WorldWideScience

Sample records for case studies decommissioning

  1. 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

  2. Feasibility studies for decommissioning

    International Nuclear Information System (INIS)

    Hladky, E.

    2000-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Salazar, M.D.

    1998-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-05-15

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

  5. Case Study to Apply Work Difficulty Factors to Decommissioning Cost Estimates

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-10-15

    This article is prepared as a guideline regarding how to apply the work difficult factor (WDF) when it comes to the estimates of the decommissioning costs. Although several cases of the decommissioning cost estimates have been made for a few commercial nuclear power plants, the different technical, site-specific economic assumptions used make it difficult to interpret those cost estimates and compare them with that of Kori-1. In addition, it is clear that we are supposed to experience difficulties being created in the process of the Kori-1 and the virtual inaccessibility to the limited areas at the pre-decommissioning stage. Estimating decommissioning costs is one of the most crucial processes since it encompasses all the spectrum of decommissioning activities from the planning to the last evaluation on whether the decommissioning has successfully been proceeded from the safety and economic perspectives. Here I suggested the activity dependent costs is only related to WDFs of the incumbent plant planning or undergone to be decommissioned since as a matter of fact, estimating WDFs is the core process to articulately scrutinize the practical costs to apply to Kori-1 project.

  6. INL - NNL an International Technology Collaboration Case Study - Advanced Fogging Technologies for Decommissioning - 13463

    International Nuclear Information System (INIS)

    Banford, Anthony; Edwards, Jeremy; Demmer, Rick; Rankin, Richard; Hastings, Jeremy

    2013-01-01

    International collaboration and partnerships have become a reality as markets continue to globalize. This is the case in nuclear sector where over recent years partnerships commonly form to bid for capital projects internationally in the increasingly contractorized world and international consortia regularly bid and lead Management and Operations (M and O) / Parent Body Organization (PBO) site management contracts. International collaboration can also benefit research and technology development. The Idaho National Laboratory (INL) and the UK National Nuclear Laboratory (NNL) are internationally recognized organizations delivering leading science and technology development programmes both nationally and internationally. The Laboratories are actively collaborating in several areas with benefits to both the laboratories and their customers. Recent collaborations have focused on fuel cycle separations, systems engineering supporting waste management and decommissioning, the use of misting for decontamination and in-situ waste characterisation. This paper focuses on a case study illustrating how integration of two technologies developed on different sides of the Atlantic are being integrated through international collaboration to address real decommissioning challenges using fogging technology. (authors)

  7. Summary of case studies presented at the WPDD topical session on stakeholder involvement in decommissioning projects - november 14, 2005

    International Nuclear Information System (INIS)

    Metcalfe, Doug

    2006-01-01

    Full text of publication follows: Two case studies were presented on experiences with stakeholder involvement in decommissioning projects. The first paper described the development of the United Kingdom Atomic Energy Authority's (UKAEA) stakeholder involvement activities for the Dounreay Nuclear Reactor Test Establishment. The second paper presented the US Nuclear Regulatory Commission regulatory process for decommissioning that includes opportunities for public involvement. The presentation contrasted the stakeholder involvement for two commercial US nuclear power plants (NPPs) that completed decommissioning in 2005, the Trojan NPP and the Maine Yankee NPP. The two case studies highlighted the importance of involving stakeholders in decommissioning projects, and provide important lessons learned. The Dounreay case study demonstrated the UKAEA's determination and commitment to continuously improve its stakeholder engagement program. In 2002, the UKAEA set out to broaden its stakeholder program by improving both public understanding and participation. With regard to public understanding, the UKAEA committed to keep the public informed on decommissioning developments, and ensure that communication was in an understandable form. To improve participation, the UKAEA actively worked to identify and engage stakeholders. The UKAEA then made efforts to involve stakeholders in decision-making activities, including the use of stakeholder panels to discuss and consider options for specific aspects of the Dounreay decommissioning and site restoration plan. In 2004, the UKAEA commissioned an independent review of its stakeholder involvement program to assess the program's effectiveness and benchmark it against best practices. The program was found to be useful, and positive feedback was provided on the use of stakeholder panels and the UKAEA's determination to deliver a broad based and effective stakeholder strategy. Recommendations to UKAEA included involving stakeholders

  8. 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

  9. 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

  10. 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.

  11. 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.

  12. Direction for the Estimation of Required Resources for Nuclear Power Plant Decommissioning based on BIM via Case Study

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Insu [Korea Institute of Construction Technology, Goyang (Korea, Republic of); Kim, Woojung [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. As demands on efficient management and use of complicated construction information increased these days, demands on the introduction of Building Information Modeling (herein after referred to as BIM) technology has increased. In the area of quotation, considerable effects are expected as to the accuracy and reliability predicting construction costs through the characteristics that can automatically estimate quantities by using attribute information of BIM model. BIM-based estimation and quotation of required resources is more accurate than the existing 2D-based quotations and have many advantages such as reviews over constructability and interference. It can be desirable to estimate decommissioning required resources in nuclear power plants using BIM as well as using tools that are compatible with usual international/industrial standards. As we looked into the cases where required resources were estimated, using BIM in Korea and abroad, they dealt with estimation of required resources, estimation of construction cost and process management at large. In each area, methodologies, classification systems, BIM, and realization tests have been used variably. Nonetheless, several problems have been reported, and among them, it is noticeable that although BIM standard classification system exists, no case was found that has used standard classification system. This means that no interlink among OBS (Object Breakdown Structure), WBS (Work Breakdown Structure) and CBS (Cost Breakdown Structure) was possible. Thus, for nuclear power plant decommissioning, decommissioning method and process, etc. shall be defined clearly in the stage of decommissioning strategy establishment, so that classification systems must be set up

  13. Direction for the Estimation of Required Resources for Nuclear Power Plant Decommissioning based on BIM via Case Study

    International Nuclear Information System (INIS)

    Jung, Insu; Kim, Woojung

    2014-01-01

    Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. As demands on efficient management and use of complicated construction information increased these days, demands on the introduction of Building Information Modeling (herein after referred to as BIM) technology has increased. In the area of quotation, considerable effects are expected as to the accuracy and reliability predicting construction costs through the characteristics that can automatically estimate quantities by using attribute information of BIM model. BIM-based estimation and quotation of required resources is more accurate than the existing 2D-based quotations and have many advantages such as reviews over constructability and interference. It can be desirable to estimate decommissioning required resources in nuclear power plants using BIM as well as using tools that are compatible with usual international/industrial standards. As we looked into the cases where required resources were estimated, using BIM in Korea and abroad, they dealt with estimation of required resources, estimation of construction cost and process management at large. In each area, methodologies, classification systems, BIM, and realization tests have been used variably. Nonetheless, several problems have been reported, and among them, it is noticeable that although BIM standard classification system exists, no case was found that has used standard classification system. This means that no interlink among OBS (Object Breakdown Structure), WBS (Work Breakdown Structure) and CBS (Cost Breakdown Structure) was possible. Thus, for nuclear power plant decommissioning, decommissioning method and process, etc. shall be defined clearly in the stage of decommissioning strategy establishment, so that classification systems must be set up

  14. Preliminary nuclear decommissioning cost study

    International Nuclear Information System (INIS)

    Sissingh, R.A.P.

    1981-04-01

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

  15. Erosion at decommissioned road-stream crossings: case studies from three northern California watersheds

    Science.gov (United States)

    Sam A. Flanagan; David Fuller; Leonard Job; Sam Morrison

    2012-01-01

    Post-treatment erosion was observed for 41 decommissioned road stream crossings in three northern California watersheds. Sites were purposefully selected in order to characterize the nature and range of post-treatment erosional responses. Sites with the highest visible erosion were selected in order to better understand the dominant process and incorporate any...

  16. Concrete release protocol case studies for decommissioning work at the Idaho National Engineering and Environmental Laboratory

    International Nuclear Information System (INIS)

    Kamboj, S.; Arnish, J.; Chen, S-Y; Parker, F. L.; Phillips, A. M.; Tripp, J. L.; Meservey, R. H.

    2000-01-01

    in 1996 was used in the analysis; therefore, because of radioactive decay, the resultant doses to receptors (now or later) would be less than the values reported in this analysis. For the generic case study, costs associated with Alternatives A and C were shown to be much smaller than for Alternative E. For the INEEL-specific case, in general, costs were much higher for Alternatives A and C than for Alternative E because of on-site disposal with zero disposal cost

  17. Detritiation studies for JET decommissioning

    International Nuclear Information System (INIS)

    Perevezentsev, A.N.; Bell, A.C.; Williams, J.; Brennan, P.D.

    2007-01-01

    JET is the world largest tokamak and has the capacity of operating with a tritium plasma. Three experimental campaigns, the Preliminary Tritium Experiment (0.1g T 2 ) in 1991, the Trace Tritium Experiment (5g T 2 ) in 2005, and the large experiment, the Deuterium-Tritium Experiment (DTE1) (100g T 2 ) in 1997, were carried out at JET with tritium plasmas. In DTE1 about 35 grams of tritium were fed directly into the vacuum vessel, with about 30% of this tritium being retained inside the vessel. In several years time JET will cease experimental operations and enter a decommissioning phase. In preparation for this the United Kingdom Atomic Energy Authority, the JET Operator, has been carrying out studies of various detritiation techniques. The materials which have been the subject of these studies include solid materials, such as various metals (Inconel 600 and 625, stainless steel 316L, beryllium, ''oxygen-free'' copper, aluminium bronze), carbon fibre composite tiles, ''carbon'' flakes and dust present in the vacuum vessel and also soft housekeeping materials. Liquid materials include organic liquids, such as vacuum oils and scintillation cocktails, and water. Detritiation of gas streams was also investigated. The purpose of the studies was to select and experimentally prove primary and auxiliary technologies for in-situ detritiation of in-vessel components and ex-situ detritiation of components removed from the vessel. The targets of ex-vessel detritiation were a reduction of the tritium inventory in and the rate of tritium out-gassing from the materials, and conversion, if possible, of intermediate level waste to low level waste and a reduction in volume of waste for disposal. The results of experimental trials and their potential application are presented. (orig.)

  18. Decommissioning and decontamination (burial ground stabilization) studies

    International Nuclear Information System (INIS)

    Cline, J.F.

    1980-01-01

    The decommissioning and decontamination of retired Hanford facilities and the future use of surrounding landscapes require isolation of contaminated wastes from the biosphere. Burial ground stabilization studies were conducted to determine the effectiveness of physical barriers for isolating contaminated wastes in shallow-land burial sites from plants and animals. This study was undertaken to determine the effectiveness of using a layer of loose rock between the waste and the surface soil covering to prevent both plant root and animal penetrations

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

    International Nuclear Information System (INIS)

    Yang, Chih Wei; Yang, Li Chen

    2014-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-08-15

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

  1. A study on the optimization of plant life extension and decommissioning for the improvement of economy in nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Jae In; Jung, K. J.; Chung, U. S.; Baik, S. T.; Park, S. K.; Lee, D. G.; Kim, H. R.; Park, B. Y

    2000-01-01

    Fundamentals on the plan, the national policy, the safety securities for the life extension of the nuclear power plant was established from the domestic/abroad documents and case studies in relation with the life extension and decommissioning of the nuclear power plant. Concerning the decommissioning of the nuclear power plant, the management according to decommissioning stages was analyzed by the investigation of the domestic/abroad standard of the decommissioning (decontamination. dismantling) technology and regulation. Moreover, the study on the cost estimation method has been carried out for the decommissioning of the nuclear power plant. (author)

  2. Challenges in Cost Estimation under Uncertainty—A Case Study of the Decommissioning of Barsebäck Nuclear Power Plant

    Directory of Open Access Journals (Sweden)

    Olav Torp

    2016-10-01

    Full Text Available Cost estimation is an important part of project planning. Over the years different approaches have developed, taking uncertainty into account in the cost estimation processes in order to tackle the dynamic nature of projects. However, when implementing these approaches, some challenges have been revealed. The aim in a cost estimation process is to establish a realistic overview of the total project costs and its uncertainties. Even though tools and methods for taking uncertainty into account are implemented, projects with cost overruns are often seen. In this paper we look into some challenges with the practice in cost estimation processes and identify possible improvements to overcome them. The purpose of this paper is to illustrate better solutions to some of the major weaknesses identified in current cost estimation practice. We use a case study of decommissioning of Barsebäck Nuclear Power Plant to illustrate how to overcome these challenges. First of all, this is an interesting case with challenges related to the project and the cost estimation process, given the complexity in the situation and that very few have experiences related to decommission of nuclear power plants. Second, we applied an approach that is not yet commonly used to develop cost estimates for this kind of projects. The paper concludes that it is possible to improve the results of uncertainty analysis of cost estimates. A well prepared process, with a suitable group of experts that go through a well-structured process, focusing both on risks and opportunities and using a top-down approach can compensate for some of the challenges related to cost estimation under uncertainty.

  3. Prioritization methodology for the decommissioning of nuclear facilities: a study case on the Iraq former nuclear complex.

    Science.gov (United States)

    Jarjies, Adnan; Abbas, Mohammed; Monken Fernandes, Horst; Wong, Melanie; Coates, Roger

    2013-05-01

    There are a number of sites in Iraq which have been used for nuclear activities and which contain potentially significant amounts of radioactive waste. The principal nuclear site being Al-Tuwaitha. Many of these sites suffered substantial physical damage during the Gulf Wars and have been subjected to subsequent looting. All require decommissioning in order to ensure both radiological and non-radiological safety. However, it is not possible to undertake the decommissioning of all sites and facilities at the same time. Therefore, a prioritization methodology has been developed in order to aid the decision-making process. The methodology comprises three principal stages of assessment: i) a quantitative surrogate risk assessment ii) a range of sensitivity analyses and iii) the inclusion of qualitative modifying factors. A group of Tuwaitha facilities presented the highest risk among the evaluated ones, followed by a middle ranking grouping of Tuwaitha facilities and some other sites, and a relatively large group of lower risk facilities and sites. The initial order of priority is changed when modifying factors are taken into account. It has to be considered the Iraq's isolation from the international nuclear community over the last two decades and the lack of experienced personnel. Therefore it is appropriate to initiate decommissioning operations on selected low risk facilities at Tuwaitha in order to build capacity and prepare for work to be carried out in more complex and potentially high hazard facilities. In addition it is appropriate to initiate some prudent precautionary actions relating to some of the higher risk facilities. Copyright © 2012 Elsevier Ltd. All rights reserved.

  4. Some studies related to decommissioning of nuclear reactors

    International Nuclear Information System (INIS)

    Bergman, C.; Menon, S.

    1990-02-01

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

  5. Studies on future decommissioning of the Swiss nuclear power plants

    International Nuclear Information System (INIS)

    Achermann, H.; Gunten, A. von; Heep, W.; Kaiser, P.; Maxeiner, H.; Paul, R.; Utzinger, E.

    2001-01-01

    The financing of future decommissioning of the Swiss nuclear power plants and the permanent, safe disposal of the wastes arising therefrom is secured by payments into a legally established decommissioning fund. In order to update the required level of payments into the fund, which have been ongoing since 1984, 20 years after the first study the costs of decommissioning have been re-calculated from scratch using complete decommissioning studies for each plant. Following the specification of boundary conditions which take into account the specific situation in Switzerland, decommissioning concepts are drawn up for the individual plants. The measures outlined in these concepts are integrated into a cost structuring plan and the decommissioning costs are then calculated using standard models (e.g. STILLKO). The radiological inventory, which is re-calculated for each plant, has a significant influence on costs. Furthermore, the disposal costs which can be allocated to decommissioning waste have to be determined; these are based on a concept in which only two types of containers are considered for disposal. The studies have resulted in decommissioning costs which, with a range between 200 and 390 million Euro, are comparable with costs in other countries. (orig.)

  6. The decommissioning of a research reactor in the USA: A case study from planning to site release

    International Nuclear Information System (INIS)

    Boing, L.E.

    1997-01-01

    Argonne National Laboratory (ANL) has completed the D ampersand D of the Experimental Boiling Water Reactor (EBWR). The project consisted of the decontamination and/or packaging as radioactive waste the reactor vessel and internals, contaminated piping systems, miscellaneous tanks, pumps, and associated equipment. The dismantling process involved the removal and size reduction of equipment and associated plumbing, ductwork, drain lines, etc. Size reduction of reactor vessel internals was performed in the fuel pool. All radioactive and mixed waste was packaged and manifested. A thorough survey of the facility was performed after the removal of contaminated and activated material. Non-radioactive waste was disposed of in the ANL landfill or recycled as appropriate. The EBWR D ampersand D project was divided into four phases. Phases I and II were completed by ANL personnel, while Phases III and IV were done by a contractor under ANL management. The final survey was performed by the contractor, while the verification survey was performed by ANL. The project lasted 118 months. Phase I was initiated in April 1986 and the final report was issued February 1996. The duration of the project was driven by the availability of funding for decommissioning. Total exposure to project personnel was 208.7 person-mSv (20.87 person-rem), with no personnel exceeding the EBWR project dose limit of 15 mSv (1.5 rem)

  7. Study for reducing radioactive solid waste at ITER decommissioning period

    International Nuclear Information System (INIS)

    Sato, Shinichi; Araki, Masanori; Ohmori, Junji; Ohno, Isamu; Sato, Satoshi; Yamauchi, Michinori; Nishitani, Takeo

    2002-11-01

    It is one of the foremost goals for ITER to demonstrate the attractiveness with regard to safety and environmental potential. This implies that the radioactive materials and waste at decommissioning phase should carefully be treated with prescribed regulations. As possible activities during the Coordinated Technical Activity (CTA), the authors have performed a feasibility study for searching the possibility of effective reduction in the activated level as reasonably achievable as possible by taking account of minimum material changes while keeping original design concept and structure. Major induced activation in ITER comes from activated nickel and cobalt so that it is effective for the major structural components to minimize their material contents. Employing less Ni and Co steel in place of high-Ni austenitic stainless steel for blanket shield block, vacuum vessel shield material and TF coil casing has been considered as one of the effective plans to reduce the activated materials at the decommissioning phase. In this study, two less-Ni austenitic stainless steels are evaluated; one is high-Mn austenitic stainless steel JK2 which is developing for jacket material of ITER CS coil and the other is SS204L/ASTM-XM-11 which is also high-Mn steel specified in the popular standards such as American Society of Testing and Material (ASTM). Based on the material changes, activation analyses have been performed to investigate the possibility of reducing radioactive wastes. As a most impressive result, at 40 years after the termination some of main components such as a TF coil casing will reach to the clearance level which is specified by IAEA, and most components will be categorized into extremely low level waste except for limited components. These results will give the appropriate short decommissioning period that is assumed to start at 100 years after the termination in the original design. (author)

  8. Nuclear decommissioning trusts: A case for convertible bonds

    International Nuclear Information System (INIS)

    Nichols, R.W.

    1992-01-01

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

  9. Topical Session on the Decommissioning and Dismantling Safety Case

    International Nuclear Information System (INIS)

    2002-01-01

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

  10. Costs of Decommissioning Nuclear Power Plants

    International Nuclear Information System (INIS)

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

    2016-01-01

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

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

    International Nuclear Information System (INIS)

    Matsuhashi, Kazuya; Yanagihara, Satoshi

    2015-01-01

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

  12. Workshop on decommissioning

    International Nuclear Information System (INIS)

    Broden, K.

    2005-12-01

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

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

    International Nuclear Information System (INIS)

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

    2012-02-01

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

  14. 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)

  15. Decommissioning of a RCRA Treatment, Storage, and Disposal Facility: A case study of the 216-A-29 ditch at the Hanford Site

    International Nuclear Information System (INIS)

    Smith, D.L.; Hayward, W.M.

    1991-09-01

    The 216-A-29 ditch is located in the central portion of the Hanford Site with Operable Unit 200-PO-5. The ditch is classified under the Resource Conservation and Recovery Act of 1976 as a Treatment, Storage, and Disposal (TSD) Facility and as such, is to be removed from service in support of the Hanford Federal Facility Agreement and Consent Order Tri-Party Agreement (Ecology et al. 1989) Milestone M-17-10, which states ''cease all liquid discharges to hazardous land disposal units unless such units have been clean closed in accordance with the Resource Conservation and Recovery Act of 1976''. The 216-A-29 ditch is one stream feeding the 216-B-3 Pond system, and its removal from service was necessary to support the closure strategy for the 216-B-3 Pond system. Interim stabilization of the 216-A-29 ditch is the first step required to comply with the Tri-Party Agreement (Ecology et al. 1989) and the eventual decommissioning of the entire B Pond system. Interim stabilization was required to maintain the 216-A-29 ditch in a stable configuration until closure actions have been determined and initiated. 4 refs., 3 figs

  16. Nuclear decommissioning planning, execution and international experience

    CERN Document Server

    2012-01-01

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

  17. TWRS privatization: Phase I monitoring well engineering study and decommissioning plan

    Energy Technology Data Exchange (ETDEWEB)

    Williams, B.A.

    1996-09-11

    This engineering study evaluates all well owners and users, the status or intended use of each well, regulatory programs, and any future well needs or special purpose use for wells within the TWRS Privatization Phase I demonstration area. Based on the evaluation, the study recommends retaining 11 of the 21 total wells within the demonstration area and decommissioning four wells prior to construction activities per the Well Decommissioning Plan (WHC-SD-EN-AP-161, Rev. 0, Appendix I). Six wells were previously decommissioned.

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

    International Nuclear Information System (INIS)

    Hilton, P.A.

    2014-01-01

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

  19. 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)

  20. 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

  1. Decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Lunning, W.H.

    1977-01-01

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

  2. Training for decommissioning

    International Nuclear Information System (INIS)

    Dietzold, A.

    2009-01-01

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

  3. Decommissioning nuclear facilities

    International Nuclear Information System (INIS)

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

    1976-01-01

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

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  5. Workshop on decommissioning; Seminarium om avveckling

    Energy Technology Data Exchange (ETDEWEB)

    Broden, K. (ed.)

    2005-12-15

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

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

    International Nuclear Information System (INIS)

    LaGuardia, Thomas S.; Pescatore, Claudio; )

    2014-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-10-15

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

  8. Decommissioning Handbook

    International Nuclear Information System (INIS)

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

    1994-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  10. Decommissioning Handbook

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

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

  11. Current studies on the decommissioning materials recycling at Japan Atomic Energy Research Institute

    Energy Technology Data Exchange (ETDEWEB)

    Fujiki, K.; Nakamura, H. [Japan Atomic Research Inst., Tokai, Ibaraki (Japan). Dept. of Decommissioning and Waste Management

    1993-12-31

    Rational treatment of a large volume of solid wastes resulting from the reactor dismantling is a key to success to carry out the decommissioning smoothly. From this viewpoint, the Japan Atomic Energy Research Institute (JAERI) has been conducting development of the recycling technology for metal waste and an investigation study on the rational recycling system for the dismantling wastes recycling. With respect to the development of the recycling technology, series of melting tests using non-contaminated metals, metal waste dismantled from JPDR or imitated waste using radioisotopes have been conducted. The basic characteristics of the radionuclides transport behavior during the melting have been understood. In the investigation study on the rational recycling system, a scenario of recycling the wastes was developed based on the amount of waste arising from decommissioning nuclear power plants, and necessary processing facilities were examined, and safety and economy of the process were evaluated.

  12. Technical support to the social cost study of Ignalina NPP decommissioning

    International Nuclear Information System (INIS)

    Vitkiene, E.

    2001-01-01

    Description of Phare project on assessment of social cost related with decommissioning of unit 1 of Ignalina NPP is presented. This is the first project of social guarantees in Visaginas financed by European Commission Project will develop pilot studies aimed at encouraging small and medium size business in Visaginas, creating new jobs, employment of young people. The project will also consult about the activities of the said projects, inform the community about the things being done to mitigate social impact

  13. 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.

  14. 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

  15. A nationwide modelling approach to decommissioning - 16182

    International Nuclear Information System (INIS)

    Kelly, Bernard; Lowe, Andy; Mort, Paul

    2009-01-01

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

  16. Irradiated graphite studies prior to decommissioning of G1, G2 and G3 reactors

    International Nuclear Information System (INIS)

    Bonal, J.P.; Vistoli, J.Ph.; Combes, C.

    2005-01-01

    G1 (46 MW th ), G2 (250 MW th ) and G3 (250 MW th ) are the first French plutonium production reactors owned by CEA (Commissariat a l'Energie Atomique). They started to be operated in 1956 (G1), 1959 (G2) and 1960 (G3); their final shutdown occurred in 1968, 1980 and 1984 respectively. Each reactor used about 1200 tons of graphite as moderator, moreover in G2 and G3, a 95 tons graphite wall is used to shield the rear side concrete from neutron irradiation. G1 is an air cooled reactor operated at a graphite temperature ranging from 30 C to 230 C; G2 and G3 are CO 2 cooled reactors and during operation the graphite temperature is higher (140 C to 400 C). These reactors are now partly decommissioned, but the graphite stacks are still inside the reactors. The graphite core radioactivity has decreased enough so that a full decommissioning stage may be considered. Conceming this decommissioning, the studies reported here are: (i) stored energy in graphite, (ii) graphite radioactivity measurements, (iii) leaching of radionuclide ( 14 C, 36 Cl, 63 Ni, 60 Co, 3 H) from graphite, (iv) chlorine diffusion through graphite. (authors)

  17. Disentangling rhetoric and reality: an international Delphi study of factors and processes that facilitate the successful implementation of decisions to decommission healthcare services.

    Science.gov (United States)

    Robert, Glenn; Harlock, Jenny; Williams, Iestyn

    2014-09-10

    The need to better understand processes of removing, reducing, or replacing healthcare services that are no longer deemed essential or effective is common across publicly funded healthcare systems. This paper explores expert international opinion regarding, first, the factors and processes that shape the successful implementation of decommissioning decisions and, second, consensus as to current best practice. A three round Delphi study of 30 international experts was undertaken. In round one, participants identified factors that shape the outcome of decommissioning processes; responses were analysed using conventional content analysis. In round two, responses to 88 Likert scale statements derived from round one were analysed using measures of the degree of consensus. In round three the statements that achieved low consensus were then repeated but presented alongside the overall results from round two. The responses were re-analysed to observe whether the degree of consensus had changed. Any open comments provided during the Delphi study were analysed thematically. Participants strongly agreed that three considerations should ideally inform decommissioning decisions: quality and patient safety, clinical effectiveness and cost-effectiveness. Although there was less consensus as to which considerations informed such decisions in practice, those that drew the most agreement were: cost/budgetary pressures, government intervention and capital costs/condition. Important factors in shaping decommissioning were: strength of executive leadership, strength of clinical leadership, quality of communications, demonstrable benefits and clarity of rationale/case for change. Amongst the 19 best practice recommendations high consensus was achieved for: establishing a strong leadership team, engaging clinical leaders from an early stage, and establishing a clear rationale for change. There was a stark contrast between what experts thought should determine decommissioning decisions

  18. Recordkeeping in the decommissioning process

    International Nuclear Information System (INIS)

    Boing, L. E.

    2000-01-01

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

  19. Joint U.S./Russian Study on the Development of a Preliminary Cost Estimate of the SAFSTOR Decommissioning Alternative for the Leningrad Nuclear Power Plant Unit #1

    Energy Technology Data Exchange (ETDEWEB)

    SM Garrett

    1998-09-28

    The objectives of the two joint Russian/U.S. Leningrad Nuclear Power Plant (NPP) Unit #1 studies were the development of a safe, technically feasible, economically acceptable decom missioning strategy, and the preliminary cost evaluation of the developed strategy. The first study, resulting in the decommissioning strategy, was performed in 1996 and 1997. The preliminary cost estimation study, described in this report, was performed in 1997 and 1998. The decommissioning strategy study included the analyses of three basic RBM.K decommission- ing alternatives, refined for the Leningrad NPP Unit #1. The analyses included analysis of the requirements for the planning and preparation as well as the decommissioning phases.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-05-15

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

  1. Study on the Development of Methodology for Cost Calculations and Financial Planning of Decommissioning Operations

    International Nuclear Information System (INIS)

    2001-12-01

    The following study deals with the development of methodology for cost calculations and financial planning of decommissioning operations. It has been carried out by EDF / FRAMATOME / VUJE / SCK-CEN in the frame of the contract B7-032/2000/291058/MAR/C2 awarded by the European Commission. This study consists of 4 parts. The first task objective is to develop a reliable and transparent methodology for cost assessment and financial planning sufficient precise but without long and in depth investigations and studies. This methodology mainly contains: Calculation methods and algorithms for the elaboration of costs items making up the whole decommissioning cost. Estimated or standard values for the parameters and for the cost factors to be used in the above-mentioned algorithms Financial mechanism to be applied as to establish a financial planning. The second part task is the provision of standard values for the different parameters and costs factors described in the above-mentioned algorithms. This provision of data is based on the own various experience acquired by the members of the working team and on existing international references (databases, publications and reports). As decommissioning operations are spreading over several dozens of years, the scope of this task the description of the financial mechanisms to be applied to the different cost items as to establish a complete financial cost. It takes into account the financial schedule issued in task 1. The scope of this task consists in bringing together in a guideline all the information collected before: algorithms, data and financial mechanisms. (A.L.B.)

