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Din avgränsning ger 112 träffar.

• 2017:15 Radionuclide release rates associated with bounding cases featuring relatively early canister failures in a spent fuel repository

  Background In 2011 the Swedish Nuclear Fuel and