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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.
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.
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management -- Second Report
Canadian National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management -- Second Report
This is Canada's Second National Report and it demonstrates how Canada continues to meet its obligations under the terms of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The main aspect addressed in this report is the progress on initiatives for the long-term management of spent fuel and radioactive waste in Canada. This report also includes information on Canada's systematic monitoring programs and their implementation and addresses specific topics raised at the First Review Meeting.
Public Draft - National Plan for Siting High-Level Radioactive Waste Repositories and Environmental Assessment
Public Draft - National Plan for Siting High-Level Radioactive Waste Repositories and Environmental Assessment
The National Plan for Siting High-Level Radioactive Waste Repositories describes the process the Department of Energy (DOE) is using to find sites suitable for disposal of high-level radioactive waste.
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.
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.
Waste Isolation Projects - FY 1977
Waste Isolation Projects - FY 1977
The primary goal of the ongoing LLL program is to develop the technology and data base required to license a nuclear repository in a crystalline rock medium, located at or near the Nevada Test Site (NTS). Our secondary goal is to apply this technology in helping the Department of Energy (DOE) develop repositories in other media and locations.
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.
WIPP Chronology
WIPP Chronology
Identifying remaining socio-technical challenges at the national level: Belgium
Identifying remaining socio-technical challenges at the national level: Belgium
This report is part of the research project International Socio-Technical Challenges for Implementing Geological Disposal: InSOTEC (see www.insotec.eu), funded by the European Commission under the Seventh Framework Programme.<br/>This report is a contribution to Work Package 1 of the project, which aims to identify the most significant socio-technical challenges related to geological disposal of radioactive waste. To achieve this objective, a comparative analysis of 14 national programmes will be performed.
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).
Annual Report 2010 on Radiation and Nuclear Safety in the Republic of Slovenia
Annual Report 2010 on Radiation and Nuclear Safety in the Republic of Slovenia
In 2010, there were no events that posed a serious radiological threat to the population in Slovenia. There were also no particularities in relation to the services of radiation practices and operators of radiation facilities.
The Krško NPP operated without shutdowns and production was interrupted only for the annual outage. In 2010, the power plant produced 5.7 TWh in total and achieved 89.9% availability. The nuclear power plant had no major problems during the September floods, when the Sava river otherwise seriously threatened settlements in Posavje.
Public Meetings on Nuclear Waste Management: Their Function and Organization
Public Meetings on Nuclear Waste Management: Their Function and Organization
This report focuses on public meetings as a vehicle for public participation in nuclear waste management. The nature of public meetings is reviewed and the functions served by meetings highlighted. The range of participants and their concerns are addressed, including a review of the participants from past nuclear waste management meetings. A sound understanding of the expected participants allows DOE to tailor elements of the meeting, such as notification, format, and agenda to accommodate the attendees.
Recovering Public Trust and Confidence in Managing Radioactive Waste
Recovering Public Trust and Confidence in Managing Radioactive Waste
The director of the Task Force on Civilian Radioactive Waste Management of the Secretary of Energy Advisory Board, United States Department of Energy, asked the National Academy of Public Administration, to convene a group of approximately one dozen individuals to attend a twoday "state-of-the-art" workshop on the issue of how institutions establish, maintain, or recover trust and confidence among significant members of their task environments.
Public Perceptions of Industrial Risks: The Context of Public Attitudes Toward Radioactive Waste
Public Perceptions of Industrial Risks: The Context of Public Attitudes Toward Radioactive Waste
The generation of knowledge regarding public risk perception general, and perception of risks associated with nuclear power and radioactive waste management in particular, requires the development and use of appropriate survey methodologies. One of the fundamental limitations of many studies of public risk perception is the assumption on the part of the investigators of similarity between themselves and their respondents. In such studies respondents are required to deal with problems of interest to and structured by the investigators.
10 CFR Part 963 - Yucca Mountain Site Suitability Guidelines
10 CFR Part 963 - Yucca Mountain Site Suitability Guidelines
MRS Role in Reducing Technical Uncertainties in Geologic Disposal
MRS Role in Reducing Technical Uncertainties in Geologic Disposal
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.
Slides - Lessons Learned from US Nuclear Waste Repository Programs
Slides - Lessons Learned from US Nuclear Waste Repository Programs
Presented to the Blue Ribbon Commission on America's Nuclear Future Subcommittee on Disposal
INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - English River First Nation, Saskatchewan
INITIAL SCREENING FOR SITING A DEEP GEOLOGICAL REPOSITORY FOR CANADA'S USED NUCLEAR FUEL - English River First Nation, Saskatchewan
On September 13, 2010, the English River First Nation expressed interest in learning more about the Nuclear Waste Management Organization (NWMO) site selection process to find an informed and willing community to host a deep geological repository for Canada’s used nuclear fuel (NWMO, 2010). This report summarizes the findings of an initial screening, conducted by Golder Associates Ltd., to evaluate the potential suitability of thirteen English River First Nation reserve areas against five screening criteria using readily available information.
Spent-Fuel Test - Climax: An Evaluation of the Technical Feasibility of Geologic Storage of Spent Nuclear Fuel in Granite
Spent-Fuel Test - Climax: An Evaluation of the Technical Feasibility of Geologic Storage of Spent Nuclear Fuel in Granite
This summary volume outlines results that are covered in more detail in the final report of the Spent-Fuel Test-Climax project. The project was conducted between 1978 and 1983 in the granite Climax stock at the Nevada Test Site. Results indicate that spent fuel can be safely stored for periods of years in this host medium and that nuclear waste so emplaced can be safely retrieved. We also evaluated the effects of heat and radiation (alone and in combination) on emplacement canisters and the surrounding rock mass.