  2. Joint US/Russian study on the development of a decommissioning strategy plan for RBMK-1000 unit No. 1 at the Leningrad Nuclear Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The objective of this joint U.S./Russian study was to develop a safe, technically feasible, economically acceptable strategy for decommissioning Leningrad Nuclear Power Plant (LNPP) Unit No. 1 as a representative first-generation RBMK-1000 reactor. The ultimate goal in developing the decommissioning strategy was to select the most suitable decommissioning alternative and end state, taking into account the socioeconomic conditions, the regulatory environment, and decommissioning experience in Russia. This study was performed by a group of Russian and American experts led by Kurchatov Institute for the Russian efforts and by the Pacific Northwest National Laboratory for the U.S. efforts and for the overall project.

  3. Joint US/Russian study on the development of a decommissioning strategy plan for RBMK-1000 unit No. 1 at the Leningrad Nuclear Power Plant

    International Nuclear Information System (INIS)

    1997-12-01

    The objective of this joint U.S./Russian study was to develop a safe, technically feasible, economically acceptable strategy for decommissioning Leningrad Nuclear Power Plant (LNPP) Unit No. 1 as a representative first-generation RBMK-1000 reactor. The ultimate goal in developing the decommissioning strategy was to select the most suitable decommissioning alternative and end state, taking into account the socioeconomic conditions, the regulatory environment, and decommissioning experience in Russia. This study was performed by a group of Russian and American experts led by Kurchatov Institute for the Russian efforts and by the Pacific Northwest National Laboratory for the U.S. efforts and for the overall project

  4. 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)

  5. Decommissioning handbook

    International Nuclear Information System (INIS)

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

    1980-11-01

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

  6. Decommissioning handbook

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-11-01

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

  7. Modelling of nuclear power plant decommissioning financing.

    Science.gov (United States)

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

    2015-06-01

    Costs related to the decommissioning of nuclear power plants create a significant financial burden for nuclear power plant operators. This article discusses the various methodologies employed by selected European countries for financing of the liabilities related to the nuclear power plant decommissioning. The article also presents methodology of allocation of future decommissioning costs to the running costs of nuclear power plant in the form of fee imposed on each megawatt hour generated. The application of the methodology is presented in the form of a case study on a new nuclear power plant with installed capacity 1000 MW. © The Author 2015. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  8. Nuclear decommissioning

    International Nuclear Information System (INIS)

    Lawton, H.

    1987-01-01

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

  9. ORNL decontamination and decommissioning program

    International Nuclear Information System (INIS)

    Bell, J.P.

    1980-01-01

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

  10. Waste management considerations in nuclear facility decommissioning

    International Nuclear Information System (INIS)

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

    1981-01-01

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

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

    International Nuclear Information System (INIS)

    Allen, R.P.; Konzek, G.J.; Schneider, K.J.; Smith, R.I.

    1987-09-01

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

  12. Decommissioning: a problem or a challenge?

    Directory of Open Access Journals (Sweden)

    Mele Irena

    2004-01-01

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

  13. Planning activities for ANPP decommissioning

    International Nuclear Information System (INIS)

    Ghazaryan, K.G.

    2002-01-01

    suggested solution was a choice of SAFSTOR as a viable decommissioning option. Spent fuel management is not considered part of decommissioning; however it can strongly affect the decommissioning strategy. Currently the spent nuclear fuel is being stored on site in pools and in a newly constructed NUHOMS storage facility built by FRAMATOME under license of USA Transnuclear West Company. The facility includes 11 horizontal storage modules (HSM). Each HSM has a capacity of 56 non-failed fuel assemblies. A capacity of the existing dry storage facility is not sufficient to accommodate all spent fuel generated during plant operation. However, the NUHOMS concept is modular and it is possible to increase the storage capacity. The facility is designed for 50 years storage of spent nuclear fuel. In any case, these studies should be considered as an informative basis only. Much more additional information should be collected and the detailed characterization survey, i.e. the comprehensive engineering and radiological survey, conducted to have sufficient data for all further planning activities. (author)

  14. Decommissioning in western Europe

    International Nuclear Information System (INIS)

    Lundqvist, K.

    1999-12-01

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

  15. 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.)

  16. 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)

  17. Experiences in teaching decommissioning - 16179

    International Nuclear Information System (INIS)

    Catlow, Fred

    2009-01-01

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

  18. 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

  19. Summary of comments received at workshop on use of a Site Specific Advisory Board (SSAB) to facilitate public participation in decommissioning cases

    International Nuclear Information System (INIS)

    Caplin, J.; Padge, G.; Smith, D.; Wiblin, C.

    1995-06-01

    The Nuclear Regulatory Commission (NRC) is conducting an enhanced participatory rulemaking to establish radiological criteria for the decommissioning of NRC-licensed facilities. As part of this rulemaking, On August 20, 1994 the NRC published a proposed rule for public comment. Paragraph 20.1406(b) of the proposed rule would require that the licensee convene a Site Specific Advisory Board (SSAB) if the licensee proposed release of the site for restricted use after decommissioning. To encourage comment the NRC held a workshop on the subject of $SABs on December 6, 7, and 8, 1994. This report summarizes the 567 comments categorized from the transcript of the workshop. The commenters at the workshop generally supported public participation in decommissioning cases. Many participants favored promulgating requirements in the NRC's rules. Some industry participants favored relying on voluntary exchanges between the public and the licensees. Many participants indicated that a SSAB or something functionally equivalent is needed in controversial decommissioning cases, but that some lesser undertaking can achieve meaningful public participation in other cases. No analysis or response to the comments is included in this report

  20. 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

  1. A study on the application of standards for clearance of metal waste generated during the decommissioning of NPP by using the RESRAD-RECYCLE

    Energy Technology Data Exchange (ETDEWEB)

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

    2016-12-15

    The metal waste generated during nuclear power plant decommissioning constitutes a large proportion of the total radioactive waste. This study investigates the current status of domestic and international regulatory requirements for clearance and the clearance experience of domestic institutions. The RESRAD-RECYCLE code was used for analyzing the clearance of the metal wastes generated during actual nuclear power plant decommissioning, and assessment of the exposure dose of twenty-six scenarios was carried out. The evaluation results will be useful in preliminary analysis of clearance and recycling during nuclear power plant decommissioning. As a next step, the effects of reducing disposal costs by clearance can be studied.

  2. 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

  3. The Chinon A decommissioning plan

    International Nuclear Information System (INIS)

    Le Dantec, M.

    1991-01-01

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

  4. Decommissioning of offshore installations

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-07-01

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

  5. Decommissioning strategy and schedule for a multiple reactor nuclear power plant site

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Deiglys Borges; Moreira, Joao M.L.; Maiorino, Jose Rubens, 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

    2015-07-01

    The decommissioning is an important part of every Nuclear Power Plant life cycle gaining importance when there are more than one plant at the same site due to interactions that can arise from the operational ones and a decommissioning plant. In order to prevent undesirable problems, a suitable strategy and a very rigorous schedule should implemented and carried. In this way, decommissioning tasks such as fully decontamination and dismantling of activated and contaminated systems, rooms and structures could be delayed, posing as an interesting option to multiple reactor sites. The present work aims to purpose a strategy and a schedule for the decommissioning of a multiple reactor site highlighting the benefits of delay operational tasks and constructs some auxiliary services in the site during the stand by period of the shutdown plants. As a case study, will be presented a three-reactor site which the decommissioning process actually is in planning stage and that should start in the next decade. (author)

  6. Ringhals Site Study 2013 - An assessment of the decommissioning cost for the Ringhals site

    Energy Technology Data Exchange (ETDEWEB)

    Hansson, Tommy [Ringhals AB, Ringhals (Sweden); Norberg, Thomas [Solvina AB, Goeteborg (Sweden); Knutsson, Andreas; Fors, Patrik; Sandebert, Camilla [Vattenfall AB, Stockholm (Sweden)

    2013-03-15

    This report presents the decommissioning cost for the Ringhals site as of 2013. The objective has been to make a best estimate of the costs within the uncertainties of a budgetary estimate. To achieve this, the decommissioning costs have been assessed with support from TLG Services Inc., utilizing their knowledge and experience from U.S. decommissioning projects incorporated in their cost estimation platform DECCER. The 2013 estimate has included the development of a Ringhals-specific cost estimation method that allows for successive improvement in the future. In-house experiences have been included and the method is based on the present decommissioning strategy according to Ringhals decommissioning plan. Two basic approaches have been used in the cost assessment; a bottom up approach to develop unit cost factors (UCF) for recurrent work; and a specific analogy approach for cost estimating special items. The basic, activity-dependent, costs have been complemented by period-dependent costs, derived, among other things, from SKB's newly developed reference planning and organizational model for a Swedish decommissioning project. Furthermore, collateral costs based on the experiences of Barsebaeck have been included. As a final point, all costs have been adjusted for industrial standard contingencies, as suggested by TLG, to achieve a best estimate. In order to make the cost intelligible a comprehensive description of the assumptions, boundary conditions and general basis of the estimate is included in this report. All costs have been reported both according to the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations published by OECD/NEA and according to the SKB developed EEF structure. Furthermore, common costs have been isolated to a theoretical unit 0 to make the cost for respective unit even more comparable on a national and international scale. The calculations show that the total cost for the decommissioning of the Ringhals

  7. Ringhals Site Study 2013 - An assessment of the decommissioning cost for the Ringhals site

    International Nuclear Information System (INIS)

    Hansson, Tommy; Norberg, Thomas; Knutsson, Andreas; Fors, Patrik; Sandebert, Camilla

    2013-03-01

    This report presents the decommissioning cost for the Ringhals site as of 2013. The objective has been to make a best estimate of the costs within the uncertainties of a budgetary estimate. To achieve this, the decommissioning costs have been assessed with support from TLG Services Inc., utilizing their knowledge and experience from U.S. decommissioning projects incorporated in their cost estimation platform DECCER. The 2013 estimate has included the development of a Ringhals-specific cost estimation method that allows for successive improvement in the future. In-house experiences have been included and the method is based on the present decommissioning strategy according to Ringhals decommissioning plan. Two basic approaches have been used in the cost assessment; a bottom up approach to develop unit cost factors (UCF) for recurrent work; and a specific analogy approach for cost estimating special items. The basic, activity-dependent, costs have been complemented by period-dependent costs, derived, among other things, from SKB's newly developed reference planning and organizational model for a Swedish decommissioning project. Furthermore, collateral costs based on the experiences of Barsebaeck have been included. As a final point, all costs have been adjusted for industrial standard contingencies, as suggested by TLG, to achieve a best estimate. In order to make the cost intelligible a comprehensive description of the assumptions, boundary conditions and general basis of the estimate is included in this report. All costs have been reported both according to the International Structure for Decommissioning Costing (ISDC) of Nuclear Installations published by OECD/NEA and according to the SKB developed EEF structure. Furthermore, common costs have been isolated to a theoretical unit 0 to make the cost for respective unit even more comparable on a national and international scale. The calculations show that the total cost for the decommissioning of the Ringhals site is

  8. A study of implementing In-Cycle-Shuffle strategy to a decommissioning boiling water reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Chung-Yuan, E-mail: tuckjason@iner.gov.tw; Tung, Wu-Hsiung; Yaur, Shyun-Jung

    2017-06-15

    Highlights: • A loading pattern strategy ICS (In-Cycle-Shuffle) was implemented to the last cycle of the boiling water reactor. • The best power sharing distribution and ICS timing was found. • A new parameter “Burnup sharing” is presented to evaluate ICS strategy. - Abstract: In this paper, a loading pattern strategy In-Cycle-Shuffle (ICS) is implemented to the last cycle of the boiling water reactor (BWR) before decommissioning to save the fuel cycle cost. This method needs a core shutdown during the operation of a cycle to change the loading pattern to gain more reactivity. The reactivity model is used to model the ICS strategy in order to find out the best ICS timing and the optimum power sharing distribution before ICS and after ICS. Several parameters of reactivity model are modified and the effect of burnable poison, gadolinium (Gd), is considered in this research. Three cases are presented and it is found that the best ICS timing is at about two-thirds of total cycle length no matter the poisoning effect of Gd is considered or not. According to the optimum power sharing distribution result, it is suggested to decrease the once burnt power and increase the thrice burnt fuel power as much as possible before ICS. After ICS, it is suggested to increase the positive reactivity fuel power and decrease the thrice burnt fuel power as much as possible. A new parameter “Burnup sharing” is presented to evaluate the special case whose EOC power weighting factor and the burnup accumulation factor in the reactivity model are quite different.

  9. An Applied Study on the Decontamination and Decommissioning of the Map Tube Facility 317 Area Argonne National Laboratory, Chicago

    International Nuclear Information System (INIS)

    Varley, Geoff; Rusch, Chris

    2005-01-01

    less. Unlike the MTF, AT has some storage vaults in addition to storage tubes. Based on available descriptions of the nature of the wastes stored in AT and the MTF, in general terms the range of wastes appears to be somewhat similar. In the case of the MTF it was determined that radioactive sludge was present at the bottom of the tubes, resulting from water ingress and corrosion of both storage containers and their contents. In the case of AT it is not known exactly what the condition of the tubes is but it is recognised that leakage/contamination in the lower parts of the tubes is likely to have occurred. This is an important consideration in the planning of the AT decommissioning program and the related cost estimate, principally because of the potential consequence of different approaches and specific techniques chosen to implement decommissioning. The AT decommissioning cost estimate report is not entirely clear in detail regarding the specific methodology to be adopted. In addition there are a number of important uncertainties concerning the extent of radioactive contamination. Depending on what the reality turns out to be, the decommissioning methodology could be affected and the quantities of wastes in various categories also could vary. In any event, the AT cost estimate report is unclear regarding waste volumes in a number of respects. The AT cost estimate is presented in a similar fashion to several other recent decommissioning cost estimates prepared by Westinghouse for SVAFO, using an approach and presentation format that suffers somewhat from: - Not always being clear, - Not always being unambiguous and easy to understand and, - Lack of detail and clear substantiation of assumptions in some important areas. Setting these concerns aside, the available information has been evaluated and compared with the Argonne MTF decommissioning costs and other selected NAC derived decommissioning cost benchmarks. In summary the conclusions for the AT decommissioning cost

  10. Needs for European decommissioning academy (EDA)

    International Nuclear Information System (INIS)

    Slugen, Vladimir

    2014-01-01

    According to analyses presented at EC meeting focused on decommissioning organized at 11.9.2012 in Brussels, it was stated that at least 500 new international experts for decommissioning will be needed in Europe up to 2025, which means about 35 per year. Having in mind the actual EHRO-N report from 2013 focused on operation of nuclear facilities and an assumption that the ratio between nuclear experts, nuclearized and nuclear aware people is comparable also for decommissioning, as well as the fact that the special study branch for decommissioning in the European countries almost does not exist, this European Decommissioning Academy (EDA) could be helpful in the over-bridging this gap. The main goal is - from about 74% of nuclearized experts (graduated at different technical Universities and increased their nuclear knowledge and skills mostly via on-job training and often in the area of NPP operation) to create nuclear experts for decommissioning via our post-gradual coursed organized in two semester study at our Academy, which will include the lessons, practical exercises in our laboratories, on-site training at NPP V-1 in Jaslovske Bohunice, Slovakia as well as 3 days technical tour to JAVYS (Slovakia), UJV Rez (Czech Rep.) and PURAM (Hungary), respectively. Beside the exams in selected topics (courses), the final thesis written under supervision of recognized experts will be the precondition for graduation and certification of the participants. For the first run of the EDA scheduled on 2014 we would like to focus on VVER decommissioning issues because this reactor type is the most distributed design in the world and many of these units are actually in decommissioning process or will be decommissioned in the near future in Europe. The growing decommissioning market creates a potential for new activities, with highly skilled jobs in an innovative field, involving high-level technologies. A clear global positioning of the EU will stimulate the export of know-how to

  11. A study on Prediction of Radioactive Source-term from the Decommissioning of Domestic NPPs by using CRUDTRAN Code

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jong Soon; Lee, Sang Heon; Cho, Hoon Jo [Department of Nuclear Engineering Chosun University, Gwangju (Korea, Republic of)

    2016-10-15

    For the study, the behavior mechanism of corrosion products in the primary system of the Kori no.1 was analyzed, and the volume of activated corrosion products in the primary system was assessed based on domestic plant data with the CRUDTRAN code used to predict the volume. It is expected that the study would be utilized in predicting radiation exposure of workers performing maintenance and repairs in high radiation areas and in selecting the process of decontaminations and decommissioning in the primary system. It is also expected that in the future it would be used as the baseline data to estimate the volume of radioactive wastes when decommissioning a nuclear plant in the future, which would be an important criterion in setting the level of radioactive wastes used to compute the quantity of radioactive wastes. The results of prediction of the radioactive nuclide inventory in the primary system performed in this study would be used as baseline data for the estimation of the volume of radioactive wastes when decommissioning NPPs in the future. It is also expected that the data would be important criteria used to classify the level of radioactive wastes to calculate the volume. In addition, it is expected that the data would be utilized in reducing radiation exposure of workers in charge of system maintenance and repairing in high radiation zones and also predicting the selection of decontaminations and decommissioning processes in the primary systems. In future researches, it is planned to conduct the source term assessment against other NPP types such as CANDU and OPR-1000, in addition to the Westinghouse type nuclear plants.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-03-15

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

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

    International Nuclear Information System (INIS)

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

    2007-03-01

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

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

    International Nuclear Information System (INIS)

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

    2004-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-12-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-12-01

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

  17. CCA retention and its effects on the bonding performance of decommissioned treated wood: a preliminary study

    Science.gov (United States)

    Cheng Piao; Todd F. Shupe; Mark Gibson; Chung Y. Hse

    2009-01-01

    Chromated copper arsenate (CCA) continues to be widely used as a wood preservative for industrial uses in the U.S. Disposal of treated wood is a potential long-term environmental liability. Current practices for disposing of decommissioned preservative-treated wood include landfilling and incineration, which are increasingly impractical due to environmental...

  18. On Cost Estimate for Decommissioning of one Isotope Central

    International Nuclear Information System (INIS)

    Marek Vasko et al

    2010-08-01

    The main scope of this study has been to calculate the future cost for decommission and dismantling the Isotope central at the Studsvik site using the OMEGA CODE. Detailed empirical information is used in the study for 'bench-marking' purposes, in such cases when there is a need to supplement and correct field data from the industry. In the present study, data has been retrieved and organized such that the estimated costs for decommissioning of the Isotope Central become transparent and reliable. This approach gives a preliminary qualitative indication about the accuracy of the cost estimate delivered by the industry

  19. Decommissioning of CANDU nuclear power stations

    International Nuclear Information System (INIS)

    Unsworth, G.N.

    1979-04-01

    This report summarizes the results of a detailed study of the various procedures and costs associated with decommissioning a CANDU reactor. The three internationally recognized 'stages' of decommissioning (mothballing, encasement, and dismantling) are discussed. It is concluded that decommissioning is possible with presently available technology, and that costs could be financed by only a marginal increase in the cost of electricity during the life of the reactor. The environmental impact would be no greater than that of any large construction project. (auth)

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

    International Nuclear Information System (INIS)

    Hirashima, Shikazoh

    1983-01-01

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

  1. Decommissioning regulations and programme (in Belgium)

    International Nuclear Information System (INIS)

    Braeckeveldt, M.; Schrauben, M.

    1995-01-01

    A regulatory process for decommissioning in Belgium has been implemented since 1991. The National Agency for Radioactive Waste and Enriched Fissile Materials NIRAS/ONDRAF has been entrusted with some assignments regarding decommissioning for all national nuclear installations. Furthermore, the Agency is responsible since 1980 for the safe management of all radioactive waste produced in Belgium, including decommissioning waste. The Agency's assignments in the field of decommissioning cover data collection and evaluations of nuclear plants with the aim to plan future waste management strategies and to provide the necessary fundings for decommissioning during the plant operational life-time. Furthermore, the Agency may be in charge of the execution of the decommissioning programmes in case of request or failure of the operator/owner of a plant or for the so-called ''Nuclear Liabilities'', in which case the Agency is entrusted by the Belgian State with the execution of the programmes. To fulfill its legal assignments, NIRAS/ONDRAF has made recommendations to nuclear plant owners for drawing up decommissioning plans and has set up an integrated data processing system to evaluate decommissioning programmes. (Author)

  2. Utility planning for decommissioning

    International Nuclear Information System (INIS)

    Williams, D.H.

    1982-01-01

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

  3. Decommissioning Trawsfynydd - How public consultation shaped the strategy

    International Nuclear Information System (INIS)

    Kay, Martin J.

    1995-01-01

    This case study discusses the ned of consulting the public when decommissioning a nuclear power plants. When Trawsfynydd power station in North Wales shutdown in July 1993, Nuclear Electric's strategy for decommissioning its stations was not clearly defined. The company had altered its corporate policy on decommissioning fro he strategy referred to as the 'Reference Case' which had been approved by the Government, to the preferred 'Deferred Safestore' strategy, which was waiting Government approval. Deferred Safestore is preferred as it simplifies the engineering work involved by capitalising an the basic strength and integrity of the reactor building. It minimises thd radiation exposure to workers and radioactivity released to the environment, reduces the amount of radioactive waste produced and significantly cuts the total decommissioning cost. The closure and the decommissioning of Trawsfynydd power station was a sensitive issue as: The station lies within a National Park of outstanding beauty. The economic circumstances in the area are such that employment opportunities are very limited. At a crucial time when the company was approaching a Government review which would decide its future, Nuclear Electric could not afford to lose any credibility. A public consultation programme was launched in the vicinity of the power station To gauge the reactions of the public and elected local government bodies to a series of decommissioning options. Nuclear Electric presented three main options with details on the employment opportunities, the costs, and the lorry loads of material involved with each. The people were identified on whom decommissioning Trawsfynydd power station is likely to have an environmental or socioeconomic impact. As a result of the polls the Nuclear Electric received feedback in two ways. Formal feedback from the local councils Independent analysis of the completed questionnaires. The company was wholly committed to a meaningful consultation. Before

  4. Decommissioning and decontamination

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  5. Cost estimation for decommissioning of research reactors

    International Nuclear Information System (INIS)

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

    2013-01-01

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

  6. Recommended IAEA decommissioning levels

    International Nuclear Information System (INIS)

    Jacquemin, M.

    1977-01-01

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

  7. National waste terminal storage repository in a bedded salt formation for spent unreprocessed fuel. Special study No. 1. Twenty-five-year retrievability, decommissioning cost estimate

    International Nuclear Information System (INIS)

    1978-11-01

    This estimate covers decommissioning costs of facilities for the receipt, handling, and storage in bedded salt of canistered spent fuel assemblies from both BWR and PWR commercial power plants. The estimate includes all decommissioning costs for a repository, based on 25-year retrievability, constructed in accordance with the design shown in Conceptual Design Report (CDR), as modified by Special Study No. 1 (KE Report No. 78-60-RE) and decommissioned in accordance with the program outlined in the Conceptual Design Description Report, KE Report No. 78-58-R. Costs for Operating Contractor personnel on the site at this time are included in this report and not in the Operating Cost Estimate (KE Report 78-63-RE). The operating cost estimates end with the completion of storage room backfilling. The three major elements of decommissioning are: demolition of surface facilities, backfilling of main entries and airways, and shaft liner removal and shaft plugging. EDIT, ECON, and DELOX computer programs and a chart of accounts were furnished by UCC-ND under direction of the Government and the line item-capital-cost estimate was prepared according to the prescribed format. The decommissioning cost estimate referenced herein is in the same format as its companion line item-capital-cost estimate KE Report 78-62-RE

  8. Economic aspects of decommissioning

    International Nuclear Information System (INIS)

    Jenne, C.

    1988-01-01

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

  9. 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)

  10. Studies on decommissioning of TRIGA reactors and site restoration technologies in the Republic of Korea

    International Nuclear Information System (INIS)

    Oh, Won-Zin; Kim, Gye-Nam; Won, Hui-Jun

    2002-01-01

    Research and development on research reactor decommissioning and environmental restoration has been carried out at KAERI since 1997 to prepare for the decommissioning of KAERI's two TRIGA-type research reactors, which had been shut down since 1995. A 3-D graphic model of the TRIGA research reactor was built using IGRIP. The dismantling process was simulated in the graphic environment to verify the feasibility of individual operations before the execution of the remote dismantling process. An under-water wall-climbing robot, moving by propeller injection, and identifying its coordinates by using a laser sensor, was developed and tested in the TRIGA reactor pool by measuring a radioactive contamination map of the reactor surface. Using MODFLOW and TRIGA site geological data, a computer simulation of the underground migration of residual radionuclides, after the TRIGA reactor decommissioning, was carried out. It was found that the underground migration rate was very slow such that, when radionuclide decay and dilution are considered, the residual radionuclides will not have a significant environmental impact. The soil decontamination R and D, using soil washing, solvent flushing and electro-decontamination technologies, was carried out to determine the best method for decontaminating the soil waste accumulated in KAERI. The decontamination results indicated that, using the soil washing method, more than 80% of the soil wastes could be decontaminated well enough to discharge them to the environment. It was also determined that the control of solution pH and temperature in the soil washing process is important for the reduction of decontamination waste. Further decontamination, using an electro-kinetic decontamination method, was considered necessary for the residual soil waste, which consisted mainly of fine soil particles. (author)

  11. Preliminary study of the environmental radiological assessment for the Garigliano nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Esposito, A.M.; Sabbarese, C.; Sirignano, C.; Visciano, L.; D'Onofrio, A.D.; Lubritto, C.; Terrasi, F.

    2002-01-01

    In the last few years many nuclear installations in the world have been stopped either because they reached the end of production lifetime, or for operation problems or, like in Italy, for political decisions. This stop started the decommissioning procedure. It consists in the dismantling of the nuclear installation with appropriate controls and limitations of environmental and radiological impact which arises from these operations. The evaluation of risk and the actions needed for the population safeguard are generally inspired to the recommendations of the International Commission on Radiological Protection (ICRP), but each country faces the problem with different evaluation methodologies and calculations. That is due to different laws and environmental, social and economical context where nuclear installations are located. For this, the decommissioning operations must be separately evaluated for each nuclear installation. In this paper, we present the work carried out so far about the decommissioning of the Nuclear Power Plant of Garigliano (Caserta, Italy), which is managed by SoGIN (Societa di Gestione degli Impianti Nucleari). This Nuclear Power Plant began its activity in 1964 by using a boiling water reactor with a production of 160 MW electric power. In 1979 this nuclear installation was stopped for maintenance and operation has not been resumed until the referendum in 1986, after which all Italian nuclear plants were stopped. Now, the Nuclear Power Plant of Garigliano has the reactor isolated respect to the remaining part and all components and pipes have been drained and sealed. The underground tanks of radioactive wastes have been evacuated and decontaminated. The radioactive wastes have been completely conditioned with cementification in drums suitable to prevent outside release

  12. 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)

  13. 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.

  14. A database structure for radiological optimization analyses of decommissioning operations

    International Nuclear Information System (INIS)

    Zeevaert, T.; Van de Walle, B.

    1995-09-01

    The structure of a database for decommissioning experiences is described. Radiological optimization is a major radiation protection principle in practices and interventions, involving radiological protection factors, economic costs, social factors. An important lack of knowledge with respect to these factors exists in the domain of the decommissioning of nuclear power plants, due to the low number of decommissioning operations already performed. Moreover, decommissioning takes place only once for a installation. Tasks, techniques, and procedures are in most cases rather specific, limiting the use of past experiences in the radiological optimization analyses of new decommissioning operations. Therefore, it is important that relevant data or information be acquired from decommissioning experiences. These data have to be stored in a database in a way they can be used efficiently in ALARA analyses of future decommissioning activities

  15. Nuclear power plant decommissioning

    International Nuclear Information System (INIS)

    Yaziz Yunus

    1986-01-01

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

  16. Radiological considerations for decommissioning

    International Nuclear Information System (INIS)

    Adler, J.J.

    1993-01-01

    It has been said, by those uninitiated to decommissioning work, that radiological considerations required for decommissioning are the same as those for an operating facility. In reality, nothing could be further from the truth. The act of decommissioning can be likened to cutting off a tree limb while sitting on it. This paper discusses some of the unique radiological aspects that are associated with implementing a decommissioning health physics program. There are physical constraints that may cause major differences between a normal operational and a decommissioning health physics program. Throughout the decommissioning process, the installed equipment and services that were needed to support an operational program are constantly being removed or may already be disabled due to the age of the facility. Those affecting radiological protection programs typically would include radiation shielding, ventilation systems, breathing air supply for respiratory protection, and radiological monitoring systems

  17. The cost of decommissioning uranium mill tailings

    International Nuclear Information System (INIS)

    Lush, D.L.; Lendrum, C.; Hostovsky, C.; Eedy, W.; Ashbrook, A.

