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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.
Radioactive Wastes: Publc Attitudes toward Disposal Facilities
Radioactive Wastes: Publc Attitudes toward Disposal Facilities
Although some observers have concluded that the technology required to assure safe disposal of nuclear wastes is currently available, others have expressed concern about the stability of the institutions that might be required to maintain the isolation of nuclear wastes. Questions about institutional stability and other factors associated with nuclear power and nuclear waste have been the subject of some study in public opinion research.
A Persepctive on U.S. Nuclear Waste Policies for the Last 40 Years
A Persepctive on U.S. Nuclear Waste Policies for the Last 40 Years
PUBLIC CONCERNS AND CHOICES REGARDING NUCLEAR WASTE REPOSITORIES
PUBLIC CONCERNS AND CHOICES REGARDING NUCLEAR WASTE REPOSITORIES
Survey research on nuclear power issues conducted in the late 1970s has determined that nuclear waste management is now considered to be one of the most important nuclear power issues both by the U.S. public and by key leadership groups. The purpose of this research was to determine the importance placed on specific issues associated with high-level waste disposal. In addition, policy option choices were asked regarding the siting of both low-level and high-level nuclear waste repositories.
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.
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.
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.
The BRIDGE
The BRIDGE
Geologic and Hydrologic Characterization and Evaluation of the Basin and Range Province Relative to the Disposal of High-level Radioactive Waste -- Part 2
Geologic and Hydrologic Characterization and Evaluation of the Basin and Range Province Relative to the Disposal of High-level Radioactive Waste -- Part 2
The U.S. Geological Survey's program for geologic and hydrologic evaluation of physiographic provinces to identify areas potentially suitable for locating repository sites for disposal of high-level nuclear wastes was announced to the Governors of the eight States in the Basin and Range Province on May 6, 1981. Representatives of Arizona, California, Idaho, New Mexico, Nevada, Oregon, Texas, and Utah, were invited to cooperate with the Federal Government in the evaluation process.
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.
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.
Handling and final disposal of nuclear waste. September 1986
Handling and final disposal of nuclear waste. September 1986
The Act on Nuclear Activities (SFS 1984:3) obligates the owners of the Swedish nuclear power plants to<br/>jointly prepare a comprehensive programme for the research and development work and other measures<br/>required for the safe management and disposal of the waste from nuclear power.<br/>For those parts of the waste system that have already been taken into operation or are under construction - transportation and handling systems, central interim storage facility for spent nuclear fuel (CLAB) and final repository for reactor waste (SFR) - the research and development st
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.
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.