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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.
Historical Relationship Between Performance Assessment for Radioactive Waste Disposal and Other Types of Risk Assessment in the United States
Historical Relationship Between Performance Assessment for Radioactive Waste Disposal and Other Types of Risk Assessment in the United States
This paper describes the evolution of the process for assessing the hazards of a geologic disposal system for radioactive waste and, similarly, nuclear power reactors, and the relationship of this process with other assessments of risk, particularly assessments of hazards from manufactured carcinogenic chemicals during use and disposal. This perspective reviews the common history of scientific concepts for risk assessment developed to the 1950s.
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 Programme for research, development, demonstration and other measures
Treatment and final disposal of nuclear waste Programme for research, development, demonstration and other measures
The goal of radioactive waste management in Sweden is to dispose of all radioactive waste products generated at the Swedish nuclear power plants in a safe manner. Furthermore, all other radioactive waste that arises in Sweden shall be safely disposed of. The Act on Nuclear Activities /1-1/ requires that the owners of the Swedish nuclear power plants adopt the measures that are needed to achieve this goal. The owners of the Swedish nuclear power plants have commissioned the Swedish Nuclear Fuel and Waste Management Company (SKB) to implement the measures that are needed.
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
First Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
First Slovenian Report under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The National Report on Fulfilment of the Obligations of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management is prepared in fulfilment of Slovenia’s obligation as a Contracting Party to this Convention.
This report was prepared by the Slovenian Nuclear Safety Administration. Contributions to the report were made by the Krško NPP, the Jožef Stefan Institute, the Agency for Radwaste Management, the Žirovski Vrh Uranium Mine and the Slovenian Radiation Protection Administration.
National Report of the Slovak Republic, June 2008
National Report of the Slovak Republic, June 2008
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.
Demonstration and Dialogue: Mediation in Swedish Nuclear Waste Management
Demonstration and Dialogue: Mediation in Swedish Nuclear Waste Management
This report analyses mediation and mediators in Swedish nuclear waste management. Mediation is about establishing agreement and building common knowledge. It is argued that demonstrations and dialogue are the two prominent approaches to mediation in Swedish nuclear waste management. Mediation through demonstration is about showing, displaying, and pointing out a path to safe disposal for inspection. It implies a strict division between demonstrator and audience.
Expansion of the Repository for Spent Nuclear Fuel: Environmental Impact Assessment Report
Expansion of the Repository for Spent Nuclear Fuel: Environmental Impact Assessment Report
Public Involvement in Radioactive Waste Management Decisions
Public Involvement in Radioactive Waste Management Decisions
This report analyzes public participation as a key component of this openness, one that provides a means of garnering acceptance of, or reducing public opposition to, DOE's radioactive waste management activities, including facility siting and transportation.
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.
Site Selection and Evaluation Studies of the Waste Isolation Pilot Plant (WIPP), Los Medanos, Eddy County, NM
Site Selection and Evaluation Studies of the Waste Isolation Pilot Plant (WIPP), Los Medanos, Eddy County, NM
Bedded-salt deposits of the Salado Formation have been selected for evaluation for a proposed Waste Isolation Pilot Plant (WIPP) to be located in Eddy County, NM, -26 mi east of Carlsbad, Site selection and evaluation studies that included geologic mapping, geophysical surveys, drilling, and resource appraisal were conducted over and under the prospective location. The lower portion of the Salado meets essential criteria for waste isolation. Beds chosen for waste storage lie 2074-2730 ft below the surface.