    1986-04-01

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

  18. Preparatory activities of the Fugen decommissioning

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  19. Decommissioning of NPP A-1

    International Nuclear Information System (INIS)

    Anon

    2009-01-01

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

  20. A study on source term assessment and waste disposal requirement of decontamination and decommissioning for the TRIGA research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Whang, Joo Ho; Lee, Kyung JIn; Lee, Jae Min; Choi, Gyu Seup; Shin, Byoung Sun [Kyunghee Univ., Seoul (Korea, Republic of)

    1999-08-15

    The objective and necessity of the project : TRIGA is the first nuclear facility that decide to decommission and decontamination in our nation. As we estimate the expected life of nuclear power generation at 30 or 40 years, the decommissioning business should be conducted around 2010, and the development of regulatory technique supporting it should be developed previously. From a view of decommissioning and decontamination, the research reactor is just small in scale but it include all decommissioning and decontamination conditions. So, the rules by regulatory authority with decommissioning will be a guide for nuclear power plant in the future. The basis of regulatory technique required when decommissioning the research reactor are the radiological safety security and the data for it. The source term is very important condition not only for security of worker but for evaluating how we dispose the waste is appropriate for conducting the middle store and the procedure after it when the final disposal is considered. The content and the scope in this report contain the procedure of conducting the assessment of the source term which is most important in understanding the general concept of the decommissioning procedure of the decommissioning and decontamination of TRIGA research reactor. That is, the sampling and measuring method is presented as how to measure the volume of the radioactivity of the nuclear facilities. And also, the criterion of classifying the waste occurred in other countries and the site release criteria which is the final step of decommissioning and decontamination presented through MARSSIM. Finally, the program to be applicable through comparing the methods of our nation and other countries ones is presented as plan for disposal of the waste in the decommissioning.

  1. NPP Krsko decommissioning concept

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  2. NPP Krsko decommissioning concept

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  3. Decommissioning of underground structures, systems and components

    International Nuclear Information System (INIS)

    2006-01-01

    A large number of operational and shut down nuclear installations have underground systems, structures and components such as pipes, tanks or vaults. This practice of incorporating such features into the design of nuclear facilities has been in use for an extended period of time during which decommissioning was not perceived as a serious issue and was rarely considered in plant design and construction. Underground features can present formidable decontamination and/or dismantling issues, and these are addressed in this report. Decommissioning issues include, among others, difficulty of access, the possible need for remotely operated technologies, leakage of the contents and the resulting contamination of foundations and soil, as well as issues such as problematic radiological characterization. Although to date there have been more than 40 IAEA publications on decommissioning, none of them has ever addressed this subject. Although cases of decommissioning of such facilities have been described in the technical literature, no systematic treatment of relevant decommissioning strategies and technologies is currently available. It was perhaps assumed that generic decontamination and dismantling approaches would also be adequate for these 'difficult' facilities. This may be only partly true due to a number of unique physical, layout and radiological characteristics. With growing experience in the decommissioning field, it is timely to address this subject in a systematic and comprehensive fashion. Practical guidance is given in this report on relevant decommissioning strategies and technologies for underground features of facilities. Also described are alternative design and construction approaches that could facilitate a smoother path forward through the decommissioning process. The objective of this report is to highlight important points in the decommissioning of underground systems, structures or components for policy makers, operators, waste managers and other

  4. 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

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

    International Nuclear Information System (INIS)

    1986-01-01

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

  6. Options for Steam Generator Decommissioning

    International Nuclear Information System (INIS)

    Krause, Gregor; Amcoff, Bjoern; Robinson, Joe

    2016-01-01

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

  7. Decommissioning and jobs

    International Nuclear Information System (INIS)

    John, B.S.

    1990-01-01

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

  8. Decommissioning of nuclear installations - regulations - financing - responsibility - insurance

    International Nuclear Information System (INIS)

    Hubert, E.H.; Andersson, C.; Deprimoz, J.; Mayoux, J.C.; Richard, M.; Sartorelli, C.; Nocera, F.

    1983-01-01

    This paper highlights three aspects of decommissioning of nuclear installations which relate, more or less directly, to legal options already applied or advocated. It reviews the regulatory conditions for decommissioning a nuclear installation and indicates legal provisions for financing decommissioning expenditures. It also describes the legal provisions to determine liabilities in case of nuclear damage and the assistance which insurers may provide to cover the consequences of such liabilities. (NEA) [fr

  9. Social effects of decommissioning Trawsfynydd Power Station

    International Nuclear Information System (INIS)

    Jones, H.

    2001-01-01

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

  10. Criticality issues in decommissioning activities at Sellafield

    International Nuclear Information System (INIS)

    Walls, S.J.; Harris, N.

    1996-01-01

    Since 1983 British Nuclear Fuels plc (BNFL) at Sellafield has been actively involved in the decommissioning of its old plant, with 7 projects being fully completed, 6 projects in the practical phase, and 12 currently in the planning design and strategy studies phase. These projects vary from the dismantling of a single large alpha-contaminated glove box to the decommissioning of an entire 11-story building housing redundant reprocessing facilities. This paper provides an overview of the facilities involved and highlights the criticality issues that have been addressed for safety to support the decommissioning activities

  11. 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

  12. Decommissioning of NPP A-1 Phase I, Jaslovske Bohunice. Documentation for application for permission to Phase II of decommissioning of NPP A-1. Schedule stage II of decommissioning of NPP A-1

    International Nuclear Information System (INIS)

    2007-04-01

    In this study documentation for application for permission to Phase II of decommissioning of NPP A-1 and the schedule stage II of decommissioning of NPP A-1 are presented. This study consists of ten appendixes.

  13. Nuclear decommissioning and society

    International Nuclear Information System (INIS)

    Pasqualetti, M.J.

    1990-01-01

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

  14. 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

  15. The SSI project on decommissioning of nuclear plants - a preliminary study; SSI:s projekt avseende avveckling av kaerntekniska anlaeggningar - en foerstudie

    Energy Technology Data Exchange (ETDEWEB)

    Efraimsson, Henrik; Ehdwall, H.; Godaas, T.; Hofvander, P.; Lindhe, J.C.; Lumpus, J.; Lund, I.; Malmqvist, L.; Welleman, E

    1999-01-01

    SSI will amend and complete regulations and stipulations for nuclear plants in order to take into account issues which arise in connection with decommissioning. The objective of a pilot study, performed during 1998, was to identify the questions at issue, what the authority should control and how SSI should proceed with the work. The recommendations and the result of the pilot study are presented in this report 29 refs.

  16. The decommissioning of Berkeley II

    International Nuclear Information System (INIS)

    Hannan, A.

    2002-01-01

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

  17. Data needs for decommissioning

    International Nuclear Information System (INIS)

    Lippincott, E.P.

    1993-01-01

    The paper describes the most important concerns that the author has encountered in the planning for decommissioning of the Ft. St. Vrain graphite reactor and in disposal of PWR components that undergo high irradiation. 3 tabs

  18. Decommissioning and Decontamination

    International Nuclear Information System (INIS)

    Massaut, V.

    2000-01-01

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

  19. Decommissioning decontamination- a comparative study of the compatibility of materials and magnetite powder dissolution kinetics in oxidative and reductive formulations without pre-treatment

    International Nuclear Information System (INIS)

    Keny, S.J.; Gokhale, A.S.; Venkateswaran, G.

    2000-01-01

    Decontaminating a system or a sub-system for decommissioning involves reducing the radioactivity levels to background values so that these materials may be disposed off as scrap. In this respect the use of oxidative formulation containing Ce 4+ and mineral acids like HNO 3 and H 2 SO 4 for stainless steels is reported. However, the nature of the container material to carry out component decontamination for decommissioning using these strong formulations needs evaluation. This paper brings out the compatibility studies of Stainless Steel and HDPE carried out in these oxidative formulations and compares them with those carried out in organic acid based reductive formulation like CEA. The results of magnetite powder dissolution kinetics in both oxidative and reductive types of formulations are also given. The studies show that HDPE is a more compatible container material than others with the oxidative formulations while dissolution rate constant is 10-50 times higher in reductive than in oxidative formulations. (author)

  20. The environmental risk between forgetting and managing the past: the case of the decommissioning of a uranium mine in France

    International Nuclear Information System (INIS)

    Bretesche, S.; Ponnet, M.

    2013-01-01

    This description of how a uranium mine (the Lucette mine) in western France was managed once it had been shut down draws attention to what was left behind. The article emphasizes how the mine became something common, ordinary, since the work conducted there during the nineties gradually erased evidence of the mining of uranium and was like a progressive return to a pristine state. But 3 events that happened after the decommissioning of the mine revealed to be strong memories of the past activity of the mine. First, some important land surface collapses happened which led to a zoning and a regular monitoring of the site. Secondly, red-colored water seepage appeared on the site and flowed into a nearby river. Analysis have shown the presence of radium, uranium and sodium chloride in the seeping. Thirdly, the tailings were being used by a construction enterprise to build and repair roads until the tailings were considered too radioactive to be used. The example of the Lucette mine provides a framework for broader questions about the effect of what is left behind in articulating past and present, and in the public construction of what is 'memorable' in environmental management

  1. Provision for decommissioning LWR power plants by the German utilities

    International Nuclear Information System (INIS)

    Essmann, J.; Brosche, D.; Thalmann, G.; Vollradt, J.; Watzel, G.V.P.

    1979-01-01

    In the Federal Republic of Germany the licensing procedure for nuclear power plants under the Atomic Energy Act requires provision of proof that the plants can be decommissioned and removed at the end of their operating time. In particular, the requirement is specified that the design of the plants must take account of decommissioning. The German utilities which operate nuclear power plants have long concerned themselves with aspects of decommissioning, and they have especially studied the question of whether there are aspects of decommissioning which could necessitate a change in the concept of the plant. For this purpose, an engineering company was given a contract to make a study with the objective of analysing the entire spectrum of decommissioning, ranging from determination of the decommissioning techniques and extending to the calculation of the masses of decommissioning wastes and the costs expected to be incurred during the decommissioning. Initial results of this study are now available and are described in this paper. These results already indicate that changes in the concept of the plant for decommissioning reasons are not necessary. Using these results of the study it is possible to indicate to the licensing authorities what range of techniques can be applied to decommission a nuclear power plant. The purpose of these studies is not to establish the decommissionability of every plant individually, but instead to point out the feasibility in general of decommissioning a large-scale plant. Finally, an estimate will be presented of the maximum costs which can be expected in a decommissioning operation and of what influence these costs will have on power production costs. (author)

  2. Casing study

    Energy Technology Data Exchange (ETDEWEB)

    Roche, P.

    2000-12-01

    An unorthodox method of casing drilling used by Tesco Corporation at a gas well in Wyoming to drill deeper using casings as drillpipe is discussed. The process involves either rotating the casing as drill string or using a downhole mud motor to rotate the bit. In this instance, the surface hole and the production hole were casing-drilled to a record 8,312 feet by rotating the casing. The 8 1/2-inch surface hole was drilled with 7-inch casing to 1,200 feet using a Tesco underreamer and a polycrystalline pilot bit; drilling and cementing was completed in 12 1/2 hours. The 6 1/4-inch production hole was drilled with 4 1/2-inch casing and the bottomhole assembly was retrieved after 191 hours rotating. This case was the first in which the entire well was casing-drilled from surface to TD. Penetration rate compared favorably with conventional methods: 12 1/2 hours for casing-drilling to 18.9 hours for conventional drilling, despite the fact that the casing-drilling technology is still in its infancy. It is suggested that casing-drilling has the potential to eliminate the need for the drillpipe entirely. If these expectations were to be realised, casing-drilling could be one of the most radical drilling changes in the history of the oil and gas industry. 1 photo.

  3. 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.

  4. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1982-12-01

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

  6. The study on the recycle condition for existence of the decommissioning waste in the nuclear power station

    International Nuclear Information System (INIS)

    Hironaga, Michihiko; Ozaki, Sachio; Hirai, Mitsuyuki; Sakamoto, Hiroyuki; Usui, Tatsuo; Simizu, Yasuo; Ogane, Daisuke

    2000-01-01

    To establish the technique of the recycle for concrete waste, this paper describes the recycle condition for existence of the decommissioning concrete waste in the nuclear power plant and considers the durability of cask yard concrete constructed at about twenty years ago. The authors examine the recycle system of concrete in the power plant. (author)

  7. 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

  8. 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)

  9. Decommissioning strategy selection

    International Nuclear Information System (INIS)

    Warnecke, E.

    2005-01-01

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

  10. WPDD workshop on: 'safe, efficient, and cost-effective decommissioning'. Workshop Conclusions/Final Stocktaking

    International Nuclear Information System (INIS)

    2005-01-01

    On September 6-10, 2004 a workshop on 'Safe, Efficient, and Cost-Effective Decommissioning' was held in Rome (Italy) to enable international experts on decommissioning to compare and evaluate respective approaches and experiences in decommissioning nuclear power and fuel cycle facilities and to formulate proposals for future international cooperation in the decommissioning arena. The main messages emerging from the workshop are: - Decommissioning is a mature industrial process and many projects have been safely completed with support of local communities. Technical and scientific issues are well-understood and practical experience and associated lessons are being documented to guide future activities. Emphasis is being placed on effective planning with active programmes of community involvement. - Individual countries need to further develop integrated decommissioning and waste management strategies to ensure that long-term solutions will be available for all wastes generated from decommissioning. National systems are evolving to meet national needs, against a framework provided by the international organisations, and these seem increasingly to favour early dismantling regardless of the availability of waste disposal routes. - Realistic and streamlined regulatory programmes are being developed with feed back from industry experience and are placing more responsibility and accountability on licensees. - Accurate decommissioning waste cost calculation methods is needed. Waste volumes may vary from project to project even for similar installations. There though appears to be a strong case for accumulating data and benchmarking costs for similar plants and processes. Further work and experience exchange on cost comparisons between different strategies (for example clearance and recycling/reuse of materials versus direct surface disposal) would be valuable. - International clearance criteria have been established, with individual countries free to adopt them

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1988-07-01

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

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

    International Nuclear Information System (INIS)

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

    1988-07-01

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

  13. CASE STUDY

    African Journals Online (AJOL)

    HIV infection has several oral manifestations, including oral candidiasis and oral hairy leucoplakia. Occasionally unusual presentations requiring rigorous investigations are seen, and in these cases the diagnosis sometimes remains a dilemma owing to limited investigation facilities.1-3 We present the case of a patient who.

  14. Decommissioning funding: ethics, implementation, uncertainties

    International Nuclear Information System (INIS)

    2006-01-01

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

  15. Scheduling for decommissioning projects

    International Nuclear Information System (INIS)

    Podmajersky, O.E.

    1987-01-01

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

  16. Site decommissioning management plan

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-10-01

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

  17. Site decommissioning management plan

    International Nuclear Information System (INIS)

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

    1993-10-01

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

  18. Shippingport Station Decommissioning Project

    International Nuclear Information System (INIS)

    McKernan, M.L.

    1989-01-01

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

  19. Decommissioning and environmental remediation: An overview

    International Nuclear Information System (INIS)

    Chatzis, Irena

    2016-01-01

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

  20. Decommissioning and environmental remediation: An overview

    International Nuclear Information System (INIS)

    Chatzis, Irena

    2016-01-01

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

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

    International Nuclear Information System (INIS)

    Batandjieva, B.; Warnecke, E.

    2008-01-01

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

  2. Decommissioning nuclear installations

    International Nuclear Information System (INIS)

    Dadoumont, J.

    2010-01-01

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

  3. Decommissioning of IFEC

    International Nuclear Information System (INIS)

    Ceccotti, G.; Sberze, L.

    1995-05-01

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

  4. Decommissioning and Decontamination

    Energy Technology Data Exchange (ETDEWEB)

    Massaut, V

    2000-07-01

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

  5. Platform decommissioning costs

    International Nuclear Information System (INIS)

    Rodger, David

    1998-01-01

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

  6. Decommissioning the Windscale AGR

    International Nuclear Information System (INIS)

    Boorman, T.

    1987-01-01

    The advanced gas cooled reactor at Windscale (WAGR) is being dismantled, that is, all fuel and coolant will be discharged and the plant dismantled completely with waste disposed of to a permanent repository. It is the first power-producing reactor to be dismantled in the UK. From a study of the main categories of materials to be disposed of it can be seen that the task of reactor decommissioning can be considered as the segregation of waste materials into appropriate categories and their disposal according to the regulations governing those categories. In the radioactive categories (only 10% of the total) only low and intermediate level wastes are involved. The high level waste was from the spent fuel which has already been removed. The remote controlled cutting, handling and packaging equipment is described. All equipment to be used has first to be tested after development. One building has been allocated as the waste packaging building and modified suitably. Dismantling is seen as a feasible process. (UK)

  7. Subsidies to the decommissioning of the first uranium mining and processing plant in Brazil - the case of the mineral industrial complex in Pocos de Caldas, Minas Gerais State

    International Nuclear Information System (INIS)

    Fernandes, Horst Richard Sebastian Monken

    1997-01-01

    The closure of an uranium mining and milling facility has the potential to cause risks (radiological and non-radiological) to the human health and to the environment as a whole; these risks may be incurred in the short as well in the long terms. The present work took the mining and milling facility of Pocos de Caldas, Minas Gerais - as a study case. The following aspects were covered by the work: analysis of the impacts associated to the facility operation; assessment of the geological processes involved in the mobilization of radioactive and non-radioactive pollutants from the main sources of these pollutants in the environment - the waste rock piles and the tailings dam; quantification of the resulting impacts associated to the emission of pollutants into the environment in future scenarios and establishment of remedial actions taking into account the risk reduction and the association costs. The main aspects arising from the study were: the wastes in the tailings dam are stratified in relation to metal and radionuclide concentrations, with the exception of 210 Pb and 226 Ra. The stratification is caused by the oxidation of the residual pyrite in the tailings, and is also related to metal and radionuclide concentrations in seepage water being higher in the upper zone and lower in the deeper zones. Sulfate anion was the only pollutant present in the seepage water to be detected in the groundwater below the tailings dam. Mathematical simulations taking into account the rest of the potential pollutants indicated the probability of groundwater contamination after 800 years. Direct liquid effluent releases into superficial waters are associated with a dose of about 8.0 mSv/y (conservative scenario) and less than 0.62 mSv/y (non-conservative scenario). If houses are built over the tailings, doses as high as 40 mSv/y and 8.0 mSv/y are to expected due to the Rn exhalation and external gamma respectively. Finally, covering the tailings dam with a clay layer 1.0 m thick

  8. The regulatory process for the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1990-01-01

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

  9. 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)

  10. CASE STUDY

    African Journals Online (AJOL)

    vascular disease necessitating bilateral amputations at the knee. The patient had no ... patients on long-term treatment and those on protease inhibitor (PI) regimens.1,2 We present a rare case of atypical lipodystrophy, presenting as multiple subcutaneous lipomas, in a patient who had been on a non-PI. ARV regimen for 6 ...

  11. Case study

    African Journals Online (AJOL)

    Point mutations in the human fibroblast growth factor receptor 3 (FGFR3) gene are well documented in inherited skeletal anomalies, such as achondroplasia and thanatophoric dysplasia, that are associated in most cases of dwarfism.10 In addition, an oncogenic role has been proposed for mutant FGFR.11 Recently,.

  12. Decommissioning of nuclear power plants: policies, strategies and costs

    International Nuclear Information System (INIS)

    Lund, I.

    2004-01-01

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

  13. Shippingport Station Decommissioning Project

    International Nuclear Information System (INIS)

    1989-01-01

    This Topical Report is a synopsis of the decontamination of plant components and structures at the Shippingport Station Decommissioning Project (SSDP). The information is provided as a part of the Technology Transfer Program to document the preparation activities in support of the shipment of radioactive wastes and the unconditional release of the site and structural materials. 1 ref., 16 figs., 4 tabs

  14. Particle-accelerator decommissioning

    International Nuclear Information System (INIS)

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

    1979-12-01

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

  15. Decommissioning, mothballing and revamping

    International Nuclear Information System (INIS)

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

    1997-01-01

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

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

    International Nuclear Information System (INIS)

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

    2002-01-01

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

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

    International Nuclear Information System (INIS)

    2006-01-01

    decommissioning techniques like dry abrasive blasting, cutting, removal of biological shielding and decontamination of concrete surfaces. Regarding the use of ventilated suits for workers in specific decommissioning activities, the information exchange in the CPD has helped push programmes to either improve the ventilated suits or to reduce the need for these systems. To address more general issues of common interest the CPD Technical Advisory Group established specific Task Groups. The Task Group on Decommissioning Costs developed, in co-operation with IAEA and EC, a standardised list of items for costing purposes, which allows for comparison of project costs. The Task Group on Recycling and Re-use put together case studies and provided information on the practicality and usefulness of the criteria under development for the release of slightly contaminated material from decommissioning, seen from the perspective of organisations engaged in actual decommissioning operations. Decontamination issues have been addressed by another Task Group that surveyed applied decommissioning techniques and characterised selected techniques in connection with decommissioning. Finally, the Task Group on Release Measurements studied collected relevant data from CPD projects and produced a report giving an overview on equipment and methods for and applications of release measurement. Looking back over the twenty years since the OECD-NEA established the CPD, the Programme has functioned as the main international forum for the exchange of technical and other information arising from nuclear decommissioning projects

  18. A study on implementation plan of decontamination and decommissioning R and D and evaluation of KAERI soil decontamination process

    International Nuclear Information System (INIS)

    Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. H.; Choi, W. K.; Kim, G. N.

    2001-08-01

    A. Decontamination Technology Development of Uranium Conversion Facility. Understanding of uranium conversion facility and related decontamination technologies, and analysis of current status of decontamination technologies. Establishment of the objective and research items of the middle and long term R and D project. Discussion of the erformance plan and about the methodology for connection with the project of environmental restoration of uranium conversion facility B. Treatment Technology Development of Uranium Sludge Analysis of the domestic and overseas research development status. Suggestion of treatment methodology of uranium slurry and cooperative R and D among industries, universities and research institute. Establishment of the objective and research items of the middle and long term R and D project. Discussion about the performance plan and about the methodology for connection with the project of environmental restoration of uranium conversion facility C. Decommissioning Technology Development Analysis of the domestic and overseas research development status and the overview of decommissioning technologies. Establishment of the objective and research items of the middle and long term R and D project. Discussion about the performance plan and about the methodology for connection with the project of TRIGA decommissioning D. Evaluation of KAERI Soil Decontamination Technology. Evaluation of soil decontamination process and the liquid decontamination waste treatment technology. Performance of soil decontamination test using solvent flushing test equipment for evaluation of residual radioactivity after decontami- nation and modeling of the results

  19. Case Study: Testing with Case Studies

    Science.gov (United States)

    Herreid, Clyde Freeman

    2015-01-01

    This column provides original articles on innovations in case study teaching, assessment of the method, as well as case studies with teaching notes. This month's issue discusses using case studies to test for knowledge or lessons learned.

  20. Decommissioning strategy for reactor AM, Russian Federation

    International Nuclear Information System (INIS)

    Suvorov, A.P.; Mukhamadeev, R.I.

    2002-01-01

    This paper presents the results of studies into the various aspects of decommissioning the oldest Russian research reactor, the AM reactor. Experimental and calculation results of a study to determine the inventory of long lived radioactive materials at the AM reactor are presented, along with a comparison to comparable data for other similar reactors. An analysis, by calculation, of the decay time needed to allow manual dismantling of the reactor vessel and stack, without remote operated equipment, defined it as 90 years. The possibility of burning most of the irradiated graphite to decrease the amount of long lived radioactive wastes was confirmed. The problems associated with the dismantling of the reactor components, contaminated with radioactive corrosion products, were analyzed. A decommissioning strategy for reactor AM was formed which is deferred dismantling, placing most of the radiological areas into long term safe enclosure. An overall decommissioning plan for reactor AM is given. (author)

  1. Innovative Nuclear Power Plant Building Arrangement Considering Decommissioning

    International Nuclear Information System (INIS)

    Choi, Won Jun; Roh, Myung Sub; Kim, Chang Lak

    2015-01-01

    There are mainly two decommissioning strategies for a nuclear power plant: immediate dismantling and deferred dismantling. In the immediate dismantling strategy, decommissioning is started immediately after the permanent shutdown of a nuclear power plant, giving a benefit of recovery and being able to reuse the decommissioned site quickly. The deferred dismantling strategy has 40-60 years safe storage period after permanent shutdown. It reduces radiation and radioactive decommissioning waste generation. A utility company planning to decommission its nuclear power plant should choose either immediate dismantling strategy for higher utilization of the site or deferred dismantling for lower radiation and less radioactive waste generation. Innovative nuclear power plant buildings arrangement (INBA) is proposed to solve a dilemma in choosing a decommissioning strategy by bringing out the advantage of immediate dismantling and deferred dismantling together. Recent studies about decommissioning cost show it to continually rise, and it is one of main causes to deteriorate economics of nuclear power. To recover it, we need a solution to improve the economics of a nuclear power plant over its entire life time including decommissioning

  2. Aspects of the decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Brosche, D.; Essmann, J.

    1976-01-01

    Some aspects of the decommissioning of nuclear power plants are discussed, and practical experience from the USA and Switzerland is studied in detail. With the increasing number of nuclear power plants in the FRG, discussions tend to center on the question whether these nuclear power plants can be decommissioned later on and how. In the safety criteria for nuclear power plants, published in 1974 by the Federal Ministry of the Interiar, criterion 2.10. makes the following statement: 'Nuclear power plants must be constructed in such a way that radiation protection specifications are met during decommissioning. There must be a concept for dismantling after final decommissioning which takes into account radiation protection regulations.' As a result of this criterion, a document of this type has been required in the licensing procedures for some nuclear power plant projects. The public utilities have been pondering about the decommissioning of nuclear power plants for some time. Now, criterion 2.10 has caused them to intensify their attempts and to prove that, from the present point of view, a nuclear power plant may be decommissioned at the end of its service life without changing their concept. The considerations made so far have also taken into account decommissioning experience in the USA and, on a European scale, decommissionings carried out and planned in Switzerland and the FRG. (orig./HP) [de

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

    International Nuclear Information System (INIS)

    Liu Yongkuo; Song Yi; Wu Xiaotian; Liu Zhen

    2014-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1988-07-01

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

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

    International Nuclear Information System (INIS)

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

    1988-07-01

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

  6. Decommissioning of NPP A1 - HWGCR type

    International Nuclear Information System (INIS)

    Burclova, J.

    1998-01-01

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

  7. Decommissioning and equipment replacement of nuclear power plants under uncertainty

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  8. Towards Greater Harmonisation of Decommissioning Cost Estimates

    International Nuclear Information System (INIS)

    O'Sullivan, Patrick; ); Laraia, Michele; ); LaGuardia, Thomas S.

    2010-01-01

    The NEA Decommissioning Cost Estimation Group (DCEG), in collaboration with the IAEA Waste Technology Section and the EC Directorate-General for Energy and Transport, has recently studied cost estimation practices in 12 countries - Belgium, Canada, France, Germany, Italy, Japan, the Netherlands, Slovakia, Spain, Sweden, the United Kingdom and the United States. Its findings are to be published in an OECD/NEA report entitled Cost Estimation for Decommissioning: An International Overview of Cost Elements, Estimation Practices and Reporting Requirements. This booklet highlights the findings contained in the full report. (authors)

  9. Decommissioning in western Europe; Kaernkraftsavveckling i Vaesteuropa

    Energy Technology Data Exchange (ETDEWEB)

    Lundqvist, K. [Castor arbetslivskonsulter AB, Stockholm (Sweden)

    1999-12-01

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

  10. The Impact of Severe Nuclear Accidents on National Decision for Nuclear Decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Young A; Hornibrook, Carol; Yim, Man Sung [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    Many researchers have tried to identify the impact of severe nuclear accidents on a country's or international nuclear energy policy [2-3]. However, there is little research on the influence of nuclear accidents and historical events on a country's decision to permanently shutdown an NPP versus international nuclear decommissioning trends. To demonstrate the correlation between a nuclear severe accident and the impact on world nuclear decommissioning, this research reviewed case studies of individual historical events, such as the St. Lucens, TMI, Chernobyl, Fukushima accidents and the series of events leading up to the collapse of the Soviet Union. For validation of the results of these case studies, a statistical analysis was conducted using the R code. This will be useful in explaining how international and national decommissioning strategies are affected by shutdown reasons, i.e. world historical events. The number of permanently shutdown NPPs was selected as an indicator because any relationship between the number of permanently In conclusion, nuclear severe accidents and historical events have an impact on the number of international NPPs that shutdown permanently and cancelled NPP construction. This directly impacts international nuclear decommissioning policy and nuclear energy policy trends. The number of permanently shutdown NPPs was selected as an indicator because any relationship between the number of permanently.

  11. 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

  12. INTERNATIONAL DECOMMISSIONING SYMPOSIUM 2000

    Energy Technology Data Exchange (ETDEWEB)

    M.A. Ebadian, Ph.D.

    2001-01-01

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

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

    International Nuclear Information System (INIS)

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

    2002-01-01

    regulations valid in the Republic of Kazakhstan and to IAEA recommendations. In a case of absence of the regulatory documentation BN-350 decommissioning works shall be performed in accordance with the standards existing for operational facilities after they have been approved by KAEC. (author)

  14. Management of safety and safety culture in regulatory work - The case of decommissioning of a Swedish plant

    International Nuclear Information System (INIS)

    Svensson, G.; Lekberg, A.

