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Transparency and Public Participation in Radioactive Waste Management: RISCOM II Final report
Transparency and Public Participation in Radioactive Waste Management: RISCOM II Final report
Long-term radioactive waste management (RWM) involves large and long-term research and development programmes in essentially all countries with civil nuclear programmes. Such programmes develop through different phases from basic research to more focussed applied research and development (R&D) and finally to the design and siting of proposed solutions. Internationally basic principles for the conduct of these programmes, basic safety principles and guidance on how to comply with them have largely been agreed upon.
Swedish Nuclear Waste Efforts
Swedish Nuclear Waste Efforts
The 1976 Parliamentary election in Sweden resulted in a coalition government which imposed extremely stringent requirements for the waste produced by Swedish nuclear power plants. The industry responded with a crash study, the Nuclear Fuel Safety (KBS) project, with experts drawn from hundreds of universities and related scientific institutions. A year later, the industry presented “a complete scheme for absolutely safe storage of nuclear waste” in engineered facilities located at about 500 m depth in the Swedish granite bedrock (KBS-I).
RD&D-Programme 98 Treatment and final disposal of nuclear waste Programme for research, development and demonstration of encapsulation and geological disposal
RD&D-Programme 98 Treatment and final disposal of nuclear waste Programme for research, development and demonstration of encapsulation and geological disposal
During the next few years, SKB will add the results of county studies and additional feasibility studies to the background data for siting of the deep repository. We plan to be able to choose at least two sites for site investigations in 2001. The investigations, which will include test drillings, should be able to be started in 2002. An important milestone will thereby be passed in the siting work.<br/><br/>The technology for deep disposal will be tested on full scale at our laboratories in Oskarshamn.
Treatment and final disposal of nuclear waste Programme for research, development, demonstration and other measures
Treatment and final disposal of nuclear waste Programme for research, development, demonstration and other measures
The goal of radioactive waste management in Sweden is to dispose of all radioactive waste products generated at the Swedish nuclear power plants in a safe manner. Furthermore, all other radioactive waste that arises in Sweden shall be safely disposed of. The Act on Nuclear Activities /1-1/ requires that the owners of the Swedish nuclear power plants adopt the measures that are needed to achieve this goal. The owners of the Swedish nuclear power plants have commissioned the Swedish Nuclear Fuel and Waste Management Company (SKB) to implement the measures that are needed.
TREATMENT AND FINAL DISPOSAL OF NUCLEAR WASTE: SUPPLEMENT TO THE 1992 PROGRAMME IN RESPONSE TO THE GOVERNMENT DECISION OF DECEMBER 16, 1993
Treatment and final disposal of nuclear waste: Programme for encapsulation, deep geological disposal, and research, development and demonstration: Ch 1 - 5
Treatment and final disposal of nuclear waste: Programme for encapsulation, deep geological disposal, and research, development and demonstration: Ch 1 - 5
In RD&D-Programme 92, SKB presented a partially new strategy for its activities. The new strategy entailed a focusing and concentration on the implementation of deep disposal of a limited quantity (about 800 tonnes) of encapsulated spent nuclear fuel during the coming 20-year period. Following this initial deposition, the results of the work will be evaluated, and only then will a decision be taken as to how and when regular deposition of the main body of the fuel and other long-lived nuclear waste will take place.
Site selection - Siting of the Final Repository for Spent Nuclear Fuel
Site selection - Siting of the Final Repository for Spent Nuclear Fuel
SKB has selected Forsmark as the site for the final repository for spent nuclear fuel. The site selection<br/>is the end result of an extensive siting process that began in the early 1990s. The strategy and<br/>plan for the work was based on experience from investigations and development work over a period<br/>of more than ten years prior to then.<br/>This document describes the siting work and SKB’s choice of site for the final repository.
RD&D-Programme 2001 Programme for research, development and demonstration of methods for the management and disposal of nuclear waste
RD&D-Programme 2001 Programme for research, development and demonstration of methods for the management and disposal of nuclear waste
The preceding RD&D-Programme from 1998 was supplemented in December 2000 by an integrated account of method, site selection and programme prior to the site<br/>investigation phase. Since the latter account lies close in time, SKB has chosen to<br/>concentrate RD&D-Programme 2001 on research and technology development. Viewpoints<br/>offered on previous RD&D-programmes and comments from the review of the<br/>SR 97 safety assessment comprise important input for RD&D-Programme 2001.
Integrated account of method, site selection and programme prior to the site investigation phase
Integrated account of method, site selection and programme prior to the site investigation phase
In order to dispose of the spent nuclear fuel in a safe manner, SKB plans to site<br/>a deep repository and an encapsulation plant with associated canister fabrication<br/>and transportation system. After an integrated evaluation of feasibility studies<br/>and other material, SKB will proceed with investigations of the rock and studies<br/>regarding establishment of the deep disposal system in the municipality of<br/>Oskarshamn or in Northern Uppland.
Handling and final disposal of nuclear waste. September 1989
Handling and final disposal of nuclear waste. September 1989
For those parts of the waste system that have already been taken into operation - transportation and handling systems, central interim storage facility for spent nuclear fuel (CLAB) and final repository for reactor waste (SFR)- the research and development stage has already largely been passed. The programme presented here therefore pertains primarily to the treatment and final disposal of spent fuel and the decommissioning of nuclear power plants.
