground at Hanford, Washington, a journey of 2,329 miles. This presentation will discuss the successful management of over 2,600 packages weighing in excess of 3,600 tons of radioactive waste from the cradle-to-the-grave, that is from the time it was generated during the decommissioning process until its final burial at the Hanford, Washington burial site. 1 tab

Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

International Nuclear Information System (INIS)

Saleh, Lydia Ilaiza; Ryong, Kim Tae

2015-01-01

The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation

Study on the financing mechanism and management for decommissioning of nuclear installations in Malaysia

Energy Technology Data Exchange (ETDEWEB)

Saleh, Lydia Ilaiza, E-mail: lydiailaiza@gmail.com; Ryong, Kim Tae [KEPCO International Nuclear Graduate School (KINGS) 658-91 Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan 689-882 (Korea, Republic of)

2015-04-29

The whole cycle of the decommissioning process development of repository requires the relevant bodies to have a financial system to ensure that it has sufficient funds for its whole life cycle (over periods of many decades). Therefore, the financing mechanism and management system shall respect the following status: the national position, institutional and legislative environment, technical capabilities, the waste origin, ownership, characteristics and inventories. The main objective of the studies is to focus on the cost considerations, alternative funding managements and mechanisms, technical and non-technical factors that may affect the repository life-cycle costs. As a conclusion, the outcomes of this paper is to make a good recommendation and could be applied to the national planners, regulatory body, engineers, or the managers, to form a financial management plan for the decommissioning of the Nuclear Installation.

Biological considerations in nuclear decommissioning, and radioactive waste management

International Nuclear Information System (INIS)

Rees, J.F.

1991-01-01

The importance of natural processes such as microbial action in waste management has recently been recognised. Although it is often difficult to predict the effects because the interactive processes are complex, human intervention can optimize the process. This paper highlights some of the fundamental stages in the management of low- and intermediate-level radioactive wastes where particular uncertainties exist and which might benefit from controlled microbial intervention. The areas considered are the use of biodegradable surfactants for cleaning surfaces before disposal, microbial adsorption and concentration of intermediate-level wastes from solution, microbial transformation of intermediate-level wastes organic fractions, enhancement of radionuclide transfer to the atmosphere, enhancement of transfer into vadose zone and ground water and the microbial treatment of any oily residues. (UK)

The Radioactive Waste Management Programme in Spain

International Nuclear Information System (INIS)

Beceiro, A. R.; Vico, E.

2000-01-01

In 1984 the Empresa Nacional de Residuos Radiactivos (ENRESA) was set up in order to be responsible for all radioactive waste management activities in the country. ENRESA is a state-owned company, the shareholders of which are CIEMAT (Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, formerly (JEN) and SEPI (Sociedad Estatal de Participaciones Industriales), both institutions dependent on the Ministry of Industry and Energy. ENRESA has a broad scope of responsibilities, including not only the management of L/ILW, HLW and spent fuel but also the decommissioning of nuclear installations, as well as the rehabilitation of uranium mining and milling facilities when required. The policy on radioactive waste management is defined by the Government, and the strategies are developed by ENRESA in accordance with the General Radioactive Waste Management Plan. This Plan is a strategic document which must be submitted yearly by ENRESA to the Government, for its approval when the Ministry of Industry and Energy decided so. The plan, in general terms, contains the main aspects related to waste generation and forecasts, as well as the strategies and technical solutions to be prepared, along with the associated economic and financial aspects. ENRESA's activities are financed by the waste producers. On the one hand the nucleoelectric sector pays a percentage fee on all the electricity sales, while small producers pay tariffs according to the services provided, both are approved by the Government. The fifth General Radioactive Waste Plan, approved by the Government in July 1999, is currently in force and contains the strategies for the management of radioactive wastes and decommissioning of nuclear installations in Spain. (author)

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

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

Brazilian nuclear power plants decommissioning plan for a multiple reactor site

Energy Technology Data Exchange (ETDEWEB)

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

2015-07-01

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

Brazilian nuclear power plants decommissioning plan for a multiple reactor site

International Nuclear Information System (INIS)

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

2015-01-01

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

Preparation of the National Radioactive Waste and Spent Fuel Management Programme in Slovenia

International Nuclear Information System (INIS)

Kralj, M.; Zeleznik, N.; Mele, I.; Veselic, M.