    2002-01-01

    The case of early closure of one of the units at a plant is one example of a situation where the regulator has to reflect on and choose its role in order to prevent an impairment of the safety culture at the plant. The strategy chosen by the Swedish Nuclear Power Inspectorate is presented and some conclusions are drawn. (author)

  15. Offshore decommissioning issues: Deductibility and transferability

    International Nuclear Information System (INIS)

    Parente, Virginia; Ferreira, Doneivan; Moutinho dos Santos, Edmilson; Luczynski, Estanislau

    2006-01-01

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

  16. Offshore decommissioning issues: deductibility and transferability

    Energy Technology Data Exchange (ETDEWEB)

    Parente, V.; Santos, M. dos [University of Sao Paulo (Brazil). Instituto de Electrotecnica; Ferreira, D. [State University of Campinas (Brazil). Dept. of Geology and Natural Resources; Luczynski, E. [Grupo de Estudos e Pesquisas Economico-Energeticas, Belem (Brazil)

    2006-10-15

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

  17. Decommissioning of nuclear submarines

    International Nuclear Information System (INIS)

    1989-01-01

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

  18. When a plant shuts down: The psychology of decommissioning

    International Nuclear Information System (INIS)

    Schulz, J.; Crawford, A.C.

    1993-01-01

    Within the next decade, 10 to 25 nuclear plants in the United States may be taken off line. Many will have reached the end of their 40-year life cycles, but others will be retired because the cost of operating them has begun to outweigh their economic benefit. Such was the case at Fort St. Vrain, the first decommissioning of a US commercial plant under new Nuclear Regulatory Commission (NRC) regulations. Two major problems associated with decommissioning plants have been obvious: (1) the technical challenges and costs of decommissioning, and (2) the cost of maintaining and finally decommissioning a plant after a safe storage (SAFSTOR) period of approximately 60 years. What has received little attention is the challenge that affects not only the people who make a plant work, but the quality of the solutions to these problems: how to maintain effective organizational performance during the process of downsizing and decommissioning and/or SAFSTOR. The quality of technical solutions for closing a plant, as well as how successfully the decommissioning process is held within or below budget, will depend largely on how effectively the nuclear organization functions as a social unit. Technical and people issues are bound together. The difficulty is how to operate a plant effectively when plant personnel have no sense of long-term security. As the nuclear power industry matures and the pace for closing operating plants accelerates, the time has come to prepare for the widespread decommissioning of plants. The industry would be well served by conducting a selective, industry-wide evaluation of plants to assess its overall readiness for the decommissioning process. A decommissioning is not likely to be trouble free, but with a healthy appreciation for the human side of the process, it will undoubtedly go more smoothly than if approached as a matter of dismantling a machine

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-01-01

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

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

    International Nuclear Information System (INIS)

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

    1996-01-01

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

  1. Radiological characterization and challenges at decommissioning sites

    International Nuclear Information System (INIS)

    Moore, Scott

    2002-01-01

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

  2. Conceptual data modeling on the KRR-1 and 2 decommissioning database

    International Nuclear Information System (INIS)

    Park, Hee Seoung; Park, Seung Kook; Lee, Kune Woo; Park, Jin Ho

    2002-01-01

    A study of the conceptual data modeling to realize the decommissioning database on the KRR-1 and 2 was carried out. In this study, the current state of the abroad decommissioning databased was investigated to make a reference of the database. A scope of the construction of decommissioning database has been set up based on user requirements. Then, a theory of the database construction was established and a scheme on the decommissioning information was classified. The facility information, work information, radioactive waste information, and radiological information dealing with the decommissioning database were extracted through interviews with an expert group and also decided upon the system configuration of the decommissioning database. A code which is composed of 17 bit was produced considering the construction, scheme and information. The results of the conceptual data modeling and the classification scheme will be used as basic data to create a prototype design of the decommissioning database

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

    International Nuclear Information System (INIS)

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

    2017-01-01

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

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

    International Nuclear Information System (INIS)

    1978-03-01

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

  5. 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)

  6. 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

  7. BNFL decommissioning strategy and techniques

    International Nuclear Information System (INIS)

    Taylor, D.

    2002-01-01

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

  8. Case Study: Writing a Journal Case Study

    Science.gov (United States)

    Prud'homme-Genereux, Annie

    2016-01-01

    This column provides original articles on innovations in case study teaching, assessment of the method, as well as case studies with teaching notes. This month's issue describes incorporating a journal article into the classroom by first converting it into a case study.

  9. Decommissioning Funding: Ethics, Implementation, Uncertainties

    International Nuclear Information System (INIS)

    2007-01-01

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

  10. Regulations and financing for decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Kumakura, Osamu

    1981-01-01

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

  11. Organization and management for decommissioning of large nuclear facilities

    International Nuclear Information System (INIS)

    2000-01-01

    organizational aspects of decommissioning and describes factors relevant to the planning and management of a decommissioning project. It identifies the general issues to be addressed and provides an overview of organizational activities necessary to manage a decommissioning project in a safe, timely and cost effective manner. There are a number of facilities that present special cases and include those which have undergone a major accident as well as uranium mines and mills and radioactive waste repositories. These facilities are not dealt with in this report. This report is structured as follows. Section 1 contains background information, objectives and scope of the document. In Section 2 considerations important for decommissioning management are discussed which could affect the organization. Section 3 deals with the management for active phases of decommissioning and provides a discussion on the organization of the decommissioning management team. Section 4 gives an overview of the decommissioning planning and approval process. Section 5 provides information on quality assurance issues relevant to decommissioning. Management of decommissioning wastes is briefly discussed in Section 6. Responsibilities and qualifications of the decommissioning management team are dealt with in Section 7. Conclusions and recommendations are given in Section 8. The report is supplemented with references, Appendix I giving details on recent experience on data management, a glossary, and national annexes, some of which indicate how the principles set out in the main report are to be utilized in different countries, and some of which are real examples of arrangements used in decommissioning projects. A list of drafting and reviewing bodies is also included

  12. Nuclear reactor decommissioning: an analysis of the regulatory environments

    International Nuclear Information System (INIS)

    Cantor, R.

    1984-04-01

    The purpose of this study is to highlight some of the current and likely regulations that will significantly affect the costs, technical alternatives and financing schemes for reactor decommissioning encountered by electric utilities and their customers. The paper includes a general review of the decommissioning literature, as well as information on specific regulations at the federal, state, and utility levels. Available estimated costs for the decommissioning of individual reactors are also presented. Finally, classification of the specific policies into common trends and practices among the various regulatory bodies is used to examine more general regulatory environments and their potential financial implications

  13. Shippingport Station Decommissioning Project Start of Physical Decommissioning

    International Nuclear Information System (INIS)

    Crimi, F. P.

    1987-01-01

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

  14. An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code

    International Nuclear Information System (INIS)

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

    2007-01-01

    The presented study is focused on an analysis of decommissioning costs for the Intermediate Storage Facility for Spent Fuel (FA) facility in Studsvik prepared by SVAFO and a proposal of the advanced decommissioning costing methodology application. Therefore, this applied study concentrates particularly in the following areas: 1. Analysis of FA facility cost estimates prepared by SVAFO including description of FA facility in Studsvik, summarised input data, applied cost estimates methodology and summarised results from SVAFO study. 2. Discussion of results of the SVAFO analysis, proposals for enhanced cost estimating methodology and upgraded structure of inputs/outputs for decommissioning study for FA facility. 3. Review of costing methodologies with the special emphasis on the advanced costing methodology and cost calculation code OMEGA. 4. Discussion on implementation of the advanced costing methodology for FA facility in Studsvik together with: - identification of areas of implementation; - analyses of local decommissioning infrastructure; - adaptation of the data for the calculation database; - inventory database; and - implementation of the style of work with the computer code OMEGA

  15. Environmental assessment after decommissioning at the North Sea- Froey oil production site: a field study with biomarkers in fish and invertebrates

    Energy Technology Data Exchange (ETDEWEB)

    Pinturier, Laurence; Beyer, Jonny; Moltu, Ulf; Plisson, Saune Stephan; Berland, Harald; Sundt, Rolf; Bjoernstad, Anne; Sanni, Steinar

    2006-03-15

    sediment environmental survey carried in 2003 indicating that sediment fauna disturbance were limited to the immediate vicinity of the field centre (less than 250 m). It was the first time that biological effects parameters were used to assess the environmental condition of an oil field after decommissioning. This survey demonstrates the feasibility of such study and its potential for assessing the condition of benthic community living in the water and at the surface sediment. (Author)

  16. Funding Decommissioning - UK Experience

    International Nuclear Information System (INIS)

    MacKerron, Gordon

    2006-01-01

    'Funding' started with CEGB and SSEB (state-owned electric utilities) in 1976 using the internal un-segregated fund route (i.e unfunded). This continued until privatisation of electricity industry (excluding nuclear) in 1990. Assets bought with the internal un-segregated fund were mostly transferred into non-nuclear private utilities. New state-owned Nuclear Electric (England and Wales) was given a 'Fossil Fuel Levy', a consumer charge of 10% on retail bills, amounting to c. BP 1 bn. annually. This allowed Nuclear Electric to trade legally (A reserve of BP 2.5 bn. was available from Government if company ran out of money). By 1996 the newer nuclear stations (AGRS plus PWR) were privatised as British Energy. British Energy started an external segregated fund, the Nuclear Decommissioning Fund, with a starting endowment of c. BP 225 m. - and BE made annual contributions of British Pound 16 m. into the Fund. Assumptions were that BE had 70 to accumulate cash and could get a 3.5% average annual real return. Older stations (Magnox) were left in private sector and went to BNFL in 1997. Magnox inherited the surplus cash in BE - mostly unspent Fossil Fuel Levy receipts - of c. BP 2.6 bn. Government gave an 'Undertaking' to pay BP 3.8 bn. (escalating at 4.5% real annually) for Magnox liabilities, should Magnox Electric run out of cash. BNFL inherited the BP 2.6 bn. and by 2000 had a 'Nuclear Liabilities Investment Portfolio' of c. BP 4 bn. This was a quasi-segregated internal fund for liabilities in general. [Note: overall UK nuclear liabilities in civilian sector were running at c. BP 48 bn. by now]. BE started profitable and paid BP 100 m. annually in dividends to private investors for several years. BE ran into severe financial problems after 2001 and Government organised restructuring aid, now approved by European Commission. Terms include: - BE now to contribute BP 20 m. a year into an expanded Nuclear Liabilities Fund; - A bond issue of BP 275 m. to go to Fund; - 65

  17. DECOST: computer routine for decommissioning cost and funding analysis

    International Nuclear Information System (INIS)

    Mingst, B.C.

    1979-12-01

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

  18. Evaluation of Nuclear Facility Decommissioning Projects program

    International Nuclear Information System (INIS)

    Baumann, B.L.

    1983-01-01

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

  19. Decommissioning of the Olkiluoto nuclear power plant

    International Nuclear Information System (INIS)

    Nykyri, M.; Peltonen, E.; Poellaenen, L.; Salonen, P.

    1987-12-01

    A conceptual plan is presented for the decommissioning of the Olkiluoto nuclear power plant. Deferred dismantlement after a storage period of 30 years is the main alternative. No detailed work plan for the demolition of structures is included. However, the world-wide development of demolition techniques for nuclear facilities has proven that the task can be performed using the existing technology. The decommissioning waste will be packed into concrete containers and wooden boxes. The total package volume is estimated at 8.000 and 30.000 m 3 depending on the treatment method. The higher figure stands for packing without any volume reduction. The activated reactor core components (fuel channels, control rods, neutron flux detectors) from the operational time of the Olkiluoto power plant are included in the decommissioning plan. The total activity of the contaminated and activated structures to be dismantled will be about 1x10 16 Bq after 30 years from the shut-down. The corresponding figure for the activated core components will be about 2x10 16 Bq. The radiation doses to personnel can be kept very low if the surface contamination of the large systems remains at a low level as it has done so far. The decommissioning waste is planned to be disposed of at the Olkiluoto site next to the reactor waste repository in the granitic bedrock at a depth of 50-100 m. The decommissioning waste repository will consist of two silos for the low-level waste and a hall for the activated metal waste. The barriers in the case of the metal waste hall will consist of the waste packages themselves, of 0.75 and 1 m thick concrete walls, of the 1 m thick bentonite/crushed rock backfill, and of the bedrock. The dismantlement will be finished by the year 2050, and the repository can be closed and sealed by 2055. The estimated decommissioning cost is FIM 808 million including the long-term storage and disposal

  20. 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)

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-10-15

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

  3. Approaches to estimating decommissioning costs

    International Nuclear Information System (INIS)

    Smith, R.I.

    1990-07-01

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

  4. Residual strength and stiffness of lumber from decommissioned chromated copper arsenate-treated southern pine utility poles

    Science.gov (United States)

    Cheng Piao; Leslie Groom

    2010-01-01

    The reusability of decommissioned treated wood is primarily dependent on the residual strength of the wood after service. Determining the residual strength can provide useful information for structural design and reuse of the decommissioned treated wood. This study evaluated the residual strength of decommissioned chromated copper arsenate–treated utility pole wood....

  5. Decontamination & decommissioning focus area

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

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

  6. Decommissioning. Success with preparation

    International Nuclear Information System (INIS)

    Klasen, Joerg; Schulz, Rolf; Wilhelm, Oliver

    2017-01-01

    The decommissioning of a nuclear power plant poses a significant challenge for the operating company. The business model is turned upside down and a working culture developed for power operation has to be adapted while necessary know- how for the upcoming tasks has to be built up. The trauma for the employees induced by the final plant shut-down has to be considered and respected. The change of working culture in the enterprise has to be managed and the organization has to be prepared for the future. Here the methods of Change-Management offer a systematic and effective approach. Confidence in the employee's competencies is one of the key success factors for the change into the future.

  7. Decommissioning Cost Assessment

    International Nuclear Information System (INIS)

    Labor, Bea

    2012-03-01

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

  8. Case Study Teaching

    Science.gov (United States)

    Herreid, Clyde Freeman

    2011-01-01

    This chapter describes the history of case study teaching, types of cases, and experimental data supporting their effectiveness. It also describes a model for comparing the efficacy of the various case study methods. (Contains 1 figure.)

  9. IAEA/CRP for decommissioning techniques for research reactors

    International Nuclear Information System (INIS)

    Oh, Won Zin; Won, H. J.; Kim, K. N.; Lee, K. W.; Jung, C. H.

    2001-03-01

    The following were studied through the project entitled 'IAEA/CRP for decommissioning techniques for research reactors 1. Decontamination technology development for TRIGA radioactive soil waste - Electrokinetic soil decontamination experimental results and its mathematical simulation 2. The 2nd IAEA/CRP for decommissioning techniques for research reactors - Meeting results and program 3. Hosting the 2001 IAEA/RCA D and D training course for research reactors and small nuclear facilities

  10. IAEA/CRP for decommissioning techniques for research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Won Zin; Won, H. J.; Kim, K. N.; Lee, K. W.; Jung, C. H

    2001-03-01

    The following were studied through the project entitled 'IAEA/CRP for decommissioning techniques for research reactors 1. Decontamination technology development for TRIGA radioactive soil waste - Electrokinetic soil decontamination experimental results and its mathematical simulation 2. The 2nd IAEA/CRP for decommissioning techniques for research reactors - Meeting results and program 3. Hosting the 2001 IAEA/RCA D and D training course for research reactors and small nuclear facilities.

  11. Construction times and the decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Erramuspe, H.J.

    1988-01-01

    The construction and the decommissioning periods of nuclear power plants (NPP), are studied, due to their importance in the generation costs. With reference to the construction periods of these plants, a review is made of the situation and technical improvements made in different countries, with the purpose of shortening them. In regard to the decommissioning of NPP, the present and future situations are reviewed in connection with different stages of decommissioning and their related problems, as the residual radioactivity of different components, and the size of the final wastes to be disposed of. The possibilities of plant life extensions are also revised in connection with these problems. Finally, the expected decommissioning costs are analyzed. (Author) [es

  12. Scheme of database structure on decommissioning of the research reactor

    International Nuclear Information System (INIS)

    Park, H. S.; Park, S. K.; Kim, H. R.; Lee, D. K.; Jung, K. J.

    2001-01-01

    ISP (Information Strategy Planning), which is the first step of the whole database development, has been studied to manage effectively information and data related to the decommissioning activities of the Korea Research Reactor 1 and 2 (KRR-1 and 2). Since Korea has not acquired the technology of the decommissioning database management system, some record management system (RMS) of large nuclear facilities of national experience such as in the U.S.A, Japan, Belgium, and Russian were reviewed. In order to construct the database structure of the whole decommissioning activities such as the working information, radioactive waste treatment, and radiological surveying and analysis has been extracted from the whole dismantling process. These information and data will be used as the basic data to analyzed the matrix to find the entity relationship diagram and will contribute to the establishment of a business system design and the development of a decommissioning database system as well

  13. FIR 1 TRIGA activity inventories for decommissioning planning

    International Nuclear Information System (INIS)

    Raety, Antti; Kotiluoto, Petri

    2016-01-01

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

  14. DECOM experience with decommissioning costing

    International Nuclear Information System (INIS)

    Daniska, V.; Zachar, M.

    2015-01-01

    The OMEGA code has been used in numerous Slovak and international decommissioning planning and costing projects and in IAEA R and D projects and is continuously updated and upgraded. The next goal for the DECOM costing activities is to develop an universal and user-friendly ISDC costing tool accessible via internet - eOMEGA taking over the advantages of the long-term experience of DECOM and being in line with up-to date trends in decommissioning costing. DECOM members participate in international expert groups for further improvement of costing methodologies, such as the uncertainties, cost practices and cost peer reviews in decommissioning costing. DECOM members participate also in IAEA projects, expert missions and training courses related to decommissioning costing and planning. (authors)

  15. On Decommissioning Costs of the Ranstad Site

    International Nuclear Information System (INIS)

    Varley, Geoff

    2010-08-01

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

  16. 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)

  17. Project management case studies

    CERN Document Server

    Kerzner, Harold R

    2013-01-01

    A new edition of the most popular book of project management case studies, expanded to include more than 100 cases plus a ""super case"" on the Iridium Project Case studies are an important part of project management education and training. This Fourth Edition of Harold Kerzner''s Project Management Case Studies features a number of new cases covering value measurement in project management. Also included is the well-received ""super case,"" which covers all aspects of project management and may be used as a capstone for a course. This new edition:Contains 100-plus case studies drawn from re

  18. General principles of nuclear safety management related to research reactor decommissioning

    International Nuclear Information System (INIS)

    Banciu, Ortenzia; Vladescu, Gabriela

    2003-01-01

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

  19. Decommissioning challenges - an industrial reality

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  20. An outsider's view of decommissioning

    International Nuclear Information System (INIS)

    Wilkie, T.

    1996-01-01

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

  1. 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.)

  2. Preliminary decommissioning plan of the reactor IPEN-MB01

    International Nuclear Information System (INIS)

    Vivas, Ary de Souza

    2014-01-01

    Around the world, many nuclear plants were built and need to be turned off at a certain time because they are close to their recommended time of use is approximately 50 years. So the IAEA (International Atomic Energy Agency), seeks to guide and recommend a set of guidelines for the conduct of activities of nuclear facilities, with special attention to countries that do not have a framework regulatory Legal that sustain the activities of decommissioning. Brazil, so far, does not have a specific standard to guide the steps of the guidelines regarding decommissioning research reactors. However, in March 2011 a study committee was formed with the main task facing the issues of decommissioning of nuclear installations in Brazil, culminating in Resolution 133 of November 8, 2012, a standard project that treat about the Decommissioning of nucleoelectric plants. O Instituto de Pesquisas Energeticas e Nucleares (IPEN) has two research reactors one being the reactor IPEN/MB-01. The purpose of this master dissertation is to develop a preliminary plan for decommissioning this research reactor, considering the technical documentation of the facility (RAS-Safety Analysis Report), the existing standards of CNEN (National Nuclear Energy Commission), as well as IAEA recommendations. In terms of procedures for decommissioning research reactors, this work was based on what is most modern in experiences, strategies and lessons learned performed and documented in IAEA publications covering techniques and technologies for decommissioning. Considering these technical knowledge and due to the peculiarities of the facility, was selected to immediate dismantling strategy, which corresponds to the start of decommissioning activities once the installation is switched off, dividing it into work sectors. As a resource for monitoring and project management of reactor decommissioning and maintenance of records, we developed a database using Microsoft Access 2007, which contain all the items and

  3. Feasibibility study - cases

    DEFF Research Database (Denmark)

    Lund, Henrik; Hvelplund, Frede Kloster; Sukkumnoed, Decharut

    2004-01-01

    The chapter presents two case studies to show the tools of feasibiliy studies within the context of technological innovation.......The chapter presents two case studies to show the tools of feasibiliy studies within the context of technological innovation....

  4. 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)

  5. Alternatives evaluation and decommissioning study on shielded transfer tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    DeVore, J.R.; Hinton, R.R.

    1994-08-01

    The shielded transfer tanks (STTs) are five obsolete cylindrical shipping casks which were used to transport high specific activity radioactive solutions by rail during the 1960s and early 1970s. The STTs are currently stored at the Oak Ridge National Laboratory under a shed roof. This report is an evaluation to determine the preferred alternative for the final disposition of the five STTs. The decommissioning alternatives assessed include: (1) the no action alternative to leave the STTs in their present location with continued surveillance and maintenance; (2) solidification of contents within the tanks and holding the STTs in long term retrievable storage; (3) sale of one or more of the used STTs to private industry for use at their treatment facility with the remaining STTs processed as in Alternative 4; and (4) removal of tank contents for de-watering/retrievable storage, limited decontamination to meet acceptance criteria, smelting the STTs to recycle the metal through the DOE contaminated scrap metal program, and returning the shielding lead to the ORNL lead recovery program because the smelting contractor cannot reprocess the lead. To completely evaluate the alternatives for the disposition of the STTs, the contents of the tanks must be characterized. Shielding and handling requirements, risk considerations, and waste acceptance criteria all require that the radioactive inventory and free liquids residual in the STTs be known. Because characterization of the STT contents in the field was not input into a computer model to predict the probable inventory and amount of free liquid. The four alternatives considered were subjected to a numerical scoring procedure. Alternative 4, smelting the STTs to recycle the metal after removal/de-watering of the tank contents, had the highest score and is, therefore, recommended as the preferred alternative. However, if a buyer for one or more STT could be found, it is recommended that Alternative 3 be reconsidered.

  6. Alternatives evaluation and decommissioning study on shielded transfer tanks at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    DeVore, J.R.; Hinton, R.R.

    1994-08-01

    The shielded transfer tanks (STTs) are five obsolete cylindrical shipping casks which were used to transport high specific activity radioactive solutions by rail during the 1960s and early 1970s. The STTs are currently stored at the Oak Ridge National Laboratory under a shed roof. This report is an evaluation to determine the preferred alternative for the final disposition of the five STTs. The decommissioning alternatives assessed include: (1) the no action alternative to leave the STTs in their present location with continued surveillance and maintenance; (2) solidification of contents within the tanks and holding the STTs in long term retrievable storage; (3) sale of one or more of the used STTs to private industry for use at their treatment facility with the remaining STTs processed as in Alternative 4; and (4) removal of tank contents for de-watering/retrievable storage, limited decontamination to meet acceptance criteria, smelting the STTs to recycle the metal through the DOE contaminated scrap metal program, and returning the shielding lead to the ORNL lead recovery program because the smelting contractor cannot reprocess the lead. To completely evaluate the alternatives for the disposition of the STTs, the contents of the tanks must be characterized. Shielding and handling requirements, risk considerations, and waste acceptance criteria all require that the radioactive inventory and free liquids residual in the STTs be known. Because characterization of the STT contents in the field was not input into a computer model to predict the probable inventory and amount of free liquid. The four alternatives considered were subjected to a numerical scoring procedure. Alternative 4, smelting the STTs to recycle the metal after removal/de-watering of the tank contents, had the highest score and is, therefore, recommended as the preferred alternative. However, if a buyer for one or more STT could be found, it is recommended that Alternative 3 be reconsidered

  7. Money Related Decommissioning and Funding Decision Making

    International Nuclear Information System (INIS)

    Goodman, Lynne S.

    2008-01-01

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

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

    International Nuclear Information System (INIS)

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

    2002-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    MC Bierschbach; DR Haffner; KJ Schneider; SM Short

    2002-12-01

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

  10. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-06-01

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

  12. Radiological characterisation and decommissioning in Denmark

    International Nuclear Information System (INIS)

    Nellemenn, Thomas

    2012-01-01

    alpha emitters will be incorporated into the inventory calculations. Due to the variable nature of the systems being decommissioned, the sampling procedures are based on ad hoc principles. The number of samples needed is determined by the conventional characterisation of the systems. For systems where conventional knowledge is limited, more samples are generally needed earlier in the decommissioning process. Otherwise sampling can take place prior to the packing of the containers for the interim storage facility. In this case less sampling is needed as few representative samples for each material from each system in the container are sufficient. (author)

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

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  14. Decommissioning of the Salaspils Research Reactor

    Directory of Open Access Journals (Sweden)

    Abramenkovs Andris

    2011-01-01

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

  15. Governments' role in decommissioning nuclear power facilities

    International Nuclear Information System (INIS)

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

    2005-01-01

    Many nuclear power plants will reach the end of their operating lives over the next 20 years; some may be life-extended, others may not. This development will precipitate enhanced industrial and regulatory activities in the area of decommissioning. We are also witnessing in many countries a significant shift in the role of government itself: new pressures on governments, such as enhanced attention on environmental impact/mitigation and strategies to implement market-oriented approaches in a variety of sectors, including the energy sector are driving the public policy agenda. The paper will examine the range of policy issues, drawing from recent NEA studies on decommissioning policies and the recent NEA study on Government and Nuclear Energy and, strategies and costs, and other current trends and developments in the nuclear industry and in the nuclear policy fields. The paper will reflect on issues to be addressed during the conference and draw conclusions on the appropriate role of government in this area. Decommissioning policy is very specific and focused: it is not a high level policy/political issue in most instances and rarely gets the same attention as the issue surrounding the future of nuclear energy itself and public concerns regarding safety, waste and economics. One reason why decommissioning does not get the same attention as for example disposal of spent nuclear fuel might be the fact that technology is available for decommissioning, while technology for disposal of spent nuclear fuel is under development. High profile or not, it will remain an important issue for governments and industry alike particularly because of the cost and long lead times involved. In some instances, governments are the owners of the facilities to be decommissioned. In addition, decommissioning factors into issues surrounding the economics of nuclear energy and the sustainability of the nuclear option. Based on results of the Tarragona Seminar (Spain, September 2-4, 2003) and

  16. Decommissioning of small medical, industrial and research facilities

    International Nuclear Information System (INIS)

    2003-01-01

    of complexity, safety risk and radiological inventory. The key objective of this report is to provide information, experience and assistance on what is appropriate and sufficient for policy makers, regulators and operators of small facilities. It is intended to promote timely and cost effective decommissioning and waste management at the end of the life of a facility so as to render such a facility harmless. No statements in the report are intended to be prescriptive. There is significant documentation on the decommissioning of large nuclear facilities but the more modest requirements of small facilities have received little attention. If users of small facilities only have available to them published information for large, complex facilities, then there may be a tendency to overreact and engage in elaborate or unnecessary studies and activities. They also may shy away from important issues and do too little, either because they are not trained or advised properly or they do not have a decommissioning plan or adequate human and financial resources. They also are often unaware of the requirements, both legal and technical, of decommissioning and waste management. Some decades ago, when the first large power and demonstration reactors started to be shut down, there were many unknowns and uncertainties on how to proceed. There is now a significant experience database on common problems, which has been shared by the international nuclear power industry. This is not necessarily the case for small facilities, however, and this report is intended to encourage the interchange of information and experience. It is intended in this report to cover all aspects of decommissioning small facilities in which radioactive material and radiation sources are produced, received, used and/or stored. Power reactors, prototype and demonstration reactors, larger research reactors, fuel processing and reprocessing plants and their associated large nuclear chemical facilities, and all forms of

  17. Case study research.

    Science.gov (United States)

    Taylor, Ruth; Thomas-Gregory, Annette

    2015-06-10

    This article describes case study research for nursing and healthcare practice. Case study research offers the researcher an approach by which a phenomenon can be investigated from multiple perspectives within a bounded context, allowing the researcher to provide a 'thick' description of the phenomenon. Although case study research is a flexible approach for the investigation of complex nursing and healthcare issues, it has methodological challenges, often associated with the multiple methods used in individual studies. These are explored through examples of case study research carried out in practice and education settings. An overview of what constitutes 'good' case study research is proposed.

  18. Decommissioning Plan for European Spallation Source

    Science.gov (United States)

    Ene, Daniela

    2017-09-01

    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..

  19. 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..

  20. The Italian decommissioning industry

    International Nuclear Information System (INIS)

    Adinolfi, R.

