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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.
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: 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.
Viewing Back End of Nuclear Fuel Cycles Synoptically and Comparatively
Viewing Back End of Nuclear Fuel Cycles Synoptically and Comparatively
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.
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.
Oak Ridge Waste Management Programs: Geologic Isolation and Actinide Partitioning
Oak Ridge Waste Management Programs: Geologic Isolation and Actinide Partitioning
There are two waste management R&D programs of national significance that are being administered for ERDA by the Union Carbide Corporation — Nuclear Division (UCC/ND). The National Waste Terminal Storage (NWTS) program is concerned with the development of geologic repositories for commercial nuclear fuel cycle wastes, and is organized as the Office of Waste Isolation within UCC/ND.
Report of the Peer review Panel on the Early Site Suitability Evaluation of the Potential Repository Site at Yucca Mountain, Nevada
Report of the Peer review Panel on the Early Site Suitability Evaluation of the Potential Repository Site at Yucca Mountain, Nevada
The U.S. Department of Energy (DOE) Yucca Mountain Site Characterization Project Office (YMPO) assigned Science Applications International Corporation (SAIC), the Technical and Management Support Services (T&MSS) contractor to the YMPO, the task of conducting an Early Site Suitability Evaluation (ESSE) of the Yucca Mountain site as a potential site for a high-level radioactive waste repository.
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.
10 CFR Part 60 - Disposal of High-Level Radioative Wastes in Geologic Repositories
10 CFR Part 60 - Disposal of High-Level Radioative Wastes in Geologic Repositories
REGION-TO-AREA SCREENING METHODOLOGY FOR THE CRYSTALLINE REPOSITORY PROJECT
REGION-TO-AREA SCREENING METHODOLOGY FOR THE CRYSTALLINE REPOSITORY PROJECT
The Crystalline Repository Project (CRP) of the Department of Energy's Civilian Radioactive Waste Management Program is responsible for identifying sites which could be considered by the Department for construction and operation of the second deep geologic repository for permanent disposal of high-level radioactive waste. The CRP is currently evaluating exposed and near surface crystalline rock bodies in three geographic regions in an effort to identify potentially suitable rock bodies for continued evaluations and eventual field investigations.
10 CFR Part 963 - Yucca Mountain Site Suitability Guidelines
10 CFR Part 963 - Yucca Mountain Site Suitability Guidelines
Regional Geological Assessment of the Devonian-Mississippian Shale Sequence of the Appalachian, Illinois, and Michigan Basins relative to Potential Storage/Disposal of Radioactive Wastes
Regional Geological Assessment of the Devonian-Mississippian Shale Sequence of the Appalachian, Illinois, and Michigan Basins relative to Potential Storage/Disposal of Radioactive Wastes
The thick and regionally extensive sequence of shales and associated clastic sedimentary rocks of Late Devonian and Early Mississippian age has been considered among the “nonsalt geologies” for deep subsurface containment of high-level radioactive wastes.
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.