2006-01-01

The first separate National Radioactive Waste and Spent Fuel Management Programme (National Programme) was prepared in Slovenia in 2005, as a separate part of the National Environmental Action Programme that was adopted in June 2005. In the previous National Environmental Action Programme from the year 1999, the radioactive waste and spent fuel management was mentioned only briefly in the paragraph on radiation and nuclear safety with two main objectives: to provide an effective management of radioactive waste, and to keep the environmental ionising radiation under control. The new National Programme from 2005 includes all topics being relevant for the management of the radioactive waste and spent fuel, from the legislation and identification of different waste streams in Slovenia, to the management of radioactive waste and spent fuel, the decommissioning of nuclear facilities and management of (TE)NORM. It deals also with the relevant actors in the radioactive waste management, communication and information activities, and the financial aspects of the radioactive waste and spent fuel management. The National Programme was already adopted by the Slovenian Government in October 2005 and will go to Parliament proceedings. The Technical bases for the National Programme was prepared by ARAO and presented to the government in the beginning of 2005. The frames for this document were taken from relevant strategic documents: the Programme of decommissioning the nuclear power plant Krsko and the radioactive waste and spent fuel management, prepared in 2004 by Slovenian and Croatian experts (ARAO and APO), the Proposal of LILW Management Strategy (1999), the Strategy of Spent Fuel Management (1996), and the Resolution on the National Energy Programme (2004). ARAO made a detailed study on the amount and types of radioactive waste produced in Slovenia and future arising with emphasis on the minimization on radioactive waste production. It considered all producers of LILW and

Decommissioning of four small nuclear waste storage buildings and an evaporation plant

International Nuclear Information System (INIS)

Hedvall, R.H.; Ellmark, C.; Stocker, P.

2008-01-01

A small-scale decommissioning concept was applied with staff from an earlier project wish strong knowledge of radiation protection, minimized radiation doses and environmental pollution. The project was therefore initiated with less than 10 people involved using standard hand held equipment. The aim of the decommissioning project was to set free as much material as possible, i.e. remove waste from the regulatory control regime and also free the remaining structures and buildings for conventional demolition and subsequent reuse of the property. Complete decommissioning will be concluded at the end of 2008 when all waste is taken case of. This is the fourth in a series of important decommissioning projects in Studsvik since the 1980s. Some of the conclusions are: 1) Obtain a group with well-known personnel that have been working together before for the entire project For a project larger than this, project management assistant would have made follow-up more efficient. Experts in instrumentation and statistics are also important. Also important is knowledge about practical decisions that would make the project more efficient in terms of time. Interviews and historical facts are important when choosing which nuclides are of most interest for measurements (but be critic). 2) Be sure all authoritative requirements are followed, like setting up a work environment plan at the entrance to the site and placing a fence around the work site. 3) Check all individual radiation exposures before project start and do whole body measurements both before and after the project. Urine samples should be taken if alpha contamination is a risk. 4) Calculate for unwanted and 'not what you expected' situations in the time schedule. 5) Be aware of contaminations and radiation sources outside the actual area. They might have to be moved. 6) Calculate and order bins and containers for waste storage well in advance. Stay informed of the updated amount of waste and keep it in locked storage. 7

The Research Results of Radioactive Waste Management Technology Center Year 1997/1998

International Nuclear Information System (INIS)

1998-12-01

The research results of Radioactive Waste Management Technology Center, National Atomic Energy Agency of Indonesia year 1997/1998 contain paper as form of research results on radioactive waste management related fields. There were included many aspects such as radioactive waste processing, storage, decontamination, decommissioning, safety and environmental aspects. There are 26 papers indexed individually (ID)

KONTEC 2009. Report about the 9th International Symposium on ''Conditioning of radioactive operational and decommissioning wastes''

International Nuclear Information System (INIS)

Anon.

2009-01-01

''Kontec 2009'' was organized in Dresden on April 15-17, 2009. For the 8 th time, this established international meeting covered the subjects of ''Conditioning of Radioactive Operational and Decommissioning Wastes'' and ''Decommissioning and Dismantling of Nuclear Facilities'' and the R and D Status Report delivered by the German Federal Ministry for Education and Research on this key topic. Some 790 participants from 13 countries heard and discussed the contributions to the three-day meeting. The program of the symposium comprised plenary sessions dealing with these 4 key subjects: Disposal of Radioactive Residues from Nuclear Facilities' Operation and Decommissioning, Decommissioning and Dismantling of Nuclear Facilities, Facilities and Systems for the Conditioning of Operational and Decommissioning Wastes, Transport, Interim and Final Storage of Non-heat Generating Wastes (i.e. Konrad). The sessions were supplemented by poster sessions and selected short presentations under the heading of ''Kontec Direct.'' (orig.)