    2005-01-01

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

  1. Global solutions through simulation for better decommissioning

    International Nuclear Information System (INIS)

    Scoto Di Suoccio, Ines; Testard, Vincent

    2016-01-01

    be tried, analyzed and compared on all output parameters in a total accordance with the ALARA/ALARP approach. Then, contingencies can be prevented by testing an infinite number of situations whatever the uncertainties are, and this enables to determine the best scenario strategy for each set of data. Simulations also allow people to test not only access issues into some environment but also radiological access. By testing different dosimetric configurations or hot spot location, simulation allows you to test them and so reduce risks. For a specific environment, when many scenarios have been developed and tested, sensitivity studies are really important to choose the optimal decommissioning strategy. Sensitivity studies can be done with simulation tools by comparing results of scenarios directly into the software. This comparison helps to choose the optimal scenario according to which output data is considered as key determinant. Simulation offers a very good return on investment in the sense that many scenarios are quick to do, they can be copied and the user can change one input data to observe instantaneously the impacts of this change on results. Doing different simulations permit to quantify risks, reduce hazard and therefore reduce costs. Finally, simulation tools enable to collect output data of decommissioning projects during realization, comparing them in real time to the studies assessments. This improve the feedback acquisition, very important in the decommissioning field in which we do not have a lot of experience. Current experiences of studies using DEMplus on different kind of projects show several benefits either on the entry data consolidation, the scenario optimization and the risks studies. The ALARA/ALARP approach is fully developed by simulating a large set of strategies, using a cost-benefits analysis on many criteria. A unique software that deals with all types of entry data in order to compute results is clearly a powerful tool as a decision

  2. Redevelopment of nuclear facilities after decommissioning

    International Nuclear Information System (INIS)

    2006-01-01

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

  3. Platform decommissioning. Environmental challenges and practical solutions

    International Nuclear Information System (INIS)

    Kvalvik, Inge

    1998-01-01

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

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

    International Nuclear Information System (INIS)

    Postelnicu, C.

    1998-01-01

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

  5. Business operations and decommissioning strategy for imperial college London research reactor 'Consort' - A financial risk management approach

    International Nuclear Information System (INIS)

    Franklin, S.J.; Gardner, D.; Mumford, J.; Lea, R.; Knight, J.

    2005-01-01

    Imperial College London (IC) operates commercially a 100 kW research reactor, and as site licensee is responsible for funding both operations and eventual decommissioning. With long lead times ahead urgent decisions on the future business options have had to be made in 2004/5 including choices on whether to move to early decommissioning, recognising the high costs entailed, or to pursue continuing operations involving life extension measures such as refuelling. To develop a coherent overall approach strategy a financial risk driven programme was initiated to help define a robust transparent business and termination case for the reactor. This study was carried out in collaboration with a UK firm of financial risk experts, PURE Risk Management Ltd (PURE), working within a dedicated IC London reactor project team. This work evaluated immediate closure options due to financial constraints or life limiting failures, and options for continuing operation extending to 2028. Decommissioning and clean up were reviewed. Bespoke financial models created single value cost outputs and ranges of probabilistic net present values (NPV) for decommissioning costs and financial provisions to meet those costs at various levels of risk acceptance and regulatory compliance. (author)

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  7. Decommissioning: guiding principles and best practices for involving local stakeholders

    International Nuclear Information System (INIS)

    Keyes, D.

    2005-01-01

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

  8. 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)

  9. Main elements in favour of an immediate decommissioning

    International Nuclear Information System (INIS)

    Cregut, A.

    1985-01-01

    After a presentation of the elements to be taken into consideration when undertaking a comparative study of the diverse possible solutions for the future of a shut down nuclear reactor, this outlines the advantages of simultaneously decommissioning and conducting final shut down operations. It is clarified that in a real situation the benefits of demonstration and judgement on the technical solutions adopted are arguments in favour of this approach but that this is only true for the first case. The advantages of this approach in a systematic manner are then developed. In conclusion, the advantages associated with this approach are theoretically beyond question and it should not be rejected a priori. However, if it is a question of taken a decision on the future of a nuclear installation, it is necessary to quantify and compare the advantages and disadvantages of other approaches in order to make the best choice

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

    International Nuclear Information System (INIS)

    John, T.; Thierfeldt, S.

    1993-01-01

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

  11. Civil engineering design for decommissioning of nuclear installations

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  12. Guidelines for producing commercial nuclear power plant decommissioning cost estimates

    International Nuclear Information System (INIS)

    LaGuardia, T.S.

    1986-01-01

    Decommissioning cost estimates have been made for specific commercial nuclear power plants and for reference plants, utilities, the US Nuclear Regulatory Commission (NRC), the US Dept. of Energy, consultants, and others. The different technical, site-specific, and economic assumptions used have made it difficult to interpret these cost estimates during the process of developing rates and rate structures for the recovery of decommissioning expenses. The estimates made to date have not anticipated that form the bases for the variations in cost estimates. The perceived incompatibility among the economic and technical assumptions in these estimates has added to the difficulties regulators have in deciding rates and rate structures for the recovery of decommissioning costs by nuclear utilities. To assist the industry, the National Environmental Studies Project (NESP) of the Atomic Industrial Forum sponsored a study to produce guidelines for developing decommissioning cost estimates. This guideline document was developed by TLG Engineering for NESP under the direction of a task force made up of some of the top experts in the decommissioning field from nuclear utilities, manufacturers, architect/engineering firms, accounting firms, the NRC, the US Federal Energy Regulatory Commission, state regulatory bodies, the National Association of Regulatory Utility Commissioners, and the electric industry research community

  13. On-site disposal as a decommissioning strategy

    International Nuclear Information System (INIS)

    1999-11-01

    On-site disposal is not a novel decommissioning strategy in the history of the nuclear industry. Several projects based on this strategy have been implemented. Moreover, a number of studies and proposals have explored variations within the strategy, ranging from in situ disposal of entire facilities or portions thereof to disposal within the site boundary of major components such as the reactor pressure vessel or steam generators. Regardless of these initiatives, and despite a significant potential for dose, radioactive waste and cost reduction, on-site disposal has often been disregarded as a viable decommissioning strategy, generally as the result of environmental and other public concerns. Little attention has been given to on-site disposal in previous IAEA publications in the field of decommissioning. The objective of this report is to establish an awareness of technical factors that may or may not favour the adoption of on-site disposal as a decommissioning strategy. In addition, this report presents an overview of relevant national experiences, studies and proposals. The expected end result is to show that, subject to safety and environmental protection assessment, on-site disposal can be a viable decommissioning option and should be taken into consideration in decision making

  14. Decommissioning of nuclear installations at CIEMAT

    International Nuclear Information System (INIS)

    Villoria, A.; Romero, N.; Garcia, J.L.; Sama, J.

    2002-01-01

    This report presents the work carried out by CIEMAT in the frame of decommissioning the research reactor JEN-1. Studies for evaluating different metal cutting techniques, including plasma-arc cutting, contact-arc cutting and mechanical saw cutting led to assessing the performance, advantages and associated problems for each technique. The main metallic material studied was aluminium, but some experiments with stainless steel were also conducted. Melting was also studied as a decontamination technique and as a way to reduce volume and facilitate the management of radioactive waste. (author)

  15. 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.

  16. Decommissioning program-sharing experience

    International Nuclear Information System (INIS)

    Sheil, A.E.; Hall, M.

    1996-01-01

    When the current reprocessing programs are complete, British Nuclear Fuels plc's (BNFL's) Sellafield site will have ∼120 radioactive plants, all of which will require decommissioning. A formal program was initiated in the early 1980s and has expanded to reach the current level of 18 plants undergoing decommissioning and a plan of work stretching over several decades. In addition to these chemical plants, BNFL's decommissioning program extends to other sites in the United Kingdom, including fuel and enrichment facilities. The BNFL has been managing a huge program, including the technical solutions adopted to meet safety and cost targets, the interaction with regulatory bodies, and the management of the site work. Particular attention has been paid to the methods used to minimize dose exposure to operators and the minimization and management of waste. Novel approaches have been used for the integration of plant and remote equipment control systems to reduce demands on operators and improve productivity. Other aspects of the extensive development program have been carried out in support of decommissioning

  17. 76 FR 35511 - Decommissioning Planning

    Science.gov (United States)

    2011-06-17

    ... licensees to conduct their operations to minimize the introduction of residual radioactivity into the site... additional information on the costs of decommissioning and spent fuel management. DATES: The final rule is... Agencywide Documents Access and Management System (ADAMS): Publicly available documents created or received...

  18. Decommissioning: A critical component of the design for uranium tailings management facilities

    International Nuclear Information System (INIS)

    Clifton, A.W.; Barsi, R.G.; Misfeldt, G.A.

    2002-01-01

    Uranium was discovered in the Beaverlodge area of northern Saskatchewan in 1934 with the first major mill beginning operation in 1953. Little attention was paid to tailings quality or tailings management practices. With the onset of the modern uranium operations beginning in the late 1970's, it was repeatedly evident, that the public had significant concerns, particularly with respect to tailings management, that must be addressed if the developments were to be allowed to proceed. Primary considerations related to environmental protection, public safety and an assurance of the ongoing sustainable development of the region. Integrating the decommissioning of a mine/mill site into development planning from the very outset has proven to be a critical component that has contributed to the ongoing success of the Saskatchewan uranium operations. This paper will provide a case study of the evolution of the uranium tailings management technology utilized in Saskatchewan. It documents the evolution of tailings management processes and the characteristics of tailings produced by successive mines in northern Saskatchewan. It also discusses the evolution of technologies applied to management of uranium mill tailings and demonstrates how progressively increasing levels of environmental protection have been achieved during the last 47 years of uranium mill operation. The paper also shows that the planned and progressive decommissioning of an operational site is the key to: Minimizing environmental impacts; Satisfying public and regulatory concerns; Minimizing operational and decommissioning costs; Minimizing corporate liability; and Shifting public resistance to public support. (author)

  19. Decommissioning: A critical component of the design for uranium tailings management facilities

    International Nuclear Information System (INIS)

    Clifton, W.A.; Barsi, R.G.; Misfeldt, G.A.

    2000-01-01

    Uranium was discovered in the Beaverlodge area of northern Saskatchewan in 1934 with the first major mill beginning operation in 1953. Little attention was paid to tailings quality or tailings management practices. With the onset of the modem uranium operations beginning in the late 1970's, it was repeatedly evident, that the public had significant concerns, particularly with respect to tailings management, that must be addressed if the developments were to be allowed to proceed. Primary considerations related to environmental protection, public safety and an assurance of the ongoing sustainable development of the region. Integrating the decommissioning of a mine/mill site into development planning from the very outset has proven to be a critical component that has contributed to the ongoing success of the Saskatchewan uranium operations. This paper will provide a case study of the evolution of the uranium tailings management technology utilized in Saskatchewan. It documents the evolution of tailings management processes and the characteristics of tailings produced by successive mines in northern Saskatchewan. It also discusses the evolution of technologies applied to management of uranium mill tailings and demonstrates how progressively increasing levels of environmental protection have been achieved during the last 47 years of uranium mill operation. The paper also shows that the planned and progressive decommissioning of an operational site is the key to: Minimizing environmental impacts; Satisfying public and regulatory concerns; Minimizing operational and decommissioning costs; Minimizing corporate liability; and Shifting public resistance to public support. (author)

  20. Environmental Problems Associated With Decommissioning The Chernobyl Nuclear Power Plant Cooling Pond

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E. B.; Jannik, G. T.; Marra, J. C.; Oskolkov, B. Ya.; Bondarkov, M. D.; Gaschak, S. P.; Maksymenko, A. M.; Maksymenko, V. M.; Martynenko, V. I.

    2009-11-09

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  1. ENVIRONMENTAL PROBLEMS ASSOCIATED WITH DECOMMISSIONING THE CHERNOBYL NUCLEAR POWER PLANT COOLING POND

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E.

    2009-09-30

    Decommissioning of nuclear power plants and other nuclear fuel cycle facilities has been an imperative issue lately. There exist significant experience and generally accepted recommendations on remediation of lands with residual radioactive contamination; however, there are hardly any such recommendations on remediation of cooling ponds that, in most cases, are fairly large water reservoirs. The literature only describes remediation of minor reservoirs containing radioactive silt (a complete closure followed by preservation) or small water reservoirs resulting in reestablishing natural water flows. Problems associated with remediation of river reservoirs resulting in flooding of vast agricultural areas also have been described. In addition, the severity of environmental and economic problems related to the remedial activities is shown to exceed any potential benefits of these activities. One of the large, highly contaminated water reservoirs that require either remediation or closure is Karachay Lake near the MAYAK Production Association in the Chelyabinsk Region of Russia where liquid radioactive waste had been deep well injected for a long period of time. Backfilling of Karachay Lake is currently in progress. It should be noted that secondary environmental problems associated with its closure are considered to be of less importance since sustaining Karachay Lake would have presented a much higher radiological risk. Another well-known highly contaminated water reservoir is the Chernobyl Nuclear Power Plant (ChNPP) Cooling Pond, decommissioning of which is planned for the near future. This study summarizes the environmental problems associated with the ChNPP Cooling Pond decommissioning.

  2. Cluff Lake decommissioning project - planning and current status

    International Nuclear Information System (INIS)

    Acott, G.; Pollock, R.

    2006-01-01

    The Cluff Lake Project, owned and operated by AREVA/COGEMA Resources Inc., is a uranium mining and milling facility in northern Saskatchewan, which commenced operation in 1980. The decommissioning plan for the Cluff Lake Project received regulatory approval in 2004, following a Comprehensive Study under the Canadian Environmental Assessment Act. The plan involves soil covers for an above-ground tailings area and a waste rock pile, completing the backfilling of an open pit with waste rock and flooding of two other open pits and of two underground mines. A large mill and associated infrastructure will also be demolished and disposed within the backfilled pit. Several alternative methods were considered for the decommissioning of each of the major areas. Success of the decommissioning will be judged by comparison to objectives established through the environmental assessment process. A comprehensive follow up program has been developed to monitor the key aspects, to demonstrate that the planning assumptions were appropriate and to ensure decommissioning will perform as designed. This paper summarizes the planning for decommissioning, and describes the current status and subsequent monitoring program. (author)

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

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  4. AECL's waste management and decommissioning program

    International Nuclear Information System (INIS)

    Kupferschmidt, W.C.H.

    2006-01-01

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

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

    International Nuclear Information System (INIS)

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

    1986-06-01

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

  6. Nuclear decommissioning in Italy

    International Nuclear Information System (INIS)

    Tripputi, I.

    2005-01-01

    in the oil market, both in terms of barrel cost and in terms of security of supplies, and the severe black-outs that have plagued also Italy (the major one in September 2003 lasting in some areas for about 24 hours), have started a widespread discussion about energy alternatives and strategic energy plans. In this frame an increasing number of politicians and scientists are calling for a reconsideration of nuclear energy as a viable option also for Italy in a new energy mix. It is clear that public acceptance of nuclear energy is strictly connected not only to the demonstration of high safety standards of future plants, but also to the solution of radioactive waste disposal and of plant decommissioning. This is the link that could make the SOGIN mission even more strategic for the country

  7. a case study

    African Journals Online (AJOL)

    Assessment of (dis)ability in a prospec tive commercial diver with a hand injury – a case study. A case study in disability. W A J (JAck) MeintJes, MB ChB, DOM, FCPHM (SA) Occ Med, MMed (Occ Med). Specialist, Occupational Medicine, Division of Community Health, Department of Interdisciplinary Health Sciences, ...

  8. Ecological and political issues surrounding decommissioning of offshore oil facilities in the Southern California Bight

    Science.gov (United States)

    Schroeder, Donna M.; Love, Milton S.

    2004-01-01

    To aid legislators, resource managers, and the general public, this paper summarizes and clarifies some of the issues and options that the federal government and the state of California face in decommissioning offshore oil and gas production platforms, particularly as these relate to platform ecology. Both local marine ecology and political climate play a role in decommissioning offshore oil production platforms. Compared to the relatively supportive political climate in the Gulf of Mexico for “rigs-to-reefs” programs, conflicting social values among stakeholders in Southern California increases the need for understanding ecological impacts of various decommissioning alternatives (which range from total removal to allowing some or all of platform structure to remain in the ocean). Additional scientific needs in the decommissioning process include further assessment of platform habitat quality, estimation of regional impacts of decommissioning alternatives to marine populations, and determination of biological effects of any residual contaminants. The principal management need is a ranking of environmental priorities (e.g. species-of-interest and marine habitats). Because considerable numbers of economically important species reside near oil platforms, National Oceanic and Atmospheric Administration Fisheries should consider the consequences of decommissioning alternatives in their overall management plans. Management strategies could include designating reefed platforms as marine protected areas. The overarching conclusion from both ecological and political perspectives is that decommissioning decisions should be made on a case-by-case basis.

  9. 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)

  10. Nuclear Decommissioning R and D: a successful history that goes on. Evolution of R and D for nuclear decommissioning

    International Nuclear Information System (INIS)

    Laraia, Michele; )

    2017-01-01

    reports on the decommissioning of certain installations and individual systems, structures and components, and related techniques, have been published in the 1990's and 2000's. These reports include, among others, the achievements of several Coordinated Research Projects in a row where 10-15 organizations active in nuclear decommissioning shared a common theme and periodically reported on their progress at Research Coordination Meetings. While the writer does not expect significant breakthroughs in decommissioning technology in the foreseeable future, a new impetus to R and D has been given by the Fukushima accident. Due to the complexity of Fukushima circumstances, this is one case where the available technology may not be equal to the challenges that lie ahead and significant technological progress is needed to move on. It is possible that innovative technologies stemming from Fukushima will boost a staggering change in decommissioning. For example, a fleet of robots could carry out decommissioning instead of humans: but we are not yet there. (author)

  11. Recovery of decommissioning and spent fuel charges

    International Nuclear Information System (INIS)

    Bermanis, G.

    1982-01-01

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

  12. Allocation of Decommissioning and Waste Liabilities

    International Nuclear Information System (INIS)

    Varley, Geoff

    2011-11-01

    The work demonstrates that there are a number of methods available for cost allocation, the pros and cons of which are examined. The study investigates potential proportional and incremental methods in some depth. A recommendation in principle to use the latter methodology is given. It is concluded that a 'fair assumption' is that the potential allocation of costs for 'the RMA Leaching Hall' probably is small, in relation to the total costs, and estimated to be not more than about 175 kSEK, plus any costs associated with decommissioning/ disposal of a number of small pieces of equipment added by the current operator

  13. 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.

  14. Feedback from the decommissioning of two accelerators

    International Nuclear Information System (INIS)

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

    2003-01-01

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

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

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  16. Roadmap and performance carried out during Ciemat site decommissioning

    International Nuclear Information System (INIS)

    Quinones, Javier; Diaz Diaz, Jose Luis

    2005-01-01

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

  17. Atomics International's recent decommissioning experience

    International Nuclear Information System (INIS)

    Kittinger, W.D.

    1981-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Konzek, G.J.

    1983-07-01

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

  19. Six Heliport Case Studies

    National Research Council Canada - National Science Library

    Peisen, Deborah

    1997-01-01

    .... This report evaluates the dynamics of heliport development and operation in order to achieve greater success rate in the future through the case study investigation of six heliports that have both succeeded and failed...

  20. HYDROGEOLOGIC CASE STUDIES

    Science.gov (United States)

    Hydrogeology is the foundation of subsurface site characterization for evaluations of monitored natural attenuation (MNA). Three case studies are presented. Examples of the potentially detrimental effects of drilling additives on ground-water samples from monitoring wells are d...

  1. An Applied Study on the Decontamination and Decommissioning of Hot Cell Facilities in the United States and Comparison with the Studsvik Facility for Solid and Liquid Waste

    Energy Technology Data Exchange (ETDEWEB)

    Varley, Geoff; Rusch, Chris [NAC International, Atlanta, GA (United States)

    2006-07-15

    This report presents the plans, processes and results of the decontamination and decommissioning of the Hot Cell Facility in Building 23 at the General Atomics Torrey Pines Mesa Facility (HCF) and compares the program and cost of decommissioning HCF with the Swedish cost estimate for decontamination and decommissioning of the HM hot cell and wastes treatment facility at Studsvik in Sweden. The HCF had three main hot cells and was licensed to: Receive, handle and ship radioactive materials; Remotely handle, examine and store irradiated fuel materials; Extract tritium (engineering scale); Support new reactor production development; Develop, fabricate and inspect UO{sub 2} - BeO fuel materials. The HM facility in Studsvik was constructed to handle and package medium-active solid and liquid wastes, prior to disposal. Central to the facility is a conventional hot cell including three work stations, serviced by master slave manipulators. Other parts of the facility include holding tanks for liquid wastes and slurries, a centrifuge room, as well as an encapsulation station where drummed wastes can be encapsulated in cement, offices, laboratories and workshops and so on, as well as building and cell ventilation systems. Decontamination and decommissioning of the HCF took place during 1993 through 2001. The objective was to obtain regulatory release of the site so that it could be used on an unrestricted basis. Based on data from extensive hazardous and radiological materials characterization, GA evaluated four decommissioning options and selected dismantling as the only option that would satisfy the decommissioning objective. The decontamination and decommissioning scope included the following actions. 1. Remove the legacy waste that consisted of radioactive wastes stored at the HCF consisting of 21,434 kg of irradiated fuel material (IFM) that was owned by the US DoE and store the waste in temporary storage set up at the GA site. 2. Actual Decontamination and

  2. An Applied Study on the Decontamination and Decommissioning of Hot Cell Facilities in the United States and Comparison with the Studsvik Facility for Solid and Liquid Waste

    International Nuclear Information System (INIS)

    Varley, Geoff; Rusch, Chris

    2006-07-01

    This report presents the plans, processes and results of the decontamination and decommissioning of the Hot Cell Facility in Building 23 at the General Atomics Torrey Pines Mesa Facility (HCF) and compares the program and cost of decommissioning HCF with the Swedish cost estimate for decontamination and decommissioning of the HM hot cell and wastes treatment facility at Studsvik in Sweden. The HCF had three main hot cells and was licensed to: Receive, handle and ship radioactive materials; Remotely handle, examine and store irradiated fuel materials; Extract tritium (engineering scale); Support new reactor production development; Develop, fabricate and inspect UO 2 - BeO fuel materials. The HM facility in Studsvik was constructed to handle and package medium-active solid and liquid wastes, prior to disposal. Central to the facility is a conventional hot cell including three work stations, serviced by master slave manipulators. Other parts of the facility include holding tanks for liquid wastes and slurries, a centrifuge room, as well as an encapsulation station where drummed wastes can be encapsulated in cement, offices, laboratories and workshops and so on, as well as building and cell ventilation systems. Decontamination and decommissioning of the HCF took place during 1993 through 2001. The objective was to obtain regulatory release of the site so that it could be used on an unrestricted basis. Based on data from extensive hazardous and radiological materials characterization, GA evaluated four decommissioning options and selected dismantling as the only option that would satisfy the decommissioning objective. The decontamination and decommissioning scope included the following actions. 1. Remove the legacy waste that consisted of radioactive wastes stored at the HCF consisting of 21,434 kg of irradiated fuel material (IFM) that was owned by the US DoE and store the waste in temporary storage set up at the GA site. 2. Actual Decontamination and Dismantlement

  3. Objectivist case study research

    DEFF Research Database (Denmark)

    Ridder, Hanne Mette Ochsner; Fachner, Jörg

    2016-01-01

    be achieved through the use of objectivist case study research. The strength of the case study design is that it allows for uncovering or suggesting causal relationships in real-life settings through an intensive and rich collection of data. According to Hilliard (1993), the opposite applies for extensive...... designs, in which a small amount of data is gathered on a large number of subjects. With the richness of data, the intensive design is ―the primary pragmatic reason for engaging in single-case or small N research‖ (p. 374) and for working from an idiographic rather than a nomothetic perspective....

  4. Fort St. Vrain defueling ampersand decommissioning considerations

    International Nuclear Information System (INIS)

    Warembourg, D.

    1994-01-01

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

  5. 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

  6. Nuclear power plants life extension and decommissioning its economic aspects

    International Nuclear Information System (INIS)

    Watanabe, Yoshiaki

    1994-06-01

    In USA where the development of nuclear power was started early, the life of nuclear power plants expires successively around the turn of century, and the serious hindrance to electric power supply is feared. Therefore, the research for extending 40 year approved period of operation is in progress. By the extension of life of nuclear power plants, huge cost reduction is estimated as compared with the construction of new plants. However, due to the rise of the cost for the life extension, there were the cases of forced decommissioning. In this book, the present state of the life extension of nuclear power stations, the economical assessment and analysis of the life extension by DOE, the economical assessment by MIDAS method of Electric Power Research Institute, the economical assessment by cost-benefit method of Northern States Power Co., the assessment of the long term operation possibility of nuclear power stations, the economical assessment system for the life extension in Japan, the present state of the decommissioning of nuclear power stations and that in USA, Canada and Europe, the assessment of the decommissioning cost by OECD/NEA, and the decommissioning cost for thermal power stations are described. (K.I.)

  7. EPRI Guidance for Transition from Operations to Decommissioning

    International Nuclear Information System (INIS)

    McGrath, Richard; Reid, Richard; Snyder, Michael

    2016-01-01

    A wide range of key activities are necessary after permanent shutdown of a nuclear power plant before active dismantlement of the plant can begin. This period is typically referred to as the transition period. In some cases these activities are prescribed by regulation and in others they may be more practically driven or even optional. In either case, planning for transition activities should optimally take place prior to final shutdown. Additionally, execution of some transition period activities, such as filing required regulatory submittals, may be performed prior to plant shut down. In addition to general transition period activities such as defueling, management of operational wastes, fulfilling regulatory requirements and changes to plant technical specifications, there are a number of optional activities that may have a long-range impact on future decommissioning activities. This includes activities such as the timing of staff reductions and performance of chemical decontamination. EPRI is nearing completion of a project to develop guidance for transitioning a nuclear power plant to decommissioning. This project includes the following elements: - A review of required and recommended transition period activities. For countries where a clear regulatory framework exists, this includes country-specific requirements; - A review of pending regulatory activities in the US and other countries where there is currently no clear regulatory framework for transitioning to decommissioning; - A summary of activities that have been performed during the transition period for past and current decommissioning sites, as well as current sites that are actively planning decommissioning activities; and - Guidance for development of a transition plan for changing from an operational to decommissioning status. Informed planning of the transition period activities will provide immediate benefits in reducing costs and minimizing the duration of the transition period, as well as longer

  8. Experience of TTR-1 decommissioning

    International Nuclear Information System (INIS)

    Kato, Hiroaki; Nobuoka, Yoshishige; Yoshimura, Yukio; Homma, Hitoshi; Nakai, Masaru

    2005-01-01

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

  9. Planning For Armenian NPP Decommissioning

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  10. Decommissioning program of JRR-2

    International Nuclear Information System (INIS)

    Kishimoto, Katsumi; Banba, Masao; Arigane, Kenji

    1999-01-01

    Japan Research Reactor No.2(JRR-2), heavy water moderated and cooled tank type research reactor with maximum thermal power of 10 MW, was used over 36 years, and was permanently shut down in December, 1996. Afterward, dismantling report was submitted to the STA, and dismantling was begun in 1997. Decommissioning of JRR-2 is planned in 11 years from 1997 to 2007, and the program is divided into 4 phases. Phase 1 had already been ended, phase 2 is being executed at present. Reactor body will be removed in phase 4 by one piece removal or caisson techniques. On reactor building, it is planned to use effectively as a hot experimental facilities after decommissioning ends. How to treat heavy water and primary cooling system contaminated by tritium becomes an important problem to lead decommissioning to success because JRR-2 is heavy water reactor. On heavy water, transportation to foreign country is planned in phase 2. On primary cooling system, it is planned to remove and dispose the majority in phase 3, and tritium decontamination with technique established by the proof test is planned before them. As a preparation for them, various investigation and examination are being advanced at present. (author)

  11. Decommissioning of naval nuclear ships

    International Nuclear Information System (INIS)

    Oelgaard, P.L.

    1993-10-01

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

  12. IAEA Perspectives on Preparation for Decommissioning

    International Nuclear Information System (INIS)

    Michal, Vladimir; Ljubenov, Vladan

    2016-01-01

    There are about 160 power reactors in decommissioning phase worldwide. In addition, more than 400 other nuclear facilities, such as research reactors or nuclear fuel cycle facilities, have been shutdown for decommissioning, have been undergoing active decommissioning or have already been fully dismantled. Planned and systematic preparation for decommissioning is very important for further effective implementation of dismantling activities. While some preparatory activities for decommissioning start early in the facility life-cycle, the main preparatory activities are implemented towards the end of the operational period and during the transition period from operation to decommissioning. These may include a wide range of technical actions, such as physical and radiological characterization, pre-decommissioning decontamination, management of spent fuel and operational waste, establishment of new waste management facilities and modification of safety systems needed to support decommissioning. In parallel, some non-technical tasks are to be completed, e.g. preparation of the final decommissioning plan and its supporting documents, licensing activities, organizational changes, training of personnel for decommissioning, etc. Preparatory activities may be organized in various ways depending on considered decommissioning strategies and physical and radiological status of the nuclear facility after its routine operation is over. The IAEA published numerous safety and technical reports providing guidance, recommendations, experiences, good practices and lessons learned, fully or to some extent covering the preparatory phase for decommissioning. Many training courses, workshops, seminars etc. were organized to support sharing of good practices among specialists and organizations involved. This paper provides an overview of relevant activities and perspectives of the IAEA in this area. The paper also draws some general conclusions and identifies lessons learned on the basis of

  13. Shippingport station decommissioning project technology transfer program

    International Nuclear Information System (INIS)

    McKernan, M.L.

