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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.
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.
From Risk Analysis to the Safety Case. Values in Risk Assessments
From Risk Analysis to the Safety Case. Values in Risk Assessments
The foundation for work related to nuclear waste management is laid by laws and outlines e.g. the responsibilities of the reactor owners and the state, as represented by the authorities. The Swedish Nuclear Fuel and Waste Management Company (SKB), as well as Posiva Oy in Finland, were set up by the reactor owners in the respective countries in response to the responsibilities of planning, conducting research and to implement the physical structures leading to a safe management of nuclear wastes.
Review of initiatives addressing socio-technical challenges of RWM & geological disposal in international programmes
Review of initiatives addressing socio-technical challenges of RWM & geological disposal in international programmes
Reflecting on the Implementing Geological Disposal Technology Platform as a knowledge network and potential scenarios for stakeholder involvement
Reflecting on the Implementing Geological Disposal Technology Platform as a knowledge network and potential scenarios for stakeholder involvement
This report was prepared in the context of Work Package 3 of the InSOTEC project. The overall objective of this work package (WP) is to take a closer look at arenas where socio-technical combinations on radioactive waste management (RWM) are formed. The attempt is to illustrate the interconnections between the sources of different types of information and knowledge development with the various stakeholders having access to that information.
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Second Review Meeting, Joint Convention on the Safety of Spent Fuel Management on the Safety of Radioactive Waste Management, Answers to the Questions of Contracting Parties on the National Report submitted by Luxembourg
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 2 Ch 10 - 17
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 2 Ch 10 - 17
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.
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 3 Ch 18 -27
Geological Problems in Radioactive Waste Isolation Second Worldwide Review Part 3 Ch 18 -27
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.
Identifying remaining socio-technical challenges at the national level: France
Identifying remaining socio-technical challenges at the national level: France
France isn’t only a country known for its cheese… it’s also a country of nuclear power. With its 58 nuclear reactors (63,000 megawatts), producing 79% of the country’s electricity, France is arguably the world’s leader in the production of nuclear energy. It is estimated that the relative contribution of nuclear energy to power production in France will decline to 70% in 2020 - the main reason for this being governmental investments into renewable energies.
Performance Assessment, Participative Processes and Value Judgements: Report from the First RISCOM II Workshop
Performance Assessment, Participative Processes and Value Judgements: Report from the First RISCOM II Workshop
Articles of the Planning Act N¡. 2006-739 of 28 June 2006 Concerning the Sustainable Management of Radioactive Materials and Waste modifying the Environmental Code.
Articles of the Planning Act N¡. 2006-739 of 28 June 2006 Concerning the Sustainable Management of Radioactive Materials and Waste modifying the Environmental Code.
Frances Planning Act for Radioactive Materials and Waste
Quality of Decision-making Processes: Decision-making processes in Radioactive Waste Governance - Insights and Recommendations WP3
Quality of Decision-making Processes: Decision-making processes in Radioactive Waste Governance - Insights and Recommendations WP3
Work Package 3 (WP 3) set out to provide practical recommendations for the design and implementation of a “robust” decision-making process (DMP) in radioactive waste governance/governance of radioactive waste management (RWG).
Structuring local communities and development of local democracy for engagement in Radioactive Waste Management governance
Structuring local communities and development of local democracy for engagement in Radioactive Waste Management governance
The Cigéo Project: Meuse/Haute-Marne Reversible Geological Disposal Facility for Radioactive Waste
The Cigéo Project: Meuse/Haute-Marne Reversible Geological Disposal Facility for Radioactive Waste
Report prepared by ANDRA, the French National Radioactive Waste Management Agency, for preparing for public debate in 2013.
ANDRA presents the Actions to be Taken Following the Public Debate on the Cigéo Project
ANDRA presents the Actions to be Taken Following the Public Debate on the Cigéo Project
Press release from ANDRA, the French National Agency for Radioactive Waste Management, regarding the changes it will make in the siting process as a result of public debate on the Cigéo Project, disposal of radioactive waste in a deep geologic repository.
Act No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field
Act No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field
Text of the French Nuclear Safety and Transparency Act of 2006, translated into English.
Dossier 2005: ANDRA Research on the Geological Disposal of High-Level Long-Lived Radioactive Waste: Summary
Dossier 2005: ANDRA Research on the Geological Disposal of High-Level Long-Lived Radioactive Waste: Summary
A summary of ANDRA's research into disposal of radioactive waste in a deep geologic repository, examining both clay and granite.