UK-Nuclear decommissioning authority and US Salt-stone waste management issues

International Nuclear Information System (INIS)

Lawless, William; Whitton, John

2007-01-01

Available in abstract form only. Full text of publication follows: We update two case studies of stakeholder issues in the UK and US. Earlier versions were reported at Waste Management 2006 and 2007 and at ICEM 2005. UK: The UK nuclear industry has begun to consult stakeholders more widely in recent years. Historically, methods of engagement within the industry have varied, however, recent discussions have generally been carried out with the explicit understanding that engagement with stakeholders will be 'dialogue based' and will 'inform' the final decision made by the decision maker. Engagement is currently being carried out at several levels within the industry; at the national level (via the Nuclear Decommissioning Authority's (NDA) National Stakeholder Group (NSG)); at a local site level (via Site Stakeholder Groups) and at a project level (usually via the Best Practicable Environmental Option process (BPEO)). This paper updates earlier results by the co-author with findings from a second questionnaire issued to the NSG in Phase 2 of the engagement process. An assessment is made regarding the development of stakeholder perceptions since Phase 1 towards the NDA process. US: The US case study reviews the resolution of issues on salt-stone by Department of Energy's (DOE) Savannah River Site (SRS) Citizens Advisory Board (CAB), in Aiken, SC. Recently, SRS-CAB encouraged DOE and South Carolina's regulatory Department of Health and Environmental Control (SC-DHEC) to resolve a conflict preventing SC-DHEC from releasing a draft permit to allow SRS to restart salt-stone operations. It arose with a letter sent from DOE blaming the Governor of South Carolina for delay in restarting salt processing. In reply, the Governor blamed DOE for failing to assure that Salt Waste Processing Facility (SWPF) would be built. SWPF is designed to remove most of the radioactivity from HLW prior to vitrification, the remaining fraction destined for salt-stone. (authors)

Environmental aspects of commercial radioactive waste management

Energy Technology Data Exchange (ETDEWEB)

1979-05-01

Environmental effects (including accidents) associated with facility construction, operation, decommissioning, and transportation in the management of commercially generated radioactive waste were analyzed for plants and systems assuming a light water power reactor scenario that produces about 10,000 GWe-yr through the year 2050. The following alternative fuel cycle modes or cases that generate post-fission wastes requiring management were analyzed: a once-through option, a fuel reprocessing option for uranium and plutonium recycle, and a fuel reprocessing option for uranium-only recycle. Volume 1 comprises five chapters: introduction; summary of findings; approach to assessment of environmental effects from radioactive waste management; environmental effects related to radioactive management in a once-through fuel cycle; and environmental effects of radioactive waste management associated with an LWR fuel reprocessing plant. (LK)

Environmental aspects of commercial radioactive waste management

International Nuclear Information System (INIS)

1979-05-01

Environmental effects (including accidents) associated with facility construction, operation, decommissioning, and transportation in the management of commercially generated radioactive waste were analyzed for plants and systems assuming a light water power reactor scenario that produces about 10,000 GWe-yr through the year 2050. The following alternative fuel cycle modes or cases that generate post-fission wastes requiring management were analyzed: a once-through option, a fuel reprocessing option for uranium and plutonium recycle, and a fuel reprocessing option for uranium-only recycle. Volume 1 comprises five chapters: introduction; summary of findings; approach to assessment of environmental effects from radioactive waste management; environmental effects related to radioactive management in a once-through fuel cycle; and environmental effects of radioactive waste management associated with an LWR fuel reprocessing plant

Developments in the management of radioactive waste from the mining and milling of radioactive ores

International Nuclear Information System (INIS)

Crawley, H.

1990-01-01

The philosophy of a waste management system is discussed. The origins of the various wastes from the mining and milling processes are outlined and the development of a waste management program described. The technical aspects of a waste management plan, namely water management systems, waste rock and ore stockpile management, tailings impoundment and decommissioning and rehabilitation are discussed in detail. 12 refs., 4 tabs, 15 figs

Law on the management of radioactive waste

International Nuclear Information System (INIS)

1999-01-01

This law regulate the relations of legal persons, enterprises without the rights of legal persons, and natural persons in the management of radioactive waste in Lithuania and establish the legal grounds for the management of radioactive waste. Thirty one article of the law deals with the following subjects: principles of radioactive waste management, competence of the Government, State Nuclear Power Safety Inspectorate, Ministry of Economy, Ministry of Environment and Radiation Protection Center in the sphere of regulation of the radioactive waste management, activities subject to licensing, issue of licences and authorisations, duties and responsibilities of the waste producer, founding of the radioactive waste management agency, its basic status and principles of the activities, functions of the agency, management of the agency, transfer of the radioactive waste to the agency, assessment of the existing waste management facilities and their past practices, siting, design and construction, safety assessment, commissioning and operation of the radioactive waste management facilities, radiation protection, quality assurance, emergency preparedness, decommissioning of radioactive waste storage and other facilities, post-closure surveillance of the repository, disused sealed sources, transportation, export and transit of radioactive waste