    1988-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-06-01

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

  15. The waste management implications of decommissioning

    International Nuclear Information System (INIS)

    Passant, F.H.

    1988-01-01

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

  16. 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.)

  17. 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

  18. 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)

  19. 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.

  20. Financing the Decommissioning of Nuclear Facilities

    International Nuclear Information System (INIS)

    2016-01-01

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

  1. Status of the Fort St. Vrain decommissioning

    International Nuclear Information System (INIS)

    Fisher, M.J.

    1990-01-01

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

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

    International Nuclear Information System (INIS)

    Hrasnova, E.

    2015-01-01

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

  3. Nuclear facility decommissioning and site remedial actions

    Energy Technology Data Exchange (ETDEWEB)

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

    1989-09-01

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

  4. Nuclear facility decommissioning and site remedial actions

    International Nuclear Information System (INIS)

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

    1989-09-01

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

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

    International Nuclear Information System (INIS)

    Graham, H.B.

    1975-01-01

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

  6. Development of decontamination, decommissioning and environmental restoration technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Jik; Kwon, H. S.; Kim, G. N. and others

    1999-03-01

    Through the project of 'Development of decontamination, decommissioning and environmental restoration technology', the followings were studied. 1. Development of decontamination and repair technology for nuclear fuel cycle facilities 2. Development of dismantling technology 3. Development of environmental restoration technology. (author)

  7. 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

  8. Costing for decommissioning: Continuing NEA engagement

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  9. Decommissioning and environmental restoration of nuclear facilities in China

    International Nuclear Information System (INIS)

    Pan Ziqiang

    2000-01-01

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

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

    International Nuclear Information System (INIS)

    Brendebach, Boris; Rehs, Bernd

    2016-01-01

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

  11. SCA12 case study

    Indian Academy of Sciences (India)

    Home; Journals; Journal of Genetics; Volume 88; Issue 1. Utilizing linkage disequilibrium information from Indian Genome Variation Database for mapping mutations: SCA12 case study. Samira Bahl Ikhlak Ahmed The Indian Genome Variation Consortium Mitali Mukerji. Research Article Volume 88 Issue 1 April 2009 pp 55- ...

  12. Retrospective Case Studies

    Energy Technology Data Exchange (ETDEWEB)

    Wright, Phillip M.

    1977-09-01

    This project, Retrospective Case Studies (RCS) operates directly under DGE's Resource Exploration and Assessment program. The overall objectives of this project are: (1) to improve the general and specific level of understanding of geothermal systems, and (2) to improve tools and technology for geothermal exploration and assessment.

  13. Chaitanya case study

    International Development Research Centre (IDRC) Digital Library (Canada)

    lremy

    sustainability, that began at our inception 12 years ago. This case study ... women. Over the years, we moved towards building a model of sustainable institutions .... poverty alleviation. However, over the last decade, a number of organizations had gained expertise in organizing and managing SHGs and as a result, very few.

  14. Brief Assessment of Krsko NPP Decommissioning Costs

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  15. Decommissioning alternatives, process and work activities

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

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

  16. Criteria development methodology for DOE decommissioning operations

    International Nuclear Information System (INIS)

    Denham, D.H.

    1981-01-01

    The Radiological Guide for DOE Decommissioning Operations provides a uniform basis for assessing hazard inventories, making risk analyses, performing site characterizations, and certifying decommissioning operations. While initially addressed to radioactive contaminants, in all likelihood it will be extended to include other contaminants

  17. Impact of decommissioning on electricity generation costs

    International Nuclear Information System (INIS)

    Crijns, M.J.; Vira, J.

    1987-01-01

    By definition, the levelized decommissioning cost is the weighted average cost that should be charged for each unit of electricity produced through the lifetime of the facility, to precisely cover all the costs that the decommissioning of the facility give rise to. Although the mode in which decommissioning costs enter the electricity rates depends on utility and regulatory practices, the levelization offers a consistent means for estimating the cost impact of decommissioning. An international group of experts, called together under the auspices of the OECD Nuclear Energy Agency (NEA), has prepared estimates on levelized decommissioning costs for nuclear power plants, starting from the cost information provided by some of its Member countries. Three basic strategies for decommissioning were considered, including immediate dismantling and two strategies for deferred dismantling. The Working Group calculated the levelized decommissioning costs for several assumptions on discount rates and reactor lifetimes. The calculations showed that decommissioning has a very small impact on electricity generation cost of a large nuclear power plant. The uncertainties in cost estimates, applicable interest rates or facility operating lifetimes are large but still unlikely to significantly affect this conclusion

  18. 76 FR 3837 - Nuclear Decommissioning Funds; Correction

    Science.gov (United States)

    2011-01-21

    ... Internal Revenue Service 26 CFR Part 1 RIN 1545-BF08 Nuclear Decommissioning Funds; Correction AGENCY... decommissioning nuclear power plants. DATES: This correction is effective on January 21, 2011, and is applicable... interest in a nuclear power plant. * * * * * (e) * * * (3) * * * Example 2. * * * Pursuant to paragraph (e...

  19. 75 FR 80697 - Nuclear Decommissioning Funds

    Science.gov (United States)

    2010-12-23

    ... Nuclear Decommissioning Funds AGENCY: Internal Revenue Service (IRS), Treasury. ACTION: Final regulations... decommissioning nuclear power plants. These final regulations affect taxpayers that own an interest in a nuclear... Energy Policy Act of 2005 (the Energy Policy Act), Public Law 109-58 (119 Stat. 594). Written, electronic...

  20. Survey of decontamination and decommissioning techniques

    International Nuclear Information System (INIS)

    Kusler, L.E.

    1977-01-01

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

  1. Facilitation of decommissioning light water reactors

    International Nuclear Information System (INIS)

    Moore, E.B. Jr.

    1979-12-01

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

  2. Decommissioning of nuclear facilities 1977 edition

    International Nuclear Information System (INIS)

    1978-01-01

    The need for development or refinement of some technical aspects of decommissioning and for international acceptance of definition of ''stages'' is reviewed. The bases for a code of practice and a guide to the code for decommissioning land based reactors are outlined

  3. EPRI nuclear power plant decommissioning technology program

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  4. AREVA decommissioning strategy and programme

    International Nuclear Information System (INIS)

    Gay, A.

    2008-01-01

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

  5. MRI case studies

    International Nuclear Information System (INIS)

    Huggett, S.; Barber, J.

    1989-01-01

    Three case studies are presented to show the value of magnetic resonance imaging used in conjunction with other imaging techniques. In each case MRI proved a vital diagnostic tool and superior to CT in showing firstly the haematoma in a patient with aphasia and right-sided weakness, secondly the size of the disc herniation in a patient with severe leg and ankle pains and thirdly the existence of a metastatic lesion in a patient with a previous history of breast cancer. 11 figs

  6. A Review of the Decommissioning Costs of the Ranstad Site

    International Nuclear Information System (INIS)

    Varley, Geoff

    2009-08-01

    The main objective of this study has been to review the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. Analyses of some detailed comparative empirical information have been used in the context of preliminary 'bench-marking' studies. The estimated costs for decommissioning of the old uranium mine in Ranstad have been compared with actual costs from other relevant decommissioning projects. In this way it has been possible to give a preliminary qualitative statement about the accuracy of the Ranstad cost estimate. The study gives the following lessons learned: 1. The available information suggests that the overall estimated cost may be reasonable, but there are still some points of weakness that need to be elaborated more in detail before a full statement about the adequacy of the forecast cost will be possible. 2. Especially the costs associated with declassification activities warrant further analysis in order to determine there level of accuracy. 3. There exists the possibility that the estimate might be low concerning decontamination, dismantling and planning and institutional work. 4. Further work and analysis is needed in order to develop a more transparent cost estimate in which the stakeholders can have the highest confidence. 5. A new bidding procedure for the conventional demolition may result in lower estimated costs. Hence, it would be beneficial to obtain an updated estimate based on at least more than one quotation. 6. The method of addressing uncertainty and risk should be more connected to the logistics of specific decommissioning activities, in order to be more transparent and clearer in details. There is a need for further study to develop a better estimate. In the short run follow-up work needs to be undertaken to provide a better understanding of what are the major contributors to risk and cost drivers in the planned decommissioning process at the Ranstad industrial area

  7. Technology and costs for decommissioning of Swedish nuclear power plants

    International Nuclear Information System (INIS)

    1994-06-01

    The decommissioning study for the Swedish nuclear power plants has been carried out during 1992 to 1994 and the work has been led by a steering group consisting of people from the nuclear utilities and SKB. The study has been focused on two reference plants, Oskarshamn 3 and Ringhals 2. Oskarshamn 3 is a boiling water reactor (BWR) and Ringhals 2 is a pressurized water reactor (PWR). Subsequently, the result from these plants have been translated to the other Swedish plants. The study gives an account of the procedures, costs, waste quantities and occupational doses associated with decommissioning of the Swedish nuclear power plants. Dismantling is assumed to start immediately after removal of the spent fuel. No attempts at optimization, in terms of technology or costs, have been made. The nuclear power plant site is restored after decommissioning so that it can be released for use without restriction for other industrial activities. The study shows that a reactor can be dismantled in about five years, with an average labour force of about 150 persons. The maximum labour force required for Oskarshamn 3 has been estimated to about 300 persons. This peak load occurred the first years but is reduced to about 50 persons during the demolishing of the buildings. The cost of decommissioning Oskarshamn 3 has been estimated to be about MSEK 940 in January 1994 prices. The decommissioning of Ringhals 2 has been estimated to be MSEK 640. The costs for the other Swedish nuclear power plants lie in the range MSEK 590-960. 17 refs, 21 figs, 15 tabs

  8. Impact of metals recycling on a Swedish BWR decommissioning project

    International Nuclear Information System (INIS)

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

    2014-01-01

    Decommissioning of nuclear power plants generates large volumes of radioactive or potentially contaminated metals. By proper management of the waste streams significant amounts can be free released and recycled either directly or after decontamination and melting. A significant part of the required work should be performed early in the process to make the project run smoothly without costly surprises and delays. A large portion of the clearance activities can be performed on-site. This on-site work should focus on the so called low-risk for contamination material. Other material can be decontaminated and released on site if schedule and the available facility areas so allow. It should be noted that the on-site decontamination and clearance activities can be a significant bottle neck for a decommissioning project. The availability of and access to a specialized metals recycling facility is an asset for a decommissioning project. This paper will describe the forecasted positive impact of a well-structured metals characterisation, categorisation and clearance process for a BWR plant decommissioning project. The paper is based on recent studies, performed projects and recent in-house development. (authors)

  9. 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)

  10. Generation of database for future decommissioning of CIRUS

    International Nuclear Information System (INIS)

    Sankar, S.; Rao, D.V.H.; Vakharwala, K.J.; Jauhri, G.H.; Maheshchandra

    2002-01-01

    Safe decommissioning of a research reactor in a planned manner is inevitable at the end of its useful life even after refurbishment and life extension. This involves advance planning, adopting state of the art technology, development of required new technology, a well thought out plan for nuclear waste management and necessary research and development in the areas of decontamination to recycle and reuse most of the metallic materials. The 40 MW thermal research reactor CIRUS at Bhabha Atomic Research Centre, Mumbai, India is being refurbished after 37 years of operation. Several part-decommissioning activities were carried out during the refurbishment. This was also the right time and state of the reactor to generate the necessary data and document the experience gained and lessons learned to aid in the planning for future decommissioning of CIRUS. This report presents the details of radiological mapping and characterization studies carried out, experience gained in cleaning/decontamination, dismantlement works carried out for repairs/replacement of structures, systems and components and development of new devices/techniques. It is expected that this work would considerably aid in working out an appropriate strategy of decommissioning of CIRUS when needed in the future. (author)

  11. Decontamination and decommissioning: a bibliography

    International Nuclear Information System (INIS)

    McLaren, L.H.

    1982-11-01

    This bibliography contain information on decontamination and decommissioning included in the Department of Energy's Data Base from January 1981 through October 1982. The abstracts are grouped by subject category. Within each category the arrangement is by report number for reports, followed by nonreports in reverse chronological order. These citations are to research reports journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: corporate author, personal author, subject, contract number, and report umber. (468 abstracts)

  12. Decontamination and decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1993-08-01

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

  13. 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.

  14. Comparison of standardised decommissioning costing tools on pilot Vienna TRIGA MARK-II research reactor

    International Nuclear Information System (INIS)

    Hornacek, M.; Kristofova, K.; Slugen, V.; Zachar, M.; Stummer, T.

    2017-01-01

    The main purpose of the paper is to compare decommissioning costing code CERREX (Cost Estimation for Research Reactors in Excel) with advanced calculation methodology applied in eOMEGA-RR code. CERREX code was developed in line with the IAEA recommendations for decommissioning costing of research facilities and fully implements the ISDC (International Structure for Decommissioning Costing of Nuclear Installations) structure and costing methodology. In comparison with CERREX, usually applied in preliminary costing, the code eOMEGA-RR incorporates the realistic activity and material flow during decommissioning process (e.g. decontamination, dismantling and waste management). This advanced approach enables to carry out the decommissioning planning and costing more effectively. Moreover, the user-friendly interface helps to perform wide range of sensitivity analyses. In order to meet the above mentioned objectives, the model calculation costing case for TRIGA MARK-II research reactor in Vienna was developed in both calculation codes. The whole process covered four step-by-step procedures to be implemented. At first, inventory database taking into account physical as well as radiological parameters (e.g.: contamination, dose rates, nuclide vectors, limits and conditions) was developed. At second, advanced decommissioning costing case using CERREX and eOMEGA-RR code was created. At third, sensitivity analyses to estimate the impact of changing input parameters on calculated results were performed. Finally, costing results obtained from both cost calculation codes are compared and discussed. (authors)

  15. A Prediction on the Unit Cost Estimation for Decommissioning Activities Using the Experienced Data from DECOMMIS

    Energy Technology Data Exchange (ETDEWEB)

    Park, Seung Kook; Park, Hee Seong; Choi, Yoon Dong; Song, Chan Ho; Moon, Jei Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    The KAERI (Korea Atomic Energy Research Institute) has developed the DECOMMIS (Decommissioning Information Management System) and have been applied for the decommissioning project of the KRR (Korea Research Reactor)-1 and 2 and UCP (Uranium Conversion Plant), as the meaning of the first decommissioning project in Korea. All information and data which are from the decommissioning activities are input, saved, output and managed in the DECOMMIS. This system was consists of the web server and the database server. The users could be access through a web page, depending on the input, processing and output, and be modified the permissions to do such activities can after the decommissioning activities have created the initial system-wide data is stored. When it could be used the experienced data from DECOMMIS, the cost estimation on the new facilities for the decommissioning planning will be established with the basic frame of the WBS structures and its codes. In this paper, the prediction on the cost estimation through using the experienced data which were store in DECOMMIS was studied. For the new decommissioning project on the nuclear facilities in the future, through this paper, the cost estimation for the decommissioning using the experienced data which were WBS codes, unit-work productivity factors and annual governmental unit labor cost is proposed. These data were from the KRR and UCP decommissioning project. The differences on the WBS code sectors and facility characterization between new objected components and experienced dismantled components was reduces as scaling factors. The study on the establishment the scaling factors and cost prediction for the cost estimation is developing with the algorithms from the productivity data, now.

  16. Shippingport Station decommissioning project overview

    International Nuclear Information System (INIS)

    Schreiber, J.J.

    1985-01-01

    The U.S. Department of Energy is in the process of decommissioning the Shippingport Atomic Power Station located on the Ohio River, 30 miles northwest of Pittsburgh, Pennsylvania. The Shippingport Station is the first commercial size nuclear power plant to undergo decommissioning in the United Staes. The plant is located on approximately 7 acres of land owned by the Duquesne Light Company (DLC) and leased to the U.S. Government. DLC operates two nuclear power plants, Beaver Valley 1 and 2, located immediately adjacent to the site and the Bruce Mansfield coal-fired power plant is also within the immediate area. The Station was shutdown in October, 1982. Defueling operations began in 1983 and were completed by September, 1984. The Shippingport Station consists of a 275' x 60' fuel handling building containing the reactor containment chamber, the service building, the turbine building, the radioactive waste processing building, the administration building and other smaller support buildings. The Station has four coolant loops and most of the containment structures are located below grade. Structures owned by the U.S. Government including the fuel handling building, service building, contaminated equipment room, the boiler chambers, the radioactive waste processing building and the decontamination and laydown buildings will be dismantled and removed to 3 feet below grade. The area will then be filled with clean soil and graded. The turbine building, testing and training building and the administration building are owned by DLC and will remain

  17. Uranium hexafluoride production plant decommissioning

    International Nuclear Information System (INIS)

    Santos, Ivan

    2008-01-01

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

  18. Case study - Czechoslovakia

    International Nuclear Information System (INIS)

    Kovar, P.

    1986-01-01

    In the lecture Case Study - Czechoslovakia with the sub-title 'Unified System of Personnel Preparation for Nuclear Programme in Czechoslovakia' the actual status and the current experience of NPP personnel training and preparation in Czechoslovakia are introduced. The above mentioned training system is presented and demonstrated by the story of a proxy person who is going to become shift engineer in a nuclear power plant in Czechoslovakia. (orig./HP)

  19. Case Studies - Cervical Cancer

    Centers for Disease Control (CDC) Podcasts

    2010-10-15

    Dr. Alan Waxman, a professor of obstetrics and gynecology at the University of New Mexico and chair of the American College of Obstetricians and Gynecologists (ACOG) committee for the underserved, talks about several case studies for cervical cancer screening and management.  Created: 10/15/2010 by National Center for Chronic Disease Prevention and Health Promotion (NCCDPHP), Division of Cancer Prevention and Control (DCPC).   Date Released: 6/9/2010.

  20. Decommissioning strategies for a 10 MW research reactor

    International Nuclear Information System (INIS)

    Muck, Konrad

    2002-01-01

    The 10 MW multipurpose MTR research reactor ASTRA at the Austrian Research Centers Seibersdorf which operated continuously and successfully for 39 years, is to be decommissioned. In a decommissioning study the available options and the required stages for decommissioning and removal of the radioactive components were evaluated. Advantages and disadvantages among these options - dismantling to stage 1 of IAEA technical guide- lines (storage with surveillance), continuous dismantling to stage 2 (restricted site use) or complete removal of all radioactive material from the reactor in a continuous process without intermittent phases for radioactive decay - are discussed. It is shown that the complete dismantling of all radioactive components and materials in a continuous procedure without intervals for radioactive decay is the optimum option with lowest costs and probably the lowest exposure to be expected. The reasons for this choice are described in detail. The procedure in the transition between the valid operating license to the decommissioning license are described. The scope and content of the environmental impact statement required for decommissioning a reactor according to EU regulations are presented. Also, the arising volume and activity of the radioactive waste to be expected were evaluated. The estimates amount to approximately 320 kg of medium-level radioactive waste and about 100 t of activated and about 60 t of contaminated low level radioactive waste. The activity inventory in the various components to be dismantled is described. The dismantling techniques and procedures of the various components, irradiation and experimental facilities, beam tubes, coolant system pipes and components and the concrete biological shield are discussed

  1. Decommissioning of U.S. uranium production facilities

    Energy Technology Data Exchange (ETDEWEB)

    1995-02-01

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

  2. Decommissioning of U.S. uranium production facilities

    International Nuclear Information System (INIS)

    1995-02-01

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

  3. Planning of the BN-350 reactor decommissioning

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  4. Government Assigns New Supervisory Task. Safe Decommissioning

    International Nuclear Information System (INIS)

    Lekberg, Anna

    2003-01-01

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

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  6. 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

    operator to complete the radwaste and spent fuel management. All these facts resulted to general acceleration of decommissioning activities and decommissioning planing. As a consequence of historical approach, various technical objections and also for collocation of decommissioned facilities with operating ones, the preferred decommissioning option is deferred dismantling. The reduction of range and duration of safe enclosure from confinement to core structures and from 70 to 30 years was the result of changing radwaste management strategy. Currently preliminary decommissioning studies for WWERs are being updated including the optimisation of the safe enclosure /differed dismantling duration, in accordance with the full set of parameters

  7. 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

  8. 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

  9. Methodology and technology of decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1986-01-01

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

  10. 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)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1982-03-01

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

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

    International Nuclear Information System (INIS)

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

    1982-03-01

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

  13. Case Study - Alpha

    Directory of Open Access Journals (Sweden)

    Stephen Leybourne

    2016-11-01

    Full Text Available This case study was developed from an actual scenario by Dr. Steve Leybourne of Boston University.  The case documents the historical evolution of an organization, and has been used successfully in courses dealing with organizational and cultural change, and the utilization of ‘soft skills’ in project-based management. This is a short case, ideal for classroom use and discussion.  The issues are easily accessible to students, and there is a single wide ranging question that allows for the inclusion of many issues surrounding strategic decision-making, and behavioural and cultural change. Alpha was one of the earlier companies in the USA to invest in large, edge-of-town superstores, with plentiful free vehicle parking, selling food and related household products. Alpha was created in the 1950s as a subsidiary of a major publicly quoted retail group.  It started business by opening a string of very large discount stores in converted industrial and warehouse premises in the south of the United States. In the early days shoppers were offered a limited range of very competitively priced products. When Alpha went public in 1981 it was the fourth largest food retailer in the US, selling an ever-widening range of food and non-food products.  Its success continued to be based on high volume, low margins and good value for money, under the slogan of ‘Alpha Price.’

  14. Decommissioning of French nuclear submarines

    International Nuclear Information System (INIS)

    Robin, B.; Buzonniere, A. de; Chenais, J.

    2003-01-01

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

  15. Impact of nuclear installation decommissioning on the environment

    International Nuclear Information System (INIS)

    Hrncir, T.; Tatransky, P.

    2007-01-01

    The aim of the present paper is to describe the decommissioning process in terms of its impact on the environment and population. This paper briefly outlines the issue of decommissioning, given impact of decommissioning on the environment and population. Finally, this paper indicates the materials produced during the decommissioning process as well as their distribution on the basis of their activities. Contribution is terminated with scheme of decommissioning impact on the environment. (authors)

  16. Decommissioning and decontrolling the R1-reactor

    International Nuclear Information System (INIS)

    Bergman, C.; Holmberg, B.T.

    1985-01-01

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

  17. Licensing and decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    Working Group 1 (Licensing and Decommissioning of Nuclear Installations) investigated the question, 'Should it be recommended to work out international principles and rules on the licensing and decommissioning of nuclear installations and to make them subject to international instruments'. It was found that the legal systems in the countries examined are still too disparate to allow for a recommendation aiming at harmonizing the provisions for licensing. With respect to decommissioning, the WG considers the IAEA three-stage-plan to be a valuable first step towards standardisation. (CW) [de

  18. 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)

  19. Development of a Decommissioning Certificate Program

    International Nuclear Information System (INIS)

    Morton, M. R.

    1999-01-01

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

  20. Deactivation, Decontamination and Decommissioning Project Summaries

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, David Shane; Webber, Frank Laverne

    2001-07-01

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

  1. Collection and sharing of data and experience from EC-funded decommissioning projects

    International Nuclear Information System (INIS)

    Pflugrad, K.; Colquhoun, A.P.; Schreck, G.; Huske, M.; Petrasch, P.; Tuenckens, L.R.J.

    1999-01-01

    The European Commission's Fourth Framework Programme (1994-1998) on Nuclear Fission Safety includes the funding of projects relevant to the decommissioning of nuclear installations. The objectives of the programme for decommissioning are to continue the development of technology (a) to collect and analyse relevant data (b) to test and evaluate strategies and techniques and to stimulate the exchange of information and experience. Objective (b) involves related projects aimed at collecting and analysing data from past, current and future EC programmes and making them understandable and readily available in databases as well as studying how these and other databases might be integrated in a decommissioning strategic planning tool (SPT). This aims to assist EU organizations in making strategic choices for optimizing decommissioning programmes. This paper gives an update on database work, a progress report on the development of an EU access network and work on the standardization of cost item definitions. Progress on the SPT study is reviewed. (author)

  2. NOx trade. Case studies

    International Nuclear Information System (INIS)

    Jantzen, J.

    2002-01-01

    Some of the questions with respect to the trade of nitrogen oxides that businesses in the Netherlands have to deal with are dealt with: should a business buy or sell rights for NOx emission; which measures must be taken to reduce NOx emission; how much must be invested; and how to deal with uncertainties with regard to prices. Simulations were carried out with the MOSES model to find the answers to those questions. Results of some case studies are presented, focusing on the chemical sector in the Netherlands. Finally, the financial (dis)advantages of NOx trade and the related uncertainties for a single enterprise are discussed [nl

  3. Technical studying on design and manufacturing of the container for low level radioactive solid waste from the KRR 1 and 2 decommissioning

    International Nuclear Information System (INIS)

    Park, Seung Kook; Chung, Un Soo; Yang, Sung Hong; Lee, Dong Gyu; Jung Ki Jung

    2000-12-01

    The design requirement and manufacturing criteria have been proposed on the container for the package, storage and transportation of low level radioactive solid waste from decommissioning of KRR 1 and 2. The structure analysis was carried out based on the design criteria, and the safety of the container was assessed. The container with its capacity of 4m 3 was selected for the radioactive solid waste storage. The proposed container was satisfied the criteria of ISO 1496/1 and the packaging standard of Atomic Energy Act. Manufacturing and testing standards of IAEA were also applied to the container. Stress distribution and deformation were analyzed under given condition using ANSYS code, and the maximum stress was verified to be within the yield stress without any structural deformation. From the results of lifting tests which were lifting from the four top corner fittings and fork-lift pockets, it was verified that this container was safe

  4. Final feasibility study of possibilities and potentials of the disused iron ore mine Konrad (FRG) for low-level waste and decommissioning waste disposal

    International Nuclear Information System (INIS)

    Brewitz, W.; Stippler, R.

    1982-01-01

    The ''Institut fur Tieflagerung'' of the Gesellschaft fur Strahlen- and Umweltforschung, in collaboration with the Kernforschungszentrum Karlsruhe, carries out geoscientific and technical investigations in the disused iron ore mine Konrad. The aim is to prove the mine's feasibility for the disposal of low-level radioactive waste and decommissioning waste as well as the use of the existing mining installations. The investigations were initiated in 1975 and are being financed by the Minister for Research and Technology of the Federal Republic of Germany. Since 1978 the work is being supported as well by the Commission of the European Community in the scope of two years each. So far an amount of 60 mio DM has been spent, 86% for maintenance and further operation of the mine and 14% for research work

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  6. 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)

  7. Proceedings of the topical session on stakeholder involvement in decommissioning projects

    International Nuclear Information System (INIS)

    Santiago, Juan Luis; Chandler, Steve; Metcalfe, Doug; Le Bars, Yves

    2006-01-01

    Set up by the Radioactive Waste Management Committee (RWMC), the WPDD brings together senior representatives of national organisations who have a broad overview of Decommissioning and Dismantling (D and D) issues through their work as regulators, implementers, R and D experts or policy makers. These include representatives from regulatory authorities, industrial decommissioners from the NEA Co-operative Programme on Exchange of Scientific and Technical Information on Nuclear Installation Decommissioning Projects (CPD), and cross-representation from the other NEA Committees. The EC is a member of the WPDD and the IAEA is participating as an observer. This broad participation provides good possibilities for the co-ordination efforts amongst activities in the international programmes. At its sixth meeting, in Paris, 14-16 November 2005, the WPDD held a topical session on the 'Stakeholder Involvement in Decommissioning Projects'. The topical session was jointly planned and run with members of the NEA Forum on Stakeholder Confidence (FSC). This report documents the topical session. The main text summarises the lessons learnt and includes the rapporteurs reports. Appendix 1 and 2 provide the agenda of the topical session and all contributed papers respectively. The Topical session also provided a stimuli to review all the contributions in the area of stakeholder involvement that the WPDD has received since its inception. A list of references is provided in Appendix 3. The topical session was meant to provide an exchange of information and experience on the following issues: - Views from Stakeholders Regarding Stakeholder Involvement and Their Own Role. - Case Studies on Stakeholders Confidence. At the end of each session time was allotted for a plenary discussion. The Rapporteur reviewed the main points and the lessons learnt at the end of the whole Topical Session. (authors)

  8. Decommissioning information management in decommissioning planning and operations at AECL (Ref 5054)

    International Nuclear Information System (INIS)

    Lemire, D.S.