Demonstration and Dialogue: Mediation in Swedish Nuclear Waste Management
Demonstration and Dialogue: Mediation in Swedish Nuclear Waste Management
This report analyses mediation and mediators in Swedish nuclear waste management. Mediation is about establishing agreement and building common knowledge. It is argued that demonstrations and dialogue are the two prominent approaches to mediation in Swedish nuclear waste management. Mediation through demonstration is about showing, displaying, and pointing out a path to safe disposal for inspection. It implies a strict division between demonstrator and audience.
Expansion of the Repository for Spent Nuclear Fuel: Environmental Impact Assessment Report
Expansion of the Repository for Spent Nuclear Fuel: Environmental Impact Assessment Report
Safety Case Plan
Safety Case Plan
Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy) Posiva is preparing to submit the construction license application for a spent fuel repository by the end of the year 2012. The long-term safety section supporting the license application is based on a safety case, which, according to the internationally adopted definition, is a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository.
Final Disposal of Spent Nuclear Fuel in Olkiluoto
Final Disposal of Spent Nuclear Fuel in Olkiluoto
Olkiluoto Site Description
Olkiluoto Site Description
This second version of the Olkiluoto Site Report, produced by the OMTF (Olkiluoto Modelling Task Force), updates the Olkiluoto Site Report 2004 (Posiva 2005) with the data and knowledge obtained up to December 2005.<br/>The main product of the modelling has been to develop a descriptive model of the site (the Site Descriptive Model), i.e. a model describing the geometry, properties of the bedrock and the water and the associated interacting processes and mechanisms.
Expert Judgement in Performance Assessment
Expert Judgement in Performance Assessment
Proposals to site, construct and operate a radioactive waste disposal facility in Sweden will be supported by performance assessments (PAs). Such PAs will require a range of expert judgements to be made. As part of SKI’s preparation for reviewing SKB’s Pas and for conducting independent PAs, SKI has identified a need for further research on the treatment of expert judgement in PA.
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Kivetty Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Kivetty Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Kivetty.
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Olkiluoto Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Olkiluoto Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Olkiluoto.
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Romuvaara Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Romuvaara Site Report
Posiva Oy is studying the Finnish bedrock for the geological disposal of spent nuclear fuel. The study is based on the site selection research programme started originally in 1983. The programme is in accordance with the decision in principle by the Council of State in 1983 and aims at the selection of one site in 2000. Four sites, Hastholmen in Loviisa, Kivetty in Aanekoski, Olkiluoto in Eurajoki and Romuvaara in Kuhmo, have been studied in detail. This report summarises the results of the site investigations carried out at Romuvaara.
Interim Summary Report of the Safety Case
Interim Summary Report of the Safety Case
The report outlines the current design and safety concept for the planned repository. It summarises the approach used to formulate scenarios for the evolution of the disposal system over time, describes these scenarios and presents the main models and computer codes used to analyse them. It also discusses compliance with Finnish regulatory requirements for long-term safety of a geological repository and gives the main evidence, arguments and analyses that lead to confidence, on the part of Posiva, in the long-term safety of the planned repository
The Final Disposal Facility for Spent Nuclear Fuel
The Final Disposal Facility for Spent Nuclear Fuel
Thorough long-term studies have shown that the Finnish bedrock is suitable for the permanent isolation of spent nuclear fuel from organic nature. Legislation requires that besides safety, an assessment be made of any other environmental impacts of the final disposal facility. Environmental impact assessment (EIA) in respect of the final disposal facility for spent nuclear fuel got under way in 1997 when Posiva Oy, which is responsible for the project, began work on an EIA programme.
Posiva Annual Report
Posiva Annual Report
Main events Licensing process proceeds according to plan Posiva aims to submit the construction license application in 2012. In 2011, research and analysis work continued to ensure the timely availability of results and related reports. The feedback provided by the Radiation and Nuclear Safety Authority and other authorities for the preliminary licensing documentation submitted in 2009 was systematically reviewed in 2011, and steps were taken to ensure it is taken into account during the license submission phase.
Public Values and Stakeholder Involvement - A New Framework for Performance Assessment
Public Values and Stakeholder Involvement - A New Framework for Performance Assessment
The objective of the RISCOM II project is to share the knowledge of the context of radioactive waste management in various European countries and to see to what extent it is possible to apply more widely the RISCOM Model (Andersson et al., 1998) in order to improve the acceptability of radioactive waste management. Thus, the project aims to promote the development of processes involving transparency, as well as means involving greater participation of the public.
Foreign Programs for the Storage of Spent Nuclear Power Plant Fuels, High-Level Waste Canisters and Transuranic Wastes
Foreign Programs for the Storage of Spent Nuclear Power Plant Fuels, High-Level Waste Canisters and Transuranic Wastes
Worldwide activities related to the storage of spent (irradiated) nuclear power reactor fuel and highly-radioactive, long-lived wastes are summarized, with a review of the storage programs and plans of 26 nations. The focus of the report is on the application of dry storage techniques to spent fuel, although dry storage of long-lived wastes is also reviewed.