Research and development work on radioactive waste management and storage of chemical-toxic wastes - first half of 1992

International Nuclear Information System (INIS)

1992-10-01

This progress report covers the state and results of the projects undertaken in the area of waste management. In particular, results in the area of decommissioning and retreat of nuclear installations are documented. Furthermore, measures designed to increase environmental compatibility are taken into account. Experimental results regarding the concept, planning, construction, operation, decommissioning and post-operational phase of a repository or underground disposal of hazardous wastes are also described. Lists of formalized interim reports and research institutions involved are attached. (DG) [de

International co-operation for safe radioactive waste management

International Nuclear Information System (INIS)

1983-01-01

As a specialised inter-governmental body, NEA pursues three main objectives for its radioactive waste management programme: - The promotion of studies to improve the data base available in support of national programmes. - The support of Research and Development through co-ordination of national activities and promotion of international projects. - An improvement in the general level of understanding of waste management issues and options, particularly in the field of waste disposal. The management of radioactive waste from nuclear activities covers several sequences of complex technical operations. However, as the ultimate objective of radioactive waste management is the disposal of the waste, the largest part of the work programme is directed towards the analysis of disposal options. In addition, NEA is active in various other areas of waste management, such as the treatment and conditioning of waste, the decommissioning of nuclear facilities and the institutional aspects of the long term management of radioactive waste

The Research Results of Radioactive Waste Management Technology Center Year 1996/1997

International Nuclear Information System (INIS)

Budiman, P.; Martono, H.; Las, T.; Lubis, E.; Mulyanto; Wisnubroto, D. S.; Sucipta

1997-12-01

The research results of Radioactive Waste Management Technology Center, National Atomic Energy Agency of Indonesia year 1996/1997 contain paper as form of research results on radioactive waste management related fields. There were included many aspects such as radioactive waste processing, storage, decontamination, decommissioning, safety and environmental aspects. There are 24 papers and 12 short communications indexed individually(ID)

Technology for commercial radioactive waste management

International Nuclear Information System (INIS)

1979-05-01

An analysis of the complete waste management system was developed to assess the total impact of managing radioactive wastes generated over the entire lifetime of a nuclear power system. The analysis considers the treatment and disposal of all post-fission TRU, gaseous and airborne and decommissioning wastes. Each radioactive waste stream is tracked each year from its origin through treatment, storage, transport, and accumulation in a geologic repository. The reference system is based on 400 GWe of nuclear power installed in the year 2000 and produces approximately 10,000 GWe-years of electric energy. An alternative low-growth projection based on 255 GWe in the year 2000 is also considered, but for fewer cases. This system produces approximately 6400 GWe year of electric energy. Capacity additions beyond the year 2000 are not considered a part of this system. After 40 years of operation each nuclear power plant is shut down and decommissioned. Thus, the last nuclear power plant is shut down in the year 2040. The last fuel reprocessing plant is shut down in the year 2044 and dismantled in the year 2075. Thus, the system operation encompasses a 101-year period from 1975 through 2075. In addition, the decay of radioactivity in the final repositories is followed over a million year period

Life cycle cost estimation and systems analysis of Waste Management Facilities

International Nuclear Information System (INIS)

Shropshire, D.; Feizollahi, F.

1995-01-01

This paper presents general conclusions from application of a system cost analysis method developed by the United States Department of Energy (DOE), Waste Management Division (WM), Waste Management Facilities Costs Information (WMFCI) program. The WMFCI method has been used to assess the DOE complex-wide management of radioactive, hazardous, and mixed wastes. The Idaho Engineering Laboratory, along with its subcontractor Morrison Knudsen Corporation, has been responsible for developing and applying the WMFCI cost analysis method. The cost analyses are based on system planning level life-cycle costs. The costs for life-cycle waste management activities estimated by WMFCI range from bench-scale testing and developmental work needed to design and construct a facility, facility permitting and startup, operation and maintenance, to the final decontamination, decommissioning, and closure of the facility. For DOE complex-wide assessments, cost estimates have been developed at the treatment, storage, and disposal module level and rolled up for each DOE installation. Discussions include conclusions reached by studies covering complex-wide consolidation of treatment, storage, and disposal facilities, system cost modeling, system costs sensitivity, system cost optimization, and the integration of WM waste with the environmental restoration and decontamination and decommissioning secondary wastes

Waste management aspects of decontamination and decommissioning (D ampersand D) projects

International Nuclear Information System (INIS)

Becker, B.D.