    2006-01-01

    As the AECL Decommissioning program has grown over the past few years, particularly with regard to long-term planning, so has its need to manage the records and information required to support the program. The program encompasses a diverse variety of facilities, including prototype and research reactors, fuel processing facilities, research laboratories, waste processing facilities, buildings, structures, lands and waste storage areas, many of which have changed over time. The decommissioning program involves planning, assessing, monitoring and executing projects to decommission the facilities. The efficient and effective decommissioning planning, assessment, monitoring and execution for the facilities and projects are dependent on a sound information base, upon which decisions can be made. A vital part of this Information Base is the ongoing management of historical facility records, including decommissioning records, throughout the full life cycle of the facilities. This paper describes AECL's and particularly DP and O's approach to: 1) Establishing a decommissioning records and information framework, which identifies what records and information are relevant to decommissioning, prioritizing the decommissioning facilities, identifying sources of relevant information and providing a user-friendly, electronic, search and retrieval tool for facility information accessible to staff. 2) Systematically, gathering, assessing, archiving and identifying important information and making that information available to staff to support their ongoing decommissioning work. 3) Continually managing and enhancing the records and information base and its support infrastructure to ensure its long-term availability. 4) Executing special information enhancement projects, which transform historic records into information for analysis. (author)

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

    International Nuclear Information System (INIS)

    2013-01-01

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

  10. 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

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

    International Nuclear Information System (INIS)

    Zhu Bo

    2005-01-01

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

  12. New iteration of decommissioning program for NPP Krsko

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  13. Commercialization of nuclear power plant decommissioning technology

    International Nuclear Information System (INIS)

    Williams, D.H.

    1983-01-01

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

  14. Nuclear submarine decommissioning and related environmental problems

    International Nuclear Information System (INIS)

    Sarkisov, A.

    1998-01-01

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

  15. Decommissioning of DR 1, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Lauridsen, Kurt

    2006-01-15

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

  16. Health physics considerations in decontamination and decommissioning

    International Nuclear Information System (INIS)

    1985-12-01

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

  17. Environmental impact assessment of NPP decommissioning

    International Nuclear Information System (INIS)

    Hinca, R.

    2009-01-01

    In this presentation the following potential impacts of decommissioning of NPP are discussed: - Impacts on population; Impacts on natural environment; Land impacts; Impacts on urban complex and land utilisation; Possible impacts on area as a result of failure.

  18. Canadian decommissioning experience from policy to project

    International Nuclear Information System (INIS)

    Pare, F.E.

    1992-01-01

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

  19. AECL's strategy for decommissioning Canadian nuclear facilities

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  20. NPP A-1 decommissioning - Phase I

    International Nuclear Information System (INIS)

    Krstenik, A.; Blazek, J.

    2000-01-01

    Nuclear power plant A-1 with output 150 MW e , with metallic natural uranium fuelled, CO 2 cooled and heavy water moderated reactor had been prematurely finally shut down in 1977. It is necessary to mention that neither operator nor regulatory and other authorities have been prepared for the solution of such situation. During next two consecutive years after shutdown main effort of operator focused on technical and administrative activities which are described in the previous paper together with approach, condition and constraints for NPP A-1 decommissioning as well as the work and research carried out up to the development and approval of the Project for NPP A-1 decommissioning - I. phase. Subject of this paper is description of: (1) An approach to NPP A -1 decommissioning; (2) An approach to development of the project for NPP A-1 decommissioning; (3) Project - tasks, scope, objectives; (4) Mode of the Project realisation; (5) Progress achieved up to the 1999 year. (authors)

  1. Decommissioning co-operation in Europe

    International Nuclear Information System (INIS)

    Simon, R.A.

    1992-01-01

    Under the provisions of the Euratom treaty, member states of the European Community have since 1978 been conducting successive five-year R and D programmes in the field of decommissioning on the basis of cost-sharing contracts. The main objective of the programmes is to establish safe, socially acceptable and economic decommissioning strategies for obsolete nuclear plant. The programmes share the common aim of all Euratom activities in promoting cooperation, scientific exchange and industrial competition within the Community. (author)

  2. The cost of decommissioning nuclear facilities

    International Nuclear Information System (INIS)

    1993-01-01

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

  3. New technologies in decommissioning and remediation

    International Nuclear Information System (INIS)

    Fournier, Vincent

    2016-01-01

    New and emerging technologies are making decommissioning and remediation more cost effective, faster and safer. From planning to execution and control, the use of new technologies is on the rise. Before starting decommissioning or environmental remediation, experts need to plan each step of the process, and to do that, they first need a clear idea of the characteristics of the structure and the level of radiation that they can expect to encounter

  4. Policy on the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-08-01

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

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

    International Nuclear Information System (INIS)

    Mihalic, M.A.

    1998-02-01

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

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  7. 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)

  8. 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

  9. Decommissioning Licensing Process of Nuclear Installations in Spain

    International Nuclear Information System (INIS)

    Correa Sainz, Cristina

    2016-01-01

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

  10. Decommissioning health physics a handbook for marssim users

    CERN Document Server

    Abelquist, Eric W

    2013-01-01

    "This layout makes the book useful for those with less experience at implementing the MARSS1M process and allows those with more experience to go directly to individual chapters to review specific information… As with the first edition, this book is a valuable addition to the MARSSIM practitioner's library…I recommend this book for all who are involved in the decommissioning process."-James Reese in Health Physics"This book is the most complete treatment of the topic I've seen-including chapters on virtually every aspect of MARSSIM as well as problems to solve and worked-out solutions for many of them in the back (making it a great textbook on the topic for anyone teaching a graduate class or short course on the topic). It's also a great reference since the chapters include equations, reference tables and plots, and a nice selection of case studies and examples. … The second edition is not only updated to reflect the latest and greatest guidance, it also includes some new material. … a tremendously us...

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

    International Nuclear Information System (INIS)

    Short, S.M.

    1988-01-01

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

  12. Goiania incident case study

    International Nuclear Information System (INIS)

    Petterson, J.S.

    1988-06-01

    The reasons for wanting to document this case study and present the findings are simple. According to USDOE technical risk assessments (and our own initial work on the Hanford socioeconomic study), the likelihood of a major accident involving exposure to radioactive materials in the process of site characterization, construction, operation, and closure of a high-level waste repository is extremely remote. Most would agree, however, that there is a relatively high probability that a minor accident involving radiological contamination will occur sometime during the lifetime of the repository -- for example, during transport, at an MRS site or at the permanent site itself during repacking and deposition. Thus, one of the major concerns of the Yucca Mountain Socioeconomic Study is the potential impact of a relatively minor radiation-related accident. A large number of potential impact of a relatively minor radiation-related accident. A large number of potential accident scenarios have been under consideration (such as a transportation or other surface accident which results in a significant decline in tourism, the number of conventions, or the selection of Nevada as a retirement residence). The results of the work in Goiania make it clear, however, that such a significant shift in established social patterns and trends is not likely to occur as a direct outcome of a single nuclear-related accident (even, perhaps, a relatively major one), but rather, are likely to occur as a result of the enduring social interpretations of such an accident -- that is, as a result of the process of understanding, communicating, and socially sustaining a particular set of associations with respect to the initial incident

  13. Changes in river channel pattern as a result of the construction, operation and decommissioning of watermills – the case of the middle reach of the River Liswarta near Krzepice, Poland

    OpenAIRE

    Fajer Maria

    2018-01-01

    Changes in river channel pattern in the middle reach of the River Liswarta and in the lower reaches of its tributaries near Krzepice were analysed, and were related to the construction, operation and decommissioning of watermills. For this purpose, old maps which covered the period from the beginning of the 18th century until the 20th century were used alongside written historical sources. Maps from the first half of the 19th century provided valuable source material. Traces of old mill water...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-06-01

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

  15. Securing decommissioning funds. Why organization matters?

    International Nuclear Information System (INIS)

    Tchapga, F.

    2005-01-01

    Full text: Securing decommissioning funds requires that the financial resources set aside for the purpose of decommissioning be managed prudently. Decommissioning of nuclear power plant is prescribed by National Atomic Laws or by other nuclear legislation. It is a mandatory operation. The operators of nuclear power plants set money aside for that purpose. This is known as 'Decommissioning reserve fund'. Decommissioning implies costs very distant in time. Thus, it is obvious, from an economic point of view, that the funds set aside should be managed. As decommissioning is mandatory, the funds accumulated should be secured. In others words, they should be available when needed. Availability of funds is influenced by endogenous and exogenous factors. Endogenous factors are a matter of design of the reserve funds. They include the management of the funds, its monitoring and control... Availability of funds is influenced by these factors, depending on the rules to which the behaviour of the manager of the funds is subjected. In contrast, exogenous factors deal with the energy context. These factors are mainly the electricity sector organisation and/or the overall economic situation. They are decisive factors of the economic performance of the reserve fund for a given design. Therefore, the requirement of availability of funds, when needed, is a matter of compatibility between the design of the decommissioning funds and the electricity context. Put differently, reserve fund's design need to be consistent with the electricity context's features in respect of the availability of funds. Current reserve funds were designed in a context of monopoly regime. In this context, availability of decommissioning funds was not questionable. At least, as far as the design of the reserve funds is concerned. This is because nuclear generator didn't confront any competition pressure. Electricity prices were set trough rate base mechanism, and all the business risks were borne by the

  16. Natural Learning Case Study Archives

    Science.gov (United States)

    Lawler, Robert W.

    2015-01-01

    Natural Learning Case Study Archives (NLCSA) is a research facility for those interested in using case study analysis to deepen their understanding of common sense knowledge and natural learning (how the mind interacts with everyday experiences to develop common sense knowledge). The database comprises three case study corpora based on experiences…

  17. Spatial Multicriteria Decision Analysis of Flood Risks in Aging-Dam Management in China: A Framework and Case Study

    Science.gov (United States)

    Yang, Meng; Qian, Xin; Zhang, Yuchao; Sheng, Jinbao; Shen, Dengle; Ge, Yi

    2011-01-01

    Approximately 30,000 dams in China are aging and are considered to be high-level risks. Developing a framework for analyzing spatial multicriteria flood risk is crucial to ranking management scenarios for these dams, especially in densely populated areas. Based on the theories of spatial multicriteria decision analysis, this report generalizes a framework consisting of scenario definition, problem structuring, criteria construction, spatial quantification of criteria, criteria weighting, decision rules, sensitivity analyses, and scenario appraisal. The framework is presented in detail by using a case study to rank dam rehabilitation, decommissioning and existing-condition scenarios. The results show that there was a serious inundation, and that a dam rehabilitation scenario could reduce the multicriteria flood risk by 0.25 in the most affected areas; this indicates a mean risk decrease of less than 23%. Although increased risk (<0.20) was found for some residential and commercial buildings, if the dam were to be decommissioned, the mean risk would not be greater than the current existing risk, indicating that the dam rehabilitation scenario had a higher rank for decreasing the flood risk than the decommissioning scenario, but that dam rehabilitation alone might be of little help in abating flood risk. With adjustments and improvement to the specific methods (according to the circumstances and available data) this framework may be applied to other sites. PMID:21655125

  18. Technology and costs for decommissioning the Swedish nuclear power plants

    International Nuclear Information System (INIS)

    1986-05-01

    The study shows that, from the viewpoint of radiological safety, a nuclear power plant can be dismantled immediately after it has been shut down and the fuel has been removed, which is estimated to take about one year. Most of the equipment that will be used in decommissioning is already available and is used routinely in maintenance and rebuilding work at the nuclear power plants. Special equipment need only be developed for dismantlement of the reactor vessel and for demolishing of heavy concrete structures. The dismantling of a nuclear power plant can be accomplished in about five years, with an average labour force of about 200 men. The maximum labour force required for Ringhals 1 has been estimated at about 500 men during the first years, when active systems are being dismantled in a number of fronts in the plant. During the last years when the buildings are being demolished, approximately 50 men are required. In order to limit the labour requirement and the dose burden to the personnel, the material is taken out in as large pieces as possible. The cost of decommissioning a boiling water reactor (BWR) of the size of Ringhals 1 has been estimated to be about MSEK 540 in January 1986 prices, and for a pressurized water reactor (PWR, Ringhals 2) about MSEK 460. The cost for the other Swedish nuclear power plants lie in the range of MSEK 410-760. These are the direct cost for the decommissioning work, to which must be added the costs of transportation and disposal of the decommissioning waste, about 100 000 m/sup3/. These costs have been estimated to be about MSEK 600 for the 12 Swedish reactors. (author)

  19. Nuclear reactor decommissioning: an analysis of the regulatory environments

    Energy Technology Data Exchange (ETDEWEB)

    Cantor, R.

    1986-08-01

    In the next several decades, the electric utility industry will be faced withthe retirement of 50,000 megawatts (mW) of nuclear capacity. Responsibility for the financial and technical burdens this activity entails has been delegated to the utilities operating the reactors. However, the operators will have to perform the tasks of reactor decommissioning within the regulatory environment dictated by federal, state and local regulations. The purpose of this study was to highlight some of the current and likely trends in regulations and regulatory practices that will significantly affect the costs, technical alternatives and financing schemes encountered by the electric utilities and their customers. To identify significant trends and practices among regulatory bodies and utilities, a reviw of these factors was undertaken at various levels in the regulatory hierarchy. The technical policies were examined in reference to their treatment of allowed technical modes, restoration of the plant site including any specific recognition of the residual radioactivity levels, and planning requirements. The financial policies were examined for specification of acceptable financing arrangements, mechanisms which adjust for changes in the important parameters used to establish the fund, tax and rate-base treatments of the payments to and earnings on the fund, and whether or not escalation and/or discounting were considered in the estimates of decommissioning costs. The attitudes of regulators toward financial risk, the tax treatment of the decommissioning fund, and the time distribution of the technical mode were found to have the greatest effect on the discounted revenue requirements. Under plausible assumptions, the cost of a highly restricted environment is about seven times that of the minimum revenue requirement environment for the plants that must be decommissioned in the next three decades.

  20. Nuclear reactor decommissioning: an analysis of the regulatory environments

    International Nuclear Information System (INIS)

    Cantor, R.

    1986-08-01

    In the next several decades, the electric utility industry will be faced withthe retirement of 50,000 megawatts (mW) of nuclear capacity. Responsibility for the financial and technical burdens this activity entails has been delegated to the utilities operating the reactors. However, the operators will have to perform the tasks of reactor decommissioning within the regulatory environment dictated by federal, state and local regulations. The purpose of this study was to highlight some of the current and likely trends in regulations and regulatory practices that will significantly affect the costs, technical alternatives and financing schemes encountered by the electric utilities and their customers. To identify significant trends and practices among regulatory bodies and utilities, a reviw of these factors was undertaken at various levels in the regulatory hierarchy. The technical policies were examined in reference to their treatment of allowed technical modes, restoration of the plant site including any specific recognition of the residual radioactivity levels, and planning requirements. The financial policies were examined for specification of acceptable financing arrangements, mechanisms which adjust for changes in the important parameters used to establish the fund, tax and rate-base treatments of the payments to and earnings on the fund, and whether or not escalation and/or discounting were considered in the estimates of decommissioning costs. The attitudes of regulators toward financial risk, the tax treatment of the decommissioning fund, and the time distribution of the technical mode were found to have the greatest effect on the discounted revenue requirements. Under plausible assumptions, the cost of a highly restricted environment is about seven times that of the minimum revenue requirement environment for the plants that must be decommissioned in the next three decades

  1. Decommissioning and re-utilization of the Musashi Reactor

    International Nuclear Information System (INIS)

    Tomio Tanzawa; Nobukazu Iijima; Norikazu Horiuchi; Tadashi Yoshida; Tetsuo Matsumoto; Naoto Hagura; Ryouhei Kamiya

    2008-01-01

    The Musashi Institute of Technology Research Reactor (the Musashi Reactor) is a TRIGA-? with maximum thermal power of 100 kW. The decommissioning was decided in May, 2003. The reactor facility is now under decommissioning. The phased decommissioning was selected. Phase 1 consists of permanent shutdown of the reactor and stopping the operational functions, and transportation of the spent nuclear fuels. After completion of the transportation, the reactor facility is characterized as the storage of low level radioactive materials. This is phase 2. Activities of phase 1 were completed and the facility is now under phase 2. Activities of phase 3 consist of dismantling the reactor tank and the shielding, and delivering the radioactive waste to a waste disposal facility. The phase 3 will be started on condition that the undertaking of the waste disposal for research reactors will be established. On the other hand, re-utilization of the facility has being studied, and 'realistic' reactor simulator was turned out by utilizing the reactor installations such as control rod drive and operation console. (authors)

  2. The decommissioning of the Trino nuclear power plant

    International Nuclear Information System (INIS)

    Del Lucchese, M.; De Santis, R.; Novella, M.; Nurden, P.L.; Walkden, P.; Watson, B.

    2002-01-01

    Following a referendum in Italy in the late 1980's the four nuclear power stations were closed down and subsequently, in the 1990's, the process of privatisation of the electricity industry was started. Starting from those conditions, Sogin (current owner of the four NPPs) was beginning to develop programs and projects to reach 'green field' conditions for all NPP's in Italy. Within this frame, an agreement was built between Sogin and BNFL, based on the previous successful collaboration, to develop a prompt decommissioning strategy for the Latina Magnox reactor, to work together taking into account their specific experiences in the decommissioning field, both for Italy, the United Kingdom and for other countries. Over the past year, a revised prompt decommissioning programme, drawing upon the combined experience of the two companies, has been developed for Trino. The study incorporates the removal, segmentation and packaging of components such as the reactor vessel and internals for transportation to the national repository, as well as cost efficient engineered solutions for the removal, segmentation and decontamination of the remaining systems, plant equipment and containment structures to a point where the containment structure itself can be released for demolition. It was recognised that this target was conditional upon the availability of a national LLW repository together with interim stores for both spent fuel and HLW by 2009. The strategy has been based on the principles of minimising both doses and waste products that require long term storage, maximizing 'free release' materials and utilising existing and regulatory approved technologies. (author)

  3. Closing responsibilities: decommissioning and the law

    International Nuclear Information System (INIS)

    Macrory, R.

    1990-01-01

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

  4. Systematic Approach for Decommissioning Planning and Estimating

    International Nuclear Information System (INIS)

    Dam, A. S.

    2002-01-01

    Nuclear facility decommissioning, satisfactorily completed at the lowest cost, relies on a systematic approach to the planning, estimating, and documenting the work. High quality information is needed to properly perform the planning and estimating. A systematic approach to collecting and maintaining the needed information is recommended using a knowledgebase system for information management. A systematic approach is also recommended to develop the decommissioning plan, cost estimate and schedule. A probabilistic project cost and schedule risk analysis is included as part of the planning process. The entire effort is performed by a experienced team of decommissioning planners, cost estimators, schedulers, and facility knowledgeable owner representatives. The plant data, work plans, cost and schedule are entered into a knowledgebase. This systematic approach has been used successfully for decommissioning planning and cost estimating for a commercial nuclear power plant. Elements of this approach have been used for numerous cost estimates and estimate reviews. The plan and estimate in the knowledgebase should be a living document, updated periodically, to support decommissioning fund provisioning, with the plan ready for use when the need arises

  5. 427 Case studies

    African Journals Online (AJOL)

    Marinda

    2009-05-22

    May 22, 2009 ... No other complications except hypersensitivity to hypnotic agents were observed. Case 2: The patient was a 10-year-old boy with Cornelia de Lange syndrome who underwent dental treatment under general anaesthesia. He had a history and symptoms of obstructive airway disorders in addition to showing ...

  6. 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.

  7. Treatment of mine-water from decommissioning uranium mines

    International Nuclear Information System (INIS)

    Fan Quanhui

    2002-01-01

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

  8. Magnox Electric plc's strategy for decommissioning its nuclear licensed sites

    International Nuclear Information System (INIS)

    2002-02-01

    The 1995 White Paper 'Review of Radioactive Waste Management Policy: Final Conclusions', Cm 2919, determined that the Government would ask all nuclear operators to draw up strategies for the decommissioning of their redundant plant and that the Health and Safety Executive (HSE) would review these strategies on a quinquennial basis in consultation with the environment agencies. This review has considered Magnox Electric pie (Magnox Electric) arrangements for the identification of its responsibilities for decommissioning and radioactive waste management, the quantification of the work entailed, the standards and timing of the work, and the arrangements to provide the financial resources to undertake the work. This is the second review by the HSE in response to Cm 2919 of Magnox Electric's nuclear power station decommissioning and radioactive waste management strategies and is based on the situation in April 2000. It reports the Nuclear Installations Inspectorate's (NIl) view that the strategies proposed by Magnox Electric are appropriate. The strategies are considered to be largely consistent with both national and international policy statements and guidance, and are potentially flexible enough to be able to accommodate lessons learned during ongoing decommissioning activities. During the review the Nil has considered whether Magnox Electric has identified all the tasks required to fully decommission its sites. Generally this has been found to be the case. Some additional tasks have been identified due, in part, to the reviewers' noting the changes which have recently taken place in environmental expectations. At this time, on the basis of the information presented, and with the provisos stated below, Magnox Electric's provisioning for final dismantling after 85 years is considered to be reasonable. The Nil expects Magnox Electric to further justify why a shorter timescale is not reasonably practicable before the next review. One of the purposes of this review

  9. Decommissioning of nuclear power stations in community countries carried out and projected

    International Nuclear Information System (INIS)

    Cregut, A.; Gregory, A.R.

    1984-01-01

    The decommissioning of large plants such as nuclear power stations merits an approach requiring the introduction of measures and procedures allowing them to be dealt with efficiently; this efficiency would imply concern for optimum economy of operations while respecting the safety and protection rules inherent in nuclear energy. Consequently, plant owners require: the tactical and policy elements to guide them in their decisions and choices; efficient tools, equipment and processes which meet their needs; information gained from experience of decommissioning already carried out which would provide them with a verified background knowledge when dealing with problems. Since decommissioning experience to date has not made it possible to draw up codes and guidelines, it is important to review the work carried out by Community countries in particular on the decommissioning of nuclear power plants. The following paper does not claim to be exhaustive or to make value judgements. Its aim is to list the nuclear power stations shut down in Community countries, to outline the decommissioning levels selected in each case and to underline some interesting aspects of the technical options. In conclusion it will review what appeared to be the difficulties common to the various projects. (author)

  10. Decommissioning three nuclear reactors at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Montoya, G.M.; Salazar, M.

    1992-01-01

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

  11. 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.

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

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  13. Platform decommissioning: Socio-economic impacts

    International Nuclear Information System (INIS)

    Scheelhaase, Janina D.

    1998-01-01

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

  14. Model Regulations for Decommissioning of Facilities

    International Nuclear Information System (INIS)

    2017-07-01

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

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

    International Nuclear Information System (INIS)

    Combs, A.B.; Davis, W.P.; Elswick, T.C.; Garner, J.M.; Geichman, J.R.

    1982-01-01

    Monsanto Research Corporation (MRC), which operates Mound for the Department of Energy (DOE), has been decommissioning radioactively contaminated facilities since 1949. We are currently decommissioning three plutonium-238 contaminated facilities (approximately 50,000 ft 2 ) that contained 1100 linear ft of gloveboxes; 900 linear ft of conveyor housing; 2650 linear ft of dual underground liquid waste lines; and associated contaminated piping, services, equipment, structures, and soil. As of June 1982, over 29,000 Ci of plutonium-238 have been removed in waste and scrap residues. As a result of the current and previous decommissioning projects, valuable experience has been gained in tooling and techniques. Special techniques have been developed in planning, exposure control, contamination control, equipment removal, structural decontamination, and waste packaging

  16. The Ministry of Dilemmas [decommissioning nuclear submarines

    International Nuclear Information System (INIS)

    Peden, W.

    1995-01-01

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

  17. 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)

  18. Nuclear data requirements for fission reactor decommissioning

    International Nuclear Information System (INIS)

    Kocherov, N.P.

    1993-01-01

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

  19. Site Decommissioning Management Plan. Supplement 1

    International Nuclear Information System (INIS)

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

    1995-11-01

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

  20. Decommissioning of the Neuherberg Research Reactor (FRN)

    International Nuclear Information System (INIS)

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

    1982-01-01

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

  1. Decommissioning of DR 2. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Strufe, N.

    2009-02-15

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

  2. Selection of decommissioning strategies: Issues and factors. Report by an expert group

    International Nuclear Information System (INIS)

    2005-11-01

    A comprehensive assessment of possible strategies is the key step in a decommissioning process. It should be initiated at an early stage in a facility's lifecycle and include a number of factors. The IAEA has provided extensive guidance on decommissioning strategy selection, but there are a number of cases - particularly in countries with limited resources, but not limited to them - where the selection is forced and constrained by prevailing factors and conditions. In its role of an international expert committee assisting the IAEA, the Technical Group on Decommissioning (TEGDE) debates and draws conclusions on topics omitted from general guidance. TEGDE members met in Vienna in 2003, 2004 and 2005 to develop the basis for this publication. The views expressed here reflect those of TEGDE and not necessarily those of the IAEA

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

    International Nuclear Information System (INIS)

    Rowden, M.A.; Fowler, S.E.

    1983-01-01

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

  4. General principles underlying the decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    1988-03-01

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

  5. 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)

  6. Syncope: Case Studies.

    Science.gov (United States)

    Kleyman, Inna; Weimer, Louis H

    2016-08-01

    Syncope, or the sudden loss of consciousness, is a common presenting symptom for evaluation by neurologists. It is not a unique diagnosis but rather a common manifestation of disorders with diverse mechanisms. Loss of consciousness is typically preceded by a prodrome of symptoms and sometimes there is a clear trigger. This article discusses several cases that illustrate the various causes of syncope. Reflex syncope is the most common type and includes neurally mediated, vasovagal, situational, carotid sinus hypersensitivity, and atypical forms. Acute and chronic autonomic neuropathies and neurodegenerative disorders can also present with syncope. Copyright © 2016 Elsevier Inc. All rights reserved.

  7. Decommissioning of a tritium-contaminated laboratory

    International Nuclear Information System (INIS)

    Harper, J.R.; Garde, R.

    1981-11-01

    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 was constructed in 1953 and was in service for tritium research and fabrication of lithium tritide components until 1974. The major features of the laboratory included some 25 meters of gloveboxes and hoods, associated vacuum lines, utility lines, exhaust ducts, electrodryers, blowers, and laboratory benches. This report presents details on the decommissioning, health physics, waste management, environmental surveillance, and costs for the operation

  8. Shippingport station decommissioning project technology transfer program

    International Nuclear Information System (INIS)

    McKernan, M.L.

    1989-01-01

    The US Department of Energy (DOE) Shippingport Station Decommissioning Project (SSDP) decontaminated and dismantled the world's first nuclear-fueled, commercial-size electric power plant. The SSDP programmatic goal direction for technology transfer is documentation of project management and operations experience. The objective is to provide future nuclear facility decommissioning projects with pertinent SSDP performance data for project assessment, planning, and operational implementation. This paper sets out access and availability directions for SSDP technology acquisition. Discusses are technology transfer definition; technology transfer products including topical and other project reports, professional-technical society presentations, other project liaison and media relations, visual documentation, and technology transfer data base; and retrieving SSDP information

  9. Optimization in the decommissioning of uranium tailings

    International Nuclear Information System (INIS)

    1987-06-01

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

  10. Large transport packages for decommissioning waste

    International Nuclear Information System (INIS)

    Price, M.S.T.

    1988-08-01

    This document reports progress on a study of large transport packages for decommissioning waste and is the semi-annual report for the period 1 January - 30 June 1988. The main tasks performed during the period related to the assembly of package design criteria ie those aspects of manufacture, handling, storage, transport and disposal which impose constraints on design. This work was synthesised into a design specification for packages which formed the conclusion of that task and was the entry into the final task - the development of package design concepts. The design specifications, which concentrated on the Industrial Package category of the IAEA Transport Regulations, has been interpreted for the two main concepts (a) a self-shielded package disposed of in its entirety and (b) a package with returnable shielding. Preliminary information has been prepared on the cost of providing the package as well as transport to a repository and disposal. There is considerable uncertainty about the cost of disposal and variations of over a factor of 10 are possible. Under these circumstances there is merit in choosing a design concept which is relatively insensitive to disposal cost variations. The initial results indicate that on these grounds the package with returnable shielding is preferred. (author)

  11. Building theories from case study research: the progressive case study

    NARCIS (Netherlands)

    Steenhuis, H.J.; de Bruijn, E.J.

    2006-01-01

    Meredith (1998) argues for more case and field research studies in the field of operations management. Based on a literature review, we discuss several existing approaches to case studies and their characteristics. These approaches include; the Grounded Theory approach which proposes no prior

  12. Theory Testing Using Case Studies

    DEFF Research Database (Denmark)

    Møller, Ann-Kristina Løkke; Dissing Sørensen, Pernille

    2014-01-01

    The appropriateness of case studies as a tool for theory testing is still a controversial issue, and discussions about the weaknesses of such research designs have previously taken precedence over those about its strengths. The purpose of the paper is to examine and revive the approach of theory...... testing using case studies, including the associated research goal, analysis, and generalisability. We argue that research designs for theory testing using case studies differ from theorybuilding case study research designs because different research projects serve different purposes and follow different...

