Siting Experience Documents Only
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Keywords
Stakeholder Dialogue: Experience and Analysis
Stakeholder Dialogue: Experience and Analysis
The report begins with a consideration of the factors which have led to a growth in the use of dialogue processes, a clarification of key concepts and a classification of dialogue processes. A description of recent and current activities in Europe and North America is followed by discussion of the relationship of processes and contexts. This then leads to an identification of the key aims and evaluation criteria which will be used in the design of dialogue processes to be conducted in subsequent phases of the project.
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Hastholmen Site Report
Final Disposal of Spent Nuclear Fuel in Finnish Bedrock - Hastholmen 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 Hastholment.
Nuclear waste management from a local perspective: Reflections for a Better Governance Final Report
Nuclear waste management from a local perspective: Reflections for a Better Governance Final Report
During the 1990s, nuclear waste programmes in nearly every concerned country met many difficulties. Nuclear waste management was seen as a technical issue, and the local communities were only involved in the last stage of the decision-making process when almost all components of the decision were already fixed. The management of high level radioactive waste is now recognised as a complex decision-making process entailing technical, ethical, social, political and economic dimensions where no solution can be reached solely on the basis of technical considerations.
Socio-Technical Challenges to Implementing Geological Disposal: a Synthesis of Findings from 14 Countries
Socio-Technical Challenges to Implementing Geological Disposal: a Synthesis of Findings from 14 Countries
This report aims to clarify the dynamics of socio-technical challenges in the implementation of geological disposal (GD) for High Level Waste (HLW) and Spent Nuclear Fuel (SNF). Drawing on the 14 country reports produced within InSOTEC’s WP1 the synthesis focuses on socio-technical challenges that appear across national contexts. The synthesis report elucidates issues made visible through bringing together the analyses of different national contexts.
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 1 Ch 1 - 9
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 1 Ch 1 - 9
The first world wide review of the geological problems in radioactive waste isolation was published by Lawrence Berkeley National Laboratory in 1991. This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9-19,1989 in Washington, D.C.
Activities of WENRA-WGWD
Activities of WENRA-WGWD
Summary of National and International Radioactive Waste Management Programs 1979
Summary of National and International Radioactive Waste Management Programs 1979
Many nations and international agencies are working to develop improved technology and industrial capability for nuclear fuel cycle and waste management operations. The effort in some countries is limited to research in university laboratories on treating low-level waste from reactor plant operations.
The "COWAM SPAIN" Initiative and the Current Project Under Consideration for a National Interim Storage Facility for Spent Fuel and High Level Waste
Identifying remaining socio-technical challenges at the national level: Finland
Identifying remaining socio-technical challenges at the national level: Finland
This research report is part of the research programme International Socio-Technical Challenges for Implementing Geological Disposal (InSOTEC; see www.insotec.eu). The research programme is funded by the Seventh Framework Programme Theme [Fission-2010-1.1.2] [Research activities in support of implementation of geological disposal] (Grant agreement no: 269906).
Identifying remaining socio-technical challenges at the national level: Spain
Identifying remaining socio-technical challenges at the national level: Spain
On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision.
SITING PROCESS FOR A CENTRALISED STORAGE FACILITY (ATC) FOR SPENT FUEL AND HIGH LEVEL WASTE IN SPAIN
SITING PROCESS FOR A CENTRALISED STORAGE FACILITY (ATC) FOR SPENT FUEL AND HIGH LEVEL WASTE IN SPAIN
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.
Specific Design Principles for Deep Geological Repositories and Requirements for the Safety Case
Specific Design Principles for Deep Geological Repositories and Requirements for the Safety Case
The Swiss Federal Nuclear Safety Inspectorate (ENSI) is the regulatory authority for nuclear safety and security of the nuclear installations in Switzerland. ENSI issues guidelines either in its capacity as regulatory authority or based on a mandate in an ordinance. Guidelines are support documents that formalise the implementation of legal requirements and facilitate uniformity of implementation practices. They further concretise the state-of-the-art in science and technology.
Sectoral Plan for Deep Geological Repositories: Conceptual Part
Sectoral Plan for Deep Geological Repositories: Conceptual Part
The conceptual part of the sectoral plan for deep geological repositories defines the goals of the federal government in this area and the procedures and criteria to be applied in selecting sites for deep geological repositories for all categories of waste in Switzerland. The focus of the site selection process is on safetybased criteria, with land use and socio-economic aspects playing a secondary role.
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.
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.