1993-01-01

History shows that waste management concepts have generally been overlooked during the planning stages of most projects and experiments. This is resulting,in the generation of vast amounts of waste during the clean up or D ampersand D of these facilities. Managers are not only being frustrated in their waste minimization efforts (a relatively new concept) but are also facing the prospect of not being able to dispose of the waste materials at all. At the least, managers are having to budget extraordinary amounts of time, money, and effort in defending their positions that the waste materials are not only humanly and environmentally safe, but that the waste materials are in fact what management says they are. The following discussion will attempt to provide some guidance to D ampersand D managers to help them avoid many of the common pitfalls associated with the ultimate disposal of the materials generated during these projects

Management of Radioactive Wastes

International Nuclear Information System (INIS)

Tchokosa, P.

2010-01-01

Management of Radioactive Wastes is to protect workers and the public from the radiological risk associated with radioactive waste for the present and future. It application of the principles to the management of waste generated in a radioisotope uses in the industry. Any material that contains or is contaminated with radionuclides at concentrations or radioactivity levels greater than ‘exempt quantities’ established by the competent regulatory authorities and for which no further use is foreseen or intended. Origin of the Radioactive Waste includes Uranium and Thorium mining and milling, nuclear fuel cycle operations, Operation of Nuclear power station, Decontamination and decommissioning of nuclear facilities and Institutional uses of isotopes. There are types of radioactive waste: Low-level Waste (LLW) and High-level Waste. The Management Options for Radioactive Waste Depends on Form, Activity, Concentration and half-lives of the radioactive waste, Storage and disposal methods will vary according to the following; the radionuclides present, and their concentration, and radio toxicity. The contamination results basically from: Contact between radioactive materials and any surface especially during handling. And it may occur in the solid, liquid or gas state. Decontamination is any process that will either reduce or completely remove the amount of radionuclides from a contaminated surface

Final disposal of decommissioning wastes in the Federal Republic of Germany

Energy Technology Data Exchange (ETDEWEB)

Brewitz, W; Stippler, R

1981-01-01

The waste disposal concept of the Federal Republic of Germany for nuclear power plants provides for the final disposal of radioactive waste in deep geological formations and mines. The radiological safety of such a repository depends on a system of multiple barriers of which the geological barrier is the most important one. The isolation concept must guarantee the waste to decay below the limiting values of the German Radiation Protection Regulation within the repository. The expected total decommissioning waste masses from 12 nuclear power plants operating in the Federal Republic of Germany amounts to approxiametly 85000 Mg. For the final disposal of these wastes there are, under present aspects, two mines being considered as repositories. The pilot repository in the Asse II salt mine is in the state of licensing. The adandoned iron ore mine Konrad is being investigated for its feasibility and licensing will probably be initiated in 1982. Capacity and efficiency calculations have proved that both mines have got the technical requirements needed for the disposal of decommissioning and operating wastes from existent as well as from future built nuclear power plants.

Decommissioning of reactor facilities (2). Required technology

International Nuclear Information System (INIS)

Yanagihara, Satoshi

2014-01-01

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

A system approach for the management of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Fearnley, I.G. [British Nuclear Fuels plc, Warrington, Cheshire (United Kingdom)

1995-12-31

An integrated approach to Waste Management and Decommissioning, which takes account of the lifetime implications (safety, dose uptake, discharges and cost) is an important strategic process in forward planning. This type of approach is particularly relevant when making decisions concerning waste minimization and segregation, packaging and surface storage of high and intermediate level waste in advance of the existence of disposal facilities. Such a systematic approach forms an integral part of a process which enables progress to be assessed and plans to be updated in response to changing demands upon business operations and can continually be applied to waste management policy and to optimise the detailed waste management plans. (author)

A system approach for the management of radioactive waste

International Nuclear Information System (INIS)

Fearnley, I.G.

1995-01-01

An integrated approach to Waste Management and Decommissioning, which takes account of the lifetime implications (safety, dose uptake, discharges and cost) is an important strategic process in forward planning. This type of approach is particularly relevant when making decisions concerning waste minimization and segregation, packaging and surface storage of high and intermediate level waste in advance of the existence of disposal facilities. Such a systematic approach forms an integral part of a process which enables progress to be assessed and plans to be updated in response to changing demands upon business operations and can continually be applied to waste management policy and to optimise the detailed waste management plans. (author)

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

International Nuclear Information System (INIS)

Dishkova, Denitsa

2014-01-01

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

Radioactive wastes management

International Nuclear Information System (INIS)

Albert, Ph.

