Siting Experience Documents Only
Country
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Belgian Workshop (November 2003) - Executive Summary and International Perspective
Belgian Workshop (November 2003) - Executive Summary and International Perspective
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.
DELIBERATING TOGETHER ON GEOLOGICAL REPOSITORY SITING: EXPECTATIONS AND CHALLENGES IN THE CZECH REPUBLIC
DELIBERATING TOGETHER ON GEOLOGICAL REPOSITORY SITING: EXPECTATIONS AND CHALLENGES IN THE CZECH REPUBLIC
The 9th OECD Nuclear Energy Agency "Forum on Stakeholder Confidence" Community Visit and
National Workshop was held in Karlovy Vary, Chyše and Blatno in the Czech Republic in October 2012.
Entitled "Deliberating Together on Geological Repository Siting", the workshop focussed on the process
for siting an installation for the final management of spent nuclear fuel, and the expectations and
challenges raised by this process. Three themes were examined: developing confidence in a participatory
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.
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report
Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, Czech Republic National Report
This report is the National Report submitted by the Czech Republic for the purposes of assessment meeting of the parties to the Joint Convention. Its objective is to describe the fulfillment status of obligations under the Joint Convention in the Czech Republic as on 31 December 2002. The outline of the National Report is based on recommendations approved at the preparatory meeting of the parties to the Joint Convention in December 2001 and contained in the „Guidelines regarding the form and structure of national reports (JC-SFRW/PREP/FINAL/DOCUMENT 3)“ of 13 December 2001.
Identifying remaining socio-technical challenges at the national level: Czech Republic
Identifying remaining socio-technical challenges at the national level: Czech Republic
This report describes the history, recent developments and the current situation of the management of highly radioactive waste and spent nuclear fuel in the Czech Republic, with a particular focus on the development of geological disposal for this kind of waste. Special attention is given to the interplay of social and technical aspects of the process. The first chapter gives an overview of the state of affairs and sketches out the trajectories leading to it.
Evaluation, testing and application of participatory approaches in the Czech Republic
Evaluation, testing and application of participatory approaches in the Czech Republic
Based on the review of experiences in SEA and EIA in the Czech Republic summarized in Deliverable No.3 and the testing of novel participatory and dialogue approaches summarized in Deliverables No.7, 11 and 12 in this report a model for the siting process specifically in the Czech Republic, that takes into account the need for transparency and interaction with the public, within the framework of legal requirements is outlined. Lessons learnt are summarised and a road map specified.
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
Technical overview of the SAFIR 2 report: Safety Assessment and Feasibility Interim Report 2
Technical overview of the SAFIR 2 report: Safety Assessment and Feasibility Interim Report 2
This document is the technical overview of the SAFIR 2 report that synthesises all of the technical and scientific knowledge available at the end of the second phase (1990–2000) of the ONDRAF/NIRAS programme of methodological research and development on the final disposal of category B and C waste in a poorly-indurated clay formation. The SAFIR 2 report will be handed over by ONDRAF/NIRAS to its supervisory Minister at the beginning of 2002, after publication approval by its Board of Directors.
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.
Council Directive 2011/70/EURATOM of 19 July 2011 establishing a Community framework for the responsible and safe management of spent fuel and radioactive waste
Council Directive 2011/70/EURATOM of 19 July 2011 establishing a Community framework for the responsible and safe management of spent fuel and radioactive waste
Council Directive 2011/70/EURATOM of 19 July 2011 establishing a Community framework for the responsible and safe management of spent fuel and radioactive waste
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.