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The BRIDGE
The BRIDGE
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.
Republic of Hungary National Report, Third Report, prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Republic of Hungary National Report, Third Report, prepared in the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The Republic of Hungary was among the first to sign the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereafter Convention), established under the auspices of the International Atomic Energy Agency, on 29 September 1997, and ratified it on 2 June 1998. The Convention was promulgated by Act LXXVI of 2001 [I.11].
Republic of Hungary National Report, Fourth Report, prepared within the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
Republic of Hungary National Report, Fourth Report, prepared within the Framework on the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (hereafter Convention) was promulgated by Act LXXVI of 2001 [I.11]. (Hereafter the references to legal instruments listed in Annex 4 are used by numbering in brackets.) In order to fulfill the obligations of Article 32 of the Convention the present National Report has been prepared and submitted.
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.
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.
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.
Structure for Transparency in Nuclear Waste Management
Structure for Transparency in Nuclear Waste Management
The purpose of this report is a comparison of the structures for nuclear waste management in France, Sweden and UK. The source materials for this comparison are studies carried out in each of these countries by Syncho Ltd. over the past 5 years. The Swedish structural review was sponsored by SKI and SSI, and carried out as a pilot study during the years 1996 and 1997 (Espejo & Gill, 1998) as part of the RISCOM I project.