1999-01-01

This article presents the French way to deal with nuclear wastes. 4 categories of radioactive wastes have been defined: 1) very low-level wastes (TFA), 2) low or medium-wastes with short or medium half-life (A), 3) low or medium-level wastes with long half-life (B), and 4) high-level wastes with long half-life (C). ANDRA (national agency for the management of radioactive wastes) manages 2 sites of definitive surface storage (La-Manche and Aube centers) for TFA-wastes. The Aube center allows the storage of A-wastes whose half-life is less than 30 years. This site will receive waste packages for 50 years and will require a regular monitoring for 300 years after its decommissioning. No definitive solutions have been taken for B and C wastes, they are temporarily stored at La Hague processing plant. Concerning these wastes the French parliament will have to take a decision by 2006. At this date and within the framework of the Bataille law (1991), scientific studies concerning the definitive or retrievable storage, the processing techniques (like transmutation) will have been achieved and solutions will be proposed. These studies are numerous, long and complex, they involve fresh knowledge in geology, chemistry, physics,.. and they have implied the setting of underground facilities in order to test and validate solutions in situ. This article presents also the transmutation technique. (A.C.)

Waste management facilities cost information: System cost model product description. Revision 2

International Nuclear Information System (INIS)

Lundeen, A.S.; Hsu, K.M.; Shropshire, D.E.

1996-02-01

In May of 1994, Lockheed Idaho Technologies Company (LITCO) in Idaho Falls, Idaho and subcontractors developed the System Cost Model (SCM) application. The SCM estimates life-cycle costs of the entire US Department of Energy (DOE) complex for designing; constructing; operating; and decommissioning treatment, storage, and disposal (TSD) facilities for mixed low-level, low-level, transuranic, and mixed transuranic waste. The SCM uses parametric cost functions to estimate life-cycle costs for various treatment, storage, and disposal modules which reflect planned and existing facilities at DOE installations. In addition, SCM can model new facilities based on capacity needs over the program life cycle. The SCM also provides transportation costs for DOE wastes. Transportation costs are provided for truck and rail and include transport of contact-handled, remote-handled, and alpha (transuranic) wastes. The user can provide input data (default data is included in the SCM) including the volume and nature of waste to be managed, the time period over which the waste is to be managed, and the configuration of the waste management complex (i.e., where each installation's generated waste will be treated, stored, and disposed). Then the SCM uses parametric cost equations to estimate the costs of pre-operations (designing), construction costs, operation management, and decommissioning these waste management facilities

Decommissioning and back working of Greifswald nuclear power plant

International Nuclear Information System (INIS)

Rittscher, D.; Leushacke, D.F.; Meyer, R.

1998-01-01

At Nuclear Power Plant Greifswald, the Energiewerke Nord are carrying out the presently world's largest decommissioning project. This requires the gathering up of experience from the operation of the nuclear power plants at Greifswald, the decommissioning of other nuclear power plants, waste management, project management and licensing procedures for the decommissioning of nuclear power plants. That confirmed that the back working of nuclear plants is not a technical problem but a challenge for project management and logistics. It shows that the dismantling and disposal of nuclear plants is an ordinary process in our economic life. (orig.) [de

Status of the Japan's regulatory policy on radioactive waste management. Cleanup and recycling issues

International Nuclear Information System (INIS)

Takeuchi, Daiji

1995-01-01

Wastes from nuclear facilities are very diversified concerning that have different levels of radioactivity and include different kinds of radioactive materials. Besides some of those waste is not assumed as radioactive waste. The basic policy of the radioactive waste management is taking that diversity into full account for appropriate separate management of different types of radioactive waste and treatment and disposal of each type in a rational manner, including recycling. From the point, the disposal methods are considered or under consideration to that waste, (1) from nuclear reactor facility, (2) from nuclear fuel cycle facility--HLW, waste contaminated TRU nuclides, or contaminated uranium, (3) from RI utilization or research institute, and (4) from decommissioning of nuclear facility. Now in Japan, regulation framework for some kind of LLW from reactor facility, including waste from decommissioning of reactor is established. (J.P.N.)

Technology, safety and costs of decommissioning a reference pressurized water reactor power station. Classification of decommissioning wastes. Addendum 3

International Nuclear Information System (INIS)

Murphy, E.S.

1984-09-01

The radioactive wastes expected to result from decommissioning of the reference pressurized water reactor power station are reviewed and classified in accordance with 10 CFR 61. The 17,885 cubic meters of waste from DECON are classified as follows: Class A, 98.0%; Class B, 1.2%; Class C, 0.1%. About 0.7% (133 cubic meters) of the waste would be generally unacceptable for disposal using near-surface disposal methods

Decommissioning of a tritium-contaminated laboratory

International Nuclear Information System (INIS)

Harper, J.R.; Garde, R.

1982-01-01

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

The radioactive waste management policy and practice in the Czech Republic

International Nuclear Information System (INIS)

Kucerka, M.

1996-01-01

In recent period, the new Czech Atomic Law is in the final stage of preparation, and the author expects that Parliament of the Czech Republic will approve it in the first half of the year 1996. Partly the law deals with new distribution of responsibilities among bodies involved in utilization of nuclear energy and ionizing radiation, the state and local authorities. The new provisions include also radioactive waste management activities. These provisions clarify the relations between radioactive waste generators and state, and define explicitly duties of waste generators. One of the most important duties is to cover all expenses for radioactive waste management now and in the future, including radioactive waste disposal and decommissioning of nuclear facilities. The law establishes radioactive waste management and decommissioning funds and the new, on waste generators independent radioactive waste management organization, controlled by state, to ensure the safety of inhabitants and the environment, and a optimization of expenses. Parallel to the preparation of the law, the Ministry of Industry and Trade prepares drafts of a statute of the radioactive waste management organization and its control board, and of the methodology and rules of management the radioactive waste fund. First drafts of these documents are expected to be complete in January 1996. The paper will describe recent practice and policy of the radioactive waste management including uranium mining and milling tailings, amounts of waste and its activities, economical background, and safety. A special attention will be paid to description of expected changes in connection with the new Atomic Law and expected steps and time schedule of reorganization of the radioactive waste management structure in the Czech Republic

What will we do with the low level waste from reactor decommissioning?

International Nuclear Information System (INIS)

Meehan, A. R.; Wilmott, S.; Crockett, G.; Watt, N. R.

2008-01-01

The decommissioning of the UK's Magnox reactor sites will produce large volumes of low level waste (LLW) arisings. The vast majority of this waste takes the form of concrete, building rubble and redundant plant containing relatively low levels of radioactivity. Magnox Electric Ltd (Magnox) is leading a strategic initiative funded by the Nuclear Decommissioning Authority (NDA) to explore opportunities for the disposal of such waste to suitably engineered facilities that might be located on or adjacent to the site of waste arising, if appropriate and subject to regulatory acceptance and stakeholder views. The strategic issues surrounding this initiative are described along with an update of progress with stakeholder consultations in relation to the proposed licensing of the first such facility at Hinkley Point A, which could be viewed as a test case for the development of similar disposal facilities at other nuclear sites in England and Wales. (authors)

Industrial aspects of radioactive waste management in Western Europe

International Nuclear Information System (INIS)

Marcus, F.R.

1976-01-01

Various aspects of waste management are discussed from the viewpoint of the nuclear industry. Future amounts of waste generated in the 15 Foratom countries in Western Europe are estimated. Industrial waste questions--as seen by electricity producers, reprocessors, and waste operators--are discussed; questions concerning decommissioning are also dealt with. A number of recommendations for further action, primarily on the part of national authorities and international organizations, are put forward. One conclusion of the study is that there is no reason for waste-management problems to impede the timely development of nuclear energy as a large-scale industrial activity in Western Europe

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.)

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)

Decommissioning of Salaspils Research Reactor

International Nuclear Information System (INIS)

Abramenkovs, A.; Popelis, A.; Abramenkova, G

2008-01-01

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

The work and perspective of the OECD/NEA in decommissioning

International Nuclear Information System (INIS)

O'Sullivan, P.; Pescatore, C.

2008-01-01

OECD member countries are increasingly faced with the need to make provisions for dealing with all aspects of dealing with the management of legacy nuclear installations, especially in terms of having in place adequate policies and regulatory frameworks for ensuring both safety and the efficient implementation of the decommissioning projects. Efficiency also requires that funding schemes are capable of providing adequate funds when required, even in the event that issues arise during implementation that were not anticipated during the planning phase. Waste management arrangements may encompass separate disposal routes for different categories of waste, including Very Low Level Waste, and may also include provisions for clearance and recycling. Recent moves in several countries towards establishing new nuclear programmes are bringing decommissioning activities into fresh focus, for reasons of public confidence (i.e. demonstrating that decommissioning can be done). In some instances existing nuclear sites will be used for the construction of new installations, but stakeholder issues are important for these sites as well. Maturing decommissioning experience should also provide lessons that would help in the reduction of lifetime costs for nuclear plants and other facilities. The challenge lying ahead is to establish a framework that will account for growing 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 release policies, as well as availability of technologies and skills, need to be kept under review. (authors)

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

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

International Nuclear Information System (INIS)

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

2016-01-01

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

Radioactive waste management

International Nuclear Information System (INIS)

