Abstract
The purpose of this report is to outline the origin and development over the past 30 years (up to 2009) of the KBS-3 method proposed by the Swedish Nuclear Fuel and Waste Management Co (SKB) for final disposal of spent nuclear fuel. The KBS-3 method is based on three protective barriers. The spent nuclear fuel is encapsulated in impermeable copper canisters. The canisters are placed in crystalline basement rock at a depth of 400-700 metres, embedded in bentonite clay. After disposal the tunnels and rock caverns are sealed. The account does not claim to cover all parts of the extensive technical and scientific research and development work conducted by SKB in form of collecting data, refining methods and increasing process understanding. The report forms part of the background material which SKB has gathered as a basis for future applications regarding permits under the Environmental Code and the Nuclear Activities Act to build and operate facilities for encapsulation and final disposal of spent nuclear fuel. A prominent feature of the industrial development work on the final disposal of spent nuclear fuel has been an openness for a constant input of ideas and opinions from society and public bodies (the Government, national
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Citation Formats
None.
Development of the KBS-3 method. Survey of SKB's research programs and safety assessments, reviews by Government authorities and SKB's international research cooperation; Utvecklingen av KBS-3-metoden. Genomgaang av forskningsprogram, saekerhetsanalyser, myndighetsgranskningar samt SKB:s internationella forskningssamarbete.
Sweden: N. p.,
2010.
Web.
None.
Development of the KBS-3 method. Survey of SKB's research programs and safety assessments, reviews by Government authorities and SKB's international research cooperation; Utvecklingen av KBS-3-metoden. Genomgaang av forskningsprogram, saekerhetsanalyser, myndighetsgranskningar samt SKB:s internationella forskningssamarbete.
Sweden.
None.
2010.
"Development of the KBS-3 method. Survey of SKB's research programs and safety assessments, reviews by Government authorities and SKB's international research cooperation; Utvecklingen av KBS-3-metoden. Genomgaang av forskningsprogram, saekerhetsanalyser, myndighetsgranskningar samt SKB:s internationella forskningssamarbete."
Sweden.
@misc{etde_1004322,
title = {Development of the KBS-3 method. Survey of SKB's research programs and safety assessments, reviews by Government authorities and SKB's international research cooperation; Utvecklingen av KBS-3-metoden. Genomgaang av forskningsprogram, saekerhetsanalyser, myndighetsgranskningar samt SKB:s internationella forskningssamarbete}
author = {None}
abstractNote = {The purpose of this report is to outline the origin and development over the past 30 years (up to 2009) of the KBS-3 method proposed by the Swedish Nuclear Fuel and Waste Management Co (SKB) for final disposal of spent nuclear fuel. The KBS-3 method is based on three protective barriers. The spent nuclear fuel is encapsulated in impermeable copper canisters. The canisters are placed in crystalline basement rock at a depth of 400-700 metres, embedded in bentonite clay. After disposal the tunnels and rock caverns are sealed. The account does not claim to cover all parts of the extensive technical and scientific research and development work conducted by SKB in form of collecting data, refining methods and increasing process understanding. The report forms part of the background material which SKB has gathered as a basis for future applications regarding permits under the Environmental Code and the Nuclear Activities Act to build and operate facilities for encapsulation and final disposal of spent nuclear fuel. A prominent feature of the industrial development work on the final disposal of spent nuclear fuel has been an openness for a constant input of ideas and opinions from society and public bodies (the Government, national authorities, universities and other institutes of higher education, municipalities and various non-governmental organizations). The presentation sheds light on developments in a number of areas that are of central importance for safety in a KBS-3 repository. In SKB's RDandD Programme 2007, these areas go under the headings rock line, buffer line, canister line, backfilling line and closure line. Furthermore, attention has been given to issues related to the possible retrieval of deposited canisters, variants of KBS-3, deposition technology and safety assessment, as well as a number of interdisciplinary issues. The development of methods for the safety assessment has been an important part of the development of the KBS-3 method. The work with safety assessments has led to an improved understanding and knowledge of important processes in the repository over time and, as a consequence of this, new or improved methods for describing these processes. A detailed account of related issues would be relatively extensive, however, and has therefore not been included in this report. The following thematic breakdown is used in the report: - Waste management sequence and facilities. - Interim storage facility. - Encapsulation plant. - Final repository. - Buffer and backfill. - Buffer. - Backfill. - Canister. The development of each of these thematic areas is described with an emphasis on important changes that have occurred and the reasons for them. A summarizing picture is then provided of SKB's work with the development of methods for safety assessment, plus some facts concerning SKB's international research cooperation}
place = {Sweden}
year = {2010}
month = {Nov}
}
title = {Development of the KBS-3 method. Survey of SKB's research programs and safety assessments, reviews by Government authorities and SKB's international research cooperation; Utvecklingen av KBS-3-metoden. Genomgaang av forskningsprogram, saekerhetsanalyser, myndighetsgranskningar samt SKB:s internationella forskningssamarbete}
author = {None}
abstractNote = {The purpose of this report is to outline the origin and development over the past 30 years (up to 2009) of the KBS-3 method proposed by the Swedish Nuclear Fuel and Waste Management Co (SKB) for final disposal of spent nuclear fuel. The KBS-3 method is based on three protective barriers. The spent nuclear fuel is encapsulated in impermeable copper canisters. The canisters are placed in crystalline basement rock at a depth of 400-700 metres, embedded in bentonite clay. After disposal the tunnels and rock caverns are sealed. The account does not claim to cover all parts of the extensive technical and scientific research and development work conducted by SKB in form of collecting data, refining methods and increasing process understanding. The report forms part of the background material which SKB has gathered as a basis for future applications regarding permits under the Environmental Code and the Nuclear Activities Act to build and operate facilities for encapsulation and final disposal of spent nuclear fuel. A prominent feature of the industrial development work on the final disposal of spent nuclear fuel has been an openness for a constant input of ideas and opinions from society and public bodies (the Government, national authorities, universities and other institutes of higher education, municipalities and various non-governmental organizations). The presentation sheds light on developments in a number of areas that are of central importance for safety in a KBS-3 repository. In SKB's RDandD Programme 2007, these areas go under the headings rock line, buffer line, canister line, backfilling line and closure line. Furthermore, attention has been given to issues related to the possible retrieval of deposited canisters, variants of KBS-3, deposition technology and safety assessment, as well as a number of interdisciplinary issues. The development of methods for the safety assessment has been an important part of the development of the KBS-3 method. The work with safety assessments has led to an improved understanding and knowledge of important processes in the repository over time and, as a consequence of this, new or improved methods for describing these processes. A detailed account of related issues would be relatively extensive, however, and has therefore not been included in this report. The following thematic breakdown is used in the report: - Waste management sequence and facilities. - Interim storage facility. - Encapsulation plant. - Final repository. - Buffer and backfill. - Buffer. - Backfill. - Canister. The development of each of these thematic areas is described with an emphasis on important changes that have occurred and the reasons for them. A summarizing picture is then provided of SKB's work with the development of methods for safety assessment, plus some facts concerning SKB's international research cooperation}
place = {Sweden}
year = {2010}
month = {Nov}
}