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  • 2012:32 Technical Note, Groundwater Chemistry in SKB’s Safety Assessment SR-Site: Initial Review

    This preliminary review of SR-Site is focused specifically on the treatment of groundwater chemistry in the description of the Forsmark site and in the long-term safety of a deep geological repository at Forsmark. Data for the chemical and isotopic compositions of groundwaters have contributed to a site descriptive model (SDM) for Forsmark. In that SDM, groundwater chemistry is interpreted...

    Content type: Publications
  • 2012:42 Technical Note, Initial review of physical properties and processes of the buffer and backfill – Installation and initial state

    The technical note briefly summarises the proposed designs and functions of the buffer and backfill, and examines SKB’s progress in manufacturing, installing and testing its proposed solutions. In brief, the review suggests that there are some procedural and practical engineering aspects (e.g., quality assurance procedures, backfilling rates) and several physical processes to do with the...

    Content type: Publications
  • International peer review of repository application

    The Swedish Radiation Safety Authority has performed a review of SKB’s (i.e. Svensk Kärnbränslehantering AB) application for construction of a repository for spent nuclear fuel, and recommends approval of this application, as stated in our pronouncement to the Government on 23 January 2018. A peer review has also been performed by OECD’s Nuclear Energy Agency (NEA) concerning the...

    Content type: Regular Pages
  • 2011:22 Infiltration of dilute groundwaters and resulting groundwater compositions at repository depth

    The planned Swedish concept for final disposal of spent nuclear fuel includes copper canisters placed in deposition holes at about 500 m depth in granitic bedrock. The copper canisters will be surrounded by bentonite buffer with the objective of inhibiting groundwater flow adjacent to the canister. It has been discovered that dilute glacial melt-water may induce erosion of the buffer material.

    Content type: Publications
  • 2011:21 Workshop on spent fuel performance and radionuclide chemistry -Rånäs 2010: Assessment of some outstanding issues

    The safety assessment for final disposal of spent nuclear fuel has to comprehensively address the stage when containment barriers have failed and when radionuclide releases occur to the surrounding groundwater at repository depth. Essential processes for estimating risk/dose related to this scenario involve the release of radionuclide from the spent fuel surfaces due to radio-lytic oxidative...

    Content type: Publications
  • 2012:21 Technical Note, Initial Review Phase for SKBs Safety Assessment SR-Site: Corrosion of Copper

    The uniform and localized corrosion treatments as well as stress corrosion cracking positions currently considered by SKB have been examined with the objective of identifying key unresolved issues or gaps, needs and opportunities. In conjunction with the review of the SKB reports listed in Appendix 1, there has been some consideration of the broader literature. This summary highlights the...

    Content type: Publications
  • 2012:17 Technical Note, Corrosion of copper canister

    It is expected that the inflow of ground water to the deposition holes and tunnels in the Forsmark repository will be very slow. Thus, it might take some few hundred years up to thousand years before the deposition holes are filled with ground water and it might take 6000 years or more before the bentonite buffer is fully water saturated and pressurized. The copper canisters will therefore...

    Content type: Publications
  • 2012:24 Technical Note, Initial Review of SR-Site Main Report

    The Swedish Radiation Safety Authority (SSM) is reviewing a license application, which has been submitted by Svensk Kärnbränslehantering AB (SKB), for a repository for the final disposal of spent nuclear fuel. SKB’s Application includes an assessment of the long-term safety of the proposed repository. The assessment is known as SR-Site. This technical note records the findings from a...

    Content type: Publications
  • 2012:13 Technical Note, A review of the creep ductility of copper for nuclear waste canister application

    SKB has presented insufficient evidence to justify their position that the OFP copper has an adequate creep ductility during long term storage. Their large body of experiments only serves to prove that the creep ductility is sufficient for much shorter time spans than the intended storage times. There is a clear need for a credible theory of creep brittleness of OFP copper which will permit...

    Content type: Publications
  • 2012:29 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill – Geochemical processes

    De dokument i SR-Site som är relevanta till detta granskningsområde bedöms vara generellt i tillräckligt hög kvalitet för att utgöra underlagsmaterial för vidare granskning i huvudgranskningsfasen av SSM:s GLS- (granskning av långsiktig säkerhet) projekt. Behov av kompletterande information eller förtydliganden har dock identifierats inom...

    Content type: Publications