1992-01-01

This book highlights the main issues of public concern related to radioactive waste management and puts them into perspective. It provides an overview of radioactive waste management covering, among other themes, policies, implementation and public communication based on national experiences. Its purpose is to assists in increasing the understanding of radioactive waste management issues by public and national authorities, organizations involved in radioactive waste management and the nuclear industry; it may also serve as a source book for those who communicate with the public. Even in the unlikely event that nuclear power does not further develop around the world, the necessity for dealing with nuclear waste from past usages, from uranium mining and milling, decontamination and decommissioning of existing nuclear facilities and from the uses of radioactive materials in medicine, industry and research would still exist. In many countries, radioactive waste management planning involves making effective institutional arrangements in which responsibilities and liabilities are well established for the technical operation and long term surveillance of disposal systems. Financing mechanisms are part of the arrangements. Continuous quality assurance and quality control, at all levels of radioactive waste management, are essential to ensure the required integrity of the system. As with any other human activity, improvements in technology and economics may be possible and secondary problems avoided. Improvements and confirmation of the efficiency of processes and reduction of uncertainties can only be achieved by continued active research, development and demonstration, which are the goals of many national programmes. International co-operation, also in the form of reviews, can contribute to increasing confidence in the ongoing work. The problem of radioactive wastes is not a unique one; it may be compared with other problems of toxic wastes resulting from many other

Overview of decommissioning research and development activities in the European Community

International Nuclear Information System (INIS)

Huber, B.

1982-01-01

The European Community's research program on the decommissioning of nuclear power plants is managed by the Commission of the European Communities and carried out by national laboratories and private firms under cost-sharing contracts. Starting in 1980, about fifty research contracts covering a large variety of topics have been let so far. The paper outlines the content, progress and selected results of the seven projects composing the program. These projects concern the following subjects: maintaining disused plants in a safe condition; decontamination for decommissioning purposes; dismantling techniques; treatment of waste materials; large waste containers; estimation of waste arisings; and plant design features facilitating decommissioning. 4 references

Nuclear Energy Agency task group on Radiological Characterisation for Decommissioning of Nuclear Installations

International Nuclear Information System (INIS)

Larsson, Arne; Weber, Inge

2016-01-01

Radiological characterisation plays a significant role in the process of decommissioning of shut-down nuclear facilities in order to ensure the protection of the environment and radiation safety. At all stages of a decommissioning programme or project, adequate radiological characterisation is of crucial importance, not least from a material and waste perspective. The radiological characterisation is a key element for planning, controlling and optimising decommissioning and dismantling activities. Experience has shown that data and information from the operation of a facility can - supplemented by recently collected and analysed data and information - be of crucial importance for decisions on waste management and for characterisation of radioactive waste. Once the dismantling has been done, some information may be hard, costly or even impossible to obtain later in the waste management process. This was the reason why the Working Party on Decommissioning and Dismantling (WPDD) of the OECD Nuclear Energy Agency (NEA) decided in late 2013 to extend the mandate of the Task Group on Radiological Characterisation and Decommissioning (TGRCD) for a second phase focusing on nuclear facility characterisation from a waste and material end-state perspective whereas the first phase focused on overall strategies of radiological characterisation. This paper gives an overview of the activities and findings within both phases up to now. (authors)

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.)

Radioactive waste management

International Nuclear Information System (INIS)

1982-07-01

In response to the Sixth Report of the Royal Commission on Environmental Pollution, a White Paper was published in 1977, announcing a number of steps to deal with the problems presented by wastes from the nuclear industry and setting out the position of the then government. The present White paper is in four sections. i. A brief description of the nature of radioactive wastes, and the general objectives of waste management. ii. What has been achieved, the role of the Radioactive Waste Management Advisory Committee, the expansion of research, and the conclusions from the review of existing controls. iii. The present position for each major category of waste, including relevant current action and research, transport and decommissioning. iv. The next steps. Research and development must continue; shallow land burial and the carefully controlled disposal of certain wastes to the sea will continue to play a role; and, for some wastes, new disposal facilities are needed at an early date. For others, the appropriate course of action at the moment is properly controlled storage. New developments are also required in organisation. Throughout, the public must be kept fully informed about what is being done, and there must be proper scope for public discussion. (U.K.)

Report on waste burial charges: Escalation of decommissioning waste disposal costs at low-level waste burial facilities

International Nuclear Information System (INIS)

1988-07-01

One of the requirements placed upon nuclear power reactor licensees by the US Nuclear Regulatory Commission (NRC) is for the licensees to periodically adjust the estimate of the cost of decommissioning their plant, in dollars of the current year, as part of the process to provide reasonable assurance that adequate funds for decommissioning will be available when needed. This report, which is scheduled to be revised annually, contains the development of a formula for escalating decommissioning cost estimates that is acceptable to the NRC, and contains values for the escalation of radioactive waste burial costs, by site and by year. The licensees may use the formula, the coefficients, and the burial escalation factors from this report in their escalation analysis, or may use an escalation rate at least equal to the escalation approach presented herein. 4 refs., 2 tabs

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

Managing wastes from the atomic age and into the future: programs, plans and challenges