  13. The institutional framework of decommissioning in Italy

    International Nuclear Information System (INIS)

    Goti, Massimo

    2005-01-01

    Full text: Decommissioning of the NPP is generally viewed in a negative framework. On the contrary, it is an activity which aims is said to obtain the final removal of the risk factors from the environment. It is the last step of the production cycle, whose importance is underlined by the Regulation recently issued for the correct management of resources in the territory. Decommissioning NPP involves the final arrangements of the radioactive wastes, produced either during the past operation period or resulting from the dismantling operation. All the radioactive wastes must be conditioned and maintained in safe conditions. Radioactive waste management is no longer a problem for those countries that decided to face it, that is the majority of the industrialised countries. Correct technological solutions exist, due exist, respectful of the environment, of the people, of the ethical principles. The centrality of the problem is also decreed by the fact that sometimes now, the European Commission has been working on the issue of the directive on waste management, an effort which Italy has strongly supported, also during the Presidency period. Decommissioning on NPP is moreover an activity that implies advanced technological solutions, multilateral overlapping programs, working of style situations. Not many countries have completed yet (the) decommissioning of their plants: such activity should therefore be seen as an opportunity for the growth and the assertion of the Italian industry, also in view of the potential new market and the alliance with European industries. Of the 530 nuclear reactors present in world today, approximately 100 are undergoing decommissioning. In the next 2 years another 100 will reach the end of their operative life. Probably after the necessary system improvement many of them will continue to work, but it is clear that the international market of the decommissioning will continue to grow in the next years. Italy can play an important role in

  14. Methodology to collect data on decommissioning costs and occupational radiation exposure

    International Nuclear Information System (INIS)

    Petrasch, P.; Roger, J.

    1993-01-01

    Decommissioning data collection has been, up to now, almost a national matter. The present joint study performed by NIS Ingenieurgesellschaft mbH, Hanau, and the Commissariat a l'energie atomique, Unite de declassement d'installations nucleaires, and coordinated by the Commission of the European Communities, is intended to identify a methodology allowing the collection of data which are useful to manage a decommissioning project, e.g. data on dismantling costs, occupational radiation exposure and waste arisings. A common structure for decommissioning tasks (called working packages) derived from those already in use at the abovementioned organizations has been established and the corresponding first series of data-collection sheets defined in order to cover data from LWRs, GCRs (UNGGs) and nuclear fuel cycle installations. Work focused on the cost of decommissioning tasks. The study is intended to be a first step towards an EC-wide usable data-base for data generated in the various ongoing and future decommissioning projects

  15. Analysis of the Possibility of Required Resources Estimation for Nuclear Power Plant Decommissioning Applying BIM

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Insu [Korea Institute of construction Technology, Goyang (Korea, Republic of); Kim, Woojung [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Estimation of decommissioning cost, decommissioning strategy, and decommissioning quantity at the time when entering into any decommissioning plans are some elements whose inputs are mandatory for nuclear power plant decommissioning. Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. This study aims at analyzing whether required resources for decommissioning nuclear power plants can be estimated, applying BIM. To achieve this goal, this study analyzed the status quo of BIM such as definition, characteristics, and areas applied, and made use of them when drawing out study results by examining types and features of the tools realizing BIM. In order to review how BIM could be used for decommissioning nuclear power plants, the definition, characteristics and applied areas of BIM were discussed. BIM designs objects of the structures (walls, slabs, pillars, stairs, windows and doors, etc.) by 3D technology and endows attribute (function, structure and usage) information for each object, thereby providing visualized information of structures for participants in construction projects. Major characteristics of BIM attribute information are as follows: - Geometry: The information of objects is represented by measurable geometric information - Extensible object attributes: Objects include pre-defined attributes, and allow extension of other attributes. Any model that includes these attributes forms relationships with other various attributes in order to perform analysis and simulation. - All information including the attributes are integrated to ensure continuity, accuracy and accessibility, and all information used during the life cycle of structures are supported. This means that when information of required resources is added as another attributes other than geometric

  16. Analysis of the Possibility of Required Resources Estimation for Nuclear Power Plant Decommissioning Applying BIM

    International Nuclear Information System (INIS)

    Jung, Insu; Kim, Woojung

    2014-01-01

    Estimation of decommissioning cost, decommissioning strategy, and decommissioning quantity at the time when entering into any decommissioning plans are some elements whose inputs are mandatory for nuclear power plant decommissioning. Ways to estimate decommissioning of required resources in the past have imposed great uncertainty since they analyze required resources at the construction stage, analyzing and consulting decommissioning required resources of overseas nuclear power plants. This study aims at analyzing whether required resources for decommissioning nuclear power plants can be estimated, applying BIM. To achieve this goal, this study analyzed the status quo of BIM such as definition, characteristics, and areas applied, and made use of them when drawing out study results by examining types and features of the tools realizing BIM. In order to review how BIM could be used for decommissioning nuclear power plants, the definition, characteristics and applied areas of BIM were discussed. BIM designs objects of the structures (walls, slabs, pillars, stairs, windows and doors, etc.) by 3D technology and endows attribute (function, structure and usage) information for each object, thereby providing visualized information of structures for participants in construction projects. Major characteristics of BIM attribute information are as follows: - Geometry: The information of objects is represented by measurable geometric information - Extensible object attributes: Objects include pre-defined attributes, and allow extension of other attributes. Any model that includes these attributes forms relationships with other various attributes in order to perform analysis and simulation. - All information including the attributes are integrated to ensure continuity, accuracy and accessibility, and all information used during the life cycle of structures are supported. This means that when information of required resources is added as another attributes other than geometric

  17. Fuzzy-Set Case Studies

    Science.gov (United States)

    Mikkelsen, Kim Sass

    2017-01-01

    Contemporary case studies rely on verbal arguments and set theory to build or evaluate theoretical claims. While existing procedures excel in the use of qualitative information (information about kind), they ignore quantitative information (information about degree) at central points of the analysis. Effectively, contemporary case studies rely on…

  18. Kickstarter - A Case Study

    OpenAIRE

    Willumsen, Ea Christina; Byg-Fabritius, Edith Ursula Tvede

    2013-01-01

    This paper is an investigation of the online crowdfunding platform Kickstarter, and discusses what makes a Kickstarter campaign successful. Two previous Kickstarter campaigns have been debated in focus groups interviews, as the basis of the study is a reception analysis of two focus group interviews. Ee apply theories from Schrøder (2000) and Batey (2008) to our analysis to study how the campaigns appeal to their backers. By drawing on ideas from Rogers (2003) and Pine & Gilmore (1998), w...

  19. Shippingport station decommissioning project ALARA Program

    Energy Technology Data Exchange (ETDEWEB)

    Crimi, F.P. [Lockheed Environmental Systems and Technology Co., Houston, TX (United States)

    1995-03-01

    Properly planned and implemented ALARA programs help to maintain nuclear worker radiation exposures {open_quotes}As Low As Reasonably Achievable.{close_quotes}. This paper describes the ALARA program developed and implemented for the decontamination and decommissioning (D&D) of the Shippingport Atomic Power Station. The elements required for a successful ALARA program are discussed along with examples of good ALARA practices. The Shippingport Atomic Power Station (SAPS) was the first commercial nuclear power plant to be built in the United States. It was located 35 miles northwest of Pittsburgh, PA on the south bank of the Ohio river. The reactor plant achieved initial criticality in December 1959. During its 25-year life, it produced 7.5 billion kilowatts of electricity. The SAPS was shut down in October 1982 and was the first large-scale U.S. nuclear power plant to be totally decommissioned and the site released for unrestricted use. The Decommission Project was estimated to take 1,007 man-rem of radiation exposure and $.98.3 million to complete. Physical decommissioning commenced in September 1985 and was completed in September 1989. The actual man-rem of exposure was 155. The project was completed 6 months ahead of schedule at a cost of $91.3 million.

  20. Vandellos 1 NPP decommissioning feedback experience

    International Nuclear Information System (INIS)

    Fernandez, Rodriguez A.

    2003-01-01

    The Vandellos 1 Nuclear Power Plant (CNV1) is located on the Mediterranean coast in the province of Tarragona (Spain). The Plant is of the European Natural Uranium Graphite-Gas type. The thermal power of the plant amounts to 1,670 MWt, its electrical output being 500 Mwe. The Plant started-up commercial service in May 1972; its final shutdown, due to a fire in the turbines, occurred in October 1989, after 17 years of operation with an accumulated energy production of 55,647 GWh. The option of decommissioning accepted by the Ministry of Industry, consists of first removing the spent fuel and conditioning the operating radioactive wastes, and then undertaking dismantling of almost all the structures and components located outside the reactor vessel, except those ensuring confinement of the vessel itself and the safety and surveillance of the facility and site. No action will be taken with respect to the vessel, in which the reactor will remain confined without nuclear fuel and with its internal components intact until completion of the waiting (dormancy) period. The site itself will be kept under surveillance during dormancy phase, following partial clearance, the remaining installations being left within the new site perimeter in a situation of monitored confinement. Following the dormancy period, which will last some 30 years, total dismantling of the remaining installations will be undertaken, this implying subsequent complete clearance of the site. The project was started in November of 1992, and the works on site began in 1998. The safe enclosure consists only in the reactor pressure vessel, which will be left on site. The activity content of the vessel is about 100 000 Ci, mostly Co 60. Part of the Stage 2 concept is the total static isolation of this vessel. The vessel has 1 700 penetrations, the pipes of which were cut, seal-welded and inspected. After five years of works in Vandellos 1 NPP decommissioning, ENRESA has an experience and knowledge, that is

  1. 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

  2. Decommissioning: returning the Niederaichbach site to nature

    International Nuclear Information System (INIS)

    Krieger, F.; Obst, J.

    1985-01-01

    The German Niederaichbach plant is expected to be the first reactor in Western Europe to be returned to a green-field site. A remote-controlled cutting and handling system, developed to carry out the decommissioning is described. The dismantling procedure and the project status are outlined. (author)

  3. Decommissioning of the Northrop TRIGA reactor

    International Nuclear Information System (INIS)

    Cozens, George B.; Woo, Harry; Benveniste, Jack; Candall, Walter E.; Adams-Chalmers, Jeanne

    1986-01-01

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

  4. Decontamination and decommissioning focus area. Technology summary

    International Nuclear Information System (INIS)

    1995-06-01

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

  5. MODELLING OF NUCLEAR POWER PLANT DECOMMISSIONING FINANCING

    Czech Academy of Sciences Publication Activity Database

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

    2015-01-01

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

  6. CECP, Decommissioning Costs for PWR and BWR

    International Nuclear Information System (INIS)

    Bierschbach, M.C.

    1997-01-01

    1 - Description of program or function: The Cost Estimating Computer Program CECP, designed for use on an IBM personal computer or equivalent, was developed for estimating the cost of decommissioning boiling water reactor (BWR) and light-water reactor (PWR) power stations to the point of license termination. 2 - Method of solution: Cost estimates include component, piping, and equipment removal costs; packaging costs; decontamination costs; transportation costs; burial volume and costs; and manpower staffing costs. Using equipment and consumables costs and inventory data supplied by the user, CECP calculates unit cost factors and then combines these factors with transportation and burial cost algorithms to produce a complete report of decommissioning costs. In addition to costs, CECP also calculates person-hours, crew-hours, and exposure person-hours associated with decommissioning. 3 - Restrictions on the complexity of the problem: The program is designed for a specific waste charge structure. The waste cost data structure cannot handle intermediate waste handlers or changes in the charge rate structures. The decommissioning of a reactor can be divided into 5 periods. 200 different items for special equipment costs are possible. The maximum amount for each special equipment item is 99,999,999$. You can support data for 10 buildings, 100 components each; ESTS1071/01: There are 65 components for 28 systems available to specify the contaminated systems costs (BWR). ESTS1071/02: There are 75 components for 25 systems available to specify the contaminated systems costs (PWR)

  7. Decommissioning technology development for research reactors

    International Nuclear Information System (INIS)

    Lee, K. W.; Kim, S. K.; Kim, Y. K.

    2004-03-01

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

  8. Financing strategies for nuclear power decommissioning

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1980-07-01

    The report analyzes several alternatives for financing the decommissioning of nuclear power plants from the point of view of assurance, cost, equity, and other criteria. Sensitivity analyses are performed on several important variables and possible impacts on representative companies' rates are discussed and illustrated.

  9. 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.

  10. Case study - Argentina

    International Nuclear Information System (INIS)

    Diaz, E.

    1986-01-01

    Antecedents and experience of nuclear activities in Argentina; the Atomic Energy Commission (CNEA). First development and research activities. Research reactors and radioisotopes plants. Health physics and safety regulations. - Feasibility studies for the first nuclear power plant. Awarding the first plant CNA I (Atucha I). Relevant data related to the different project stages. Plant performance. - Feasibility study for the second nuclear power plant. Awarding the second plant CNE (Central Nuclear Embalse). Relevant data related to established targets. Differences compared with the first station targets. Local participation. Plant performance. (orig./GL)

  11. The value of a mature, stable, and transparent regulatory framework in facilitating ER programs lessons learned in decommissioning of uranium recovery and other facilities in the USA - 59411

    International Nuclear Information System (INIS)

    McConnell, Keith I.; Camper, Larry

    2012-01-01

    Document available in abstract form only. Full text of publication follows: The history of decommissioning activities in the United States has demonstrated the value of a mature, stable and transparent regulatory framework in facilitating the timely completion of environmental remediation. Two examples are given as case studies. The first example relates to the history of uranium concentrate (yellowcake) production in the U.S. to support the initial development of civilian nuclear power in the U.S. in the 1950's, 60's, 70's and 80's. This yellowcake production, which took place mostly in the western U.S., was undertaken before laws and regulations to prevent contamination and protect public health and safety were fully developed. Significant contamination occurred in terms of both surface and ground water contamination. Although most conventional mills producing uranium during these early years entered decommissioning in the 70's and 80's, the vast majority are still remediating their sites because of persistent contamination in ground water. Had an effective regulatory framework been in place, much of this contamination would have been prevented and remediation accomplished more effectively. In contrast to this experience, a second example is provided related to development of the regulatory framework for decommissioning of non-uranium recovery facilities in the U.S. in the late 1990's and early 2000's

  12. A Case Study

    African Journals Online (AJOL)

    user

    Lacks of investment make it difficult for women to earn a living from agriculture. Financially independence of ... 2 Associate Professor; St. Mary's University College; School of Graduate. Studies;Eylachewz@yahoo.com .... lies within 0.5 degree north latitude and 39 degree longitude along the Addis. Ababa Gojjam road.

  13. A Psychobiographical Case Study

    African Journals Online (AJOL)

    but, due to the impact of this, the social world. The study ..... This academic dissertation, by Ndoro (2014), was undertaken in partial fulfilment of the requirements for a Master of Business. Administration (MBA) at a South African university business school ..... era) may thus have precipitated Jobs's marijuana use. (Schlender ...

  14. Risk Assessment Strategy for Decommissioning of Fukushima Daiichi Nuclear Power Station

    Directory of Open Access Journals (Sweden)

    Akira Yamaguchi

    2017-03-01

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

  15. Risk assessment strategy for decommissioning of Fukushima Daiichi Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

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

    2017-03-15

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

  16. Case Study: Shiraz Women

    Directory of Open Access Journals (Sweden)

    Bijan Khajehnoori

    2011-04-01

    Full Text Available This study investigated the relationship between lifestyle which seems as a scale of globalization process with body image. Required data was collected by systematic random sampling among 508 women in Shiraz. Based on existing theories and studies theoretical framework has constituted based on Giddens theory. Six hypotheses have been established. For collecting information, survey method and self reported questionnaire were used. In data analysis and explanation, multiple regression and unilateral dispersion analyses were used. The result showed that among effective factors on body image, modern musical lifestyle, religious' lifestyle, leisure lifestyle and participative lifestyle explained 23 percent of variations of body image. Among these variables, only religious lifestyle had negative relationship with body image and other variables had positive relationship with dependant variable.

  17. Case study: Tourism marketing

    OpenAIRE

    Kennell, James

    2014-01-01

    Tourism can be a challenging subject for students because it is both dynamic and susceptible to economic turbulence and shifts in trends. Tourism: A Modern Synthesis is an essential textbook for tourism students looking for a clear and comprehensive introduction to their studies which helps overcome these challenges. The authors apply a strong business approach to the subject reflecting developments in the teaching and content of modern courses and the text covers both key principles and cont...

  18. Decommissioning of the Plutonium Purification and Residues Recovery Plant

    International Nuclear Information System (INIS)

    Hunt, J. G.

    2006-01-01

    , despite challenging criticality and radiological hazards. With Phase 2 decommissioning nearing completion, work has commenced on Phase 3 to define and deliver the final phases of work that will lead to the complete remediation of this highly contaminated building. This work will include the development of fit for purpose engineering solutions linked to reliable and innovative safety cases to enable accelerated: - Removal of the highly contaminated redundant ventilation system, - Removal of the process cell structure which consists of contaminated brick, concrete and steel, - Remediation of the Low Active drain trench, - Demolition or recovery of the building structure. (authors)

  19. European Nuclear Decommissioning Training Facility II

    International Nuclear Information System (INIS)

    Demeulemeester, Y.

    2005-01-01

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

  20. Case Study: Derechos Digitales

    Directory of Open Access Journals (Sweden)

    Cameron Neylon

    2017-10-01

    Full Text Available Derechos Digitales is a Latin American advocacy and research network focussed on freedom on the internet, privacy and copyright reform. For the pilot project a specific IDRC funded project was the notional focus of study. However in practice the effort for considering data sharing was aimed at being organisation wide. The organisation already shares reports and other resources (particularly images and infographics by default. While open data was described as being “in the DNA of the organisation” there was little practice across the network of sharing preliminary and in-process materials. Some aspects of data collection on research projects, particularly to do with copyright and legal issues, have significant privacy issues and as the organisation focuses on privacy as one of its advocacy areas this is taken very seriously. Many materials from research projects are not placed online at all. Derechos Digitales run distributed projects and this creates challenges for consistent management. Alongside this the main contact at DD changed during the course of the pilot. This exchange exemplified the challenges of maintaining organisational systems and awareness through a personnel change.

  1. Case study: Khoramdareh County

    Directory of Open Access Journals (Sweden)

    Vahid Riahi Riahi

    2016-10-01

    Full Text Available Environmental sustainability of rural settlements based on a systematic viewpoint may be defined as a realization of sustainable development in different social, economic and environmental aspects of rural areas. Achieving this goal requires that we pay more attention to effective elements and factors through a set of sustainability indices. This research was meant to analyze sustainable factors of rural settlement in three dimensions: environmental, social and economic context using multi-criteria decision analysis and explanation of the relationships between its active and effective factors in the rural area of the Khorramdarreh County in the province of Zanjan. The research method used is the descriptive analytic approach. Data from 287 households were sampled randomly from a total of 1143 households in the four villages including: Rahmat Abad, Alvand, Baghdareh and, Sukhariz (out of 15 villages in the Khorramdarreh County. In the process of doing this research and after calculating the weights, the difference in the sustainability of environmental, social, economic and physical aspects in rural areas of this county have been determined. Data was collected using library and field research through questionnaires. Data analysis was performed by the One-Sample t Test and the Vikur and path analysis techniques, using statistical software SPSS. The findings show that environmental sustainability in the study area is half desirable. Among the different aspects of environmental sustainability, the most effective factors are physical, economic, social and environmental aspects, respectively. Little attention of policy-making –system to socio-cultural and environmental aspects, especially in practice, and rapid and unplanned utilization of production resources are the most important factors affecting this situation in two given dimensions. Although, in programmed documents the planning system agents emphasize on the socio-cultural sustainability

  2. Final report on case studies

    DEFF Research Database (Denmark)

    Ljungberg, Daniel; McKelvey, Maureen; Lassen, Astrid Heidemann

    2012-01-01

    Case study as a research design means investigating a single or multiple instance(s) or setting(s) (i.e. a case) and its entire context to explain a phenomenon and its processes. This is achieved through detailed understanding, usually comprised of multiple sources of information. In this way, ca...

  3. PUREX transition project case study

    International Nuclear Information System (INIS)

    Jasen, W.G.

    1996-01-01

    In December 1992, the US Department of Energy (DOE) directed that the Plutonium-Uranium Extraction (PUREX) Plant be shut down and deactivated because it was no longer needed to support the nation's production of weapons-grade plutonium. The PUREX/UO 2 Deactivation Project will establish a safe and environmentally secure configuration for the facility and preserve that configuration for 10 years. The 10-year span is used to predict future maintenance requirements and represents the estimated time needed to define, authorize, and initiate the follow-on decontamination and decommissioning activities. Accomplishing the deactivation project involves many activities. Removing major hazards, such as excess chemicals, spent fuel, and residual plutonium are major goals of the project. The scope of the PUREX Transition Project is described within

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

    International Nuclear Information System (INIS)

    Leibundgut, Fritz

    2017-01-01

    Paul Scherrer Institute is the largest research institute for natural and engineering science in Switzerland. It operated various nuclear facilities from 1960 to 2011: Research reactors DIORIT, SAPHIR and PROTEUS, and an incineration plant for low and medium level radioactive waste. Concerning SAPHIR research reactor: in operation from 1958 to 1993, planning of decommissioning from 1998 to 2000. Decommissioning work started in 2004. Finishing is planned for 2019. Concerning DIORIT research reactor: operation as DIORIT I (20 MWth) from 1960 to 1967, then reconstruction to DIORIT II (30 MWth) and operation from 1970 until 1977. Planning of decommissioning from 1992 to 1994. Decommissioning work started in 1994 and was finished in 2012. Concerning PROTEUS research reactor: in operation from 1966 to 2011. Planning of decommissioning from 2013 to 2014. Starting of decommissioning work is planned for 2017, finishing is planned for the end of 2018 Incineration plant: In operation from 1974 to 2002. Planning of decommissioning from 2011 to 2012. Starting of decommissioning work in 2016. Finishing planned for end of 2019. Treatment of various material categories from dismantling: Concerning aluminum: because of the production of H 2 during solidification in concrete, it was necessary to minimize the surface area. When dismantling research reactors, the aluminum removed was melted in an induction furnace and poured into a 4.5 m 3 concrete container to solidify. Cutting the metal and handling it was largely accomplished remote control, using conventional technology. Concerning Steel/Cast-iron: the storage containers to be filled determined the method used for reducing the size of these materials, and the technique used for handling them. The goal was to optimize the packing density to reduce repository costs. The selected method of reducing the size of components is to cut them up using diamond-tipped tools, like saw blades. Concerning Graphite: for graphite, grinding was the

  5. Optimization study and preliminary design for Latina NPP early core retrieval and reactor dismantling

    International Nuclear Information System (INIS)

    Macci, E.; Zirpolo, S.; Imparato, A.; Cacace, A.; Parry, D.; Walkden, P.

    2002-01-01

    In June 2000, an agreement was established between Sogin and BNFL to enable the two companies to co-operate, using their specific experiences in the decommissioning field, for the benefit of projects in Italy, the United Kingdom and for third markets. A decommissioning strategy for the Latina NPP was initially developed in a Phase 1 Study which produced a conceptual design for the decommissioning of the reactor. This study was completed in June 2000. Since then, a second study has been completed, which has further developed the strategy and produced preliminary designs for the early dismantling of the core and reactor building at Latina. The engineering and safety data were produced in order to support Sogin in the preparation of a safety case for plant decommissioning. This safety case was submitted to the Italian Regulator, ANPA, in February 2002. (author)

  6. Site release in the decommissioning of nuclear installations

    International Nuclear Information System (INIS)

    Revilla, Jose Luis; Sanz, Maria Teresa; Marugan, Inmaculada; Simon, Inmaculada; Martin, Manuel; Solis, Susana; Sterling, Agustina

    2008-01-01

    Spanish regulatory framework for the decommissioning process of a nuclear facility ends up with a decommission statement, which releases the licence-holder of the facility from its responsibilities as an operator. It also establishes -where a restricted site release applies- the appropriate future use restrictions, and the responsible of both maintaining such restrictions and ensuring their compliance. Releasing a site implies eliminating all radiological monitoring. The Regulations, however, did not specify either the radiological conditions to be met for the site to be released, or the possibility of a partial release -with or without restrictions-. In case of restricted site release, the Regulations did not specify either the required criteria for such a release. This paper presents the main features of the Safety Instruction IS-13 'Radiological criteria for the release of nuclear facilities sites' issued recently by the Spanish Nuclear Safety Council as a new specific regulation. This Safety Instruction establishes the requirements and conditions for the release of nuclear facility sites, that is, radiological criteria on the effective dose to the public, partial release of nuclear facility sites and restricted release of nuclear facility sites. (author).

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

    International Nuclear Information System (INIS)

    Harriague, S.; Barberis, C.; Cinat, E.; Grizutti, C.; Scolari, H.

    2007-01-01

    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)

  8. Financial provisions for decommissioning and disposal: the operators' view

    International Nuclear Information System (INIS)

    Mueller-Dehn, C.

    2008-01-01

    The German system of making provisions for nuclear power has been the subject of frequent examinations, and has been approved in each case - by the German federal government, the European Commission, the Court of First Instance of the European Communities and, recently, also by the European Court of Justice. The article describes the basic legal principles entailing the obligation to make financial provisions for decommissioning and disposal by setting aside the required funds in line with current practice. The management of the assets balancing the provisions, the system of controls, the economic strength of the firms involved and, especially, the demand for the product they sell, i.e. electricity, ensure permanent availability of these funds. Numerous subsidiary legal provisions ensure transparency of these financial provisions. The external fund model analyzed as an alternative is the rejected both on account of drawbacks in its contents and for legal reasons. Attention is paid to the recommendation by the European Commission of October 2006 about financial provisions for decommissioning and disposal, to which the German system conforms and which does not require the establishment of external funds either. As the system of financial provisions has been operated successfully and reliably in Germany since the beginnings of the use of nuclear power, a plea is made in favor of upholding its structures and functions. (orig.)

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

    International Nuclear Information System (INIS)

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

    1982-03-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1982-03-01

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

  11. SOGIN Decommissioning strategy and funding (Italy)

    International Nuclear Information System (INIS)

    2006-01-01

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

  12. Release from control of inactive material from decommissioning the ASTRA research reactor

    International Nuclear Information System (INIS)

    Brandl, A.; Hrnecek, E.; Steger, F.; Kurz, H.; Meyer, F.; Karacson, P.

    2003-01-01

    The Austrian Research Centers Seibersdorf have been operating a 10 MW ASTRA research reactor from 1960 until 1999. After that date, a submission of the intention to decommission the reactor has been provided to the Competent Authorities. After completion of an Environmental Impact Study by the Competent Authorities and modification of the Permissions for Site Use, the reactor finally entered the decommissioning phase in 2003. Inactive materials from the decommissioning site are expected to be released from control. The procedure for such a release from control agreed upon between the Competent Authorities and ARC Seibersdorf involves a four-step measurement, verification, and certification process detailed in this paper. By September 2003, this four-step procedure has been completed for 16500 kg of steel re-enforced concrete and for 5500 kg of other materials; the release from control of 3000 kg of paraffin and 10000 kg of graphite from the thermal column are planned for the near future. (author)

  13. Computer-aided decommissioning engineering system with 3D-CAD for JAERI's reprocessing test facility

    International Nuclear Information System (INIS)

    Tanaka, Kazuo; Aoki, Noriko; Mimori, Takeo; Iwasaki, Yukio

    1995-01-01

    We introduce the 3D-CAD system for the decommission engineering of JRTF, JAERI's Reprocessing Test Facility in Tokai Laboratories. The development of this system has been carried out under the contract with the Science and Technology Agency. Several computer simulations of the cutting process and evaluation in advance of the volume of waste are useful method to estimate the decommissioning procedure of JRTF effectively and precisely. To apply these method, we constructed the 3D-CAD data for the part of JRTF and have developed the several functions by use of the 3D-CAD system for plant design system. We will apply these data and system to the study of decommissioning procedure to promote the precision and the efficiency. (author)

  14. HYDROGEOLOGIC CASE STUDIES (DENVER PRESENTATION)

    Science.gov (United States)

    Hydrogeology is the foundation of subsurface site characterization for evaluations of monitored natural attenuation (MNA). Three case studies are presented. Examples of the potentially detrimental effects of drilling additives on ground-water samples from monitoring wells are d...

  15. HYDROGEOLOGIC CASE STUDIES (CHICAGO, IL)

    Science.gov (United States)

    Hydrogeology is the foundation of subsurface site characterization for evaluations of monitored natural attenuation (MNA). Three case studies are presented. Examples of the potentially detrimental effects of drilling additives on ground-water samples from monitoring wells are d...

  16. Hydrogeologic Case Studies (Seattle, WA)

    Science.gov (United States)

    Hydrogeology is the foundation of subsurface site characterization for evaluations of monitored natural attenuation (MNA). Three case studies are presented. Examples of the potentially detrimental effects of drilling additives on ground-water samples from monitoring wells are d...

  17. Case Study: Bangladesh Bank Heist

    OpenAIRE

    Md Ahsan Habib

    2017-01-01

    Cyber crime is a threat to our E- commerce . A hacker group named "Lazarus" hacked $951 million from Bangladesh Bank's account. This is the short case study of this incident with professional ethical view.

  18. NMSS handbook for decommissioning fuel cycle and materials licensees

    International Nuclear Information System (INIS)

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

    1997-03-01

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

  19. NMSS handbook for decommissioning fuel cycle and materials licensees

    Energy Technology Data Exchange (ETDEWEB)

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

    1997-03-01

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

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

    International Nuclear Information System (INIS)

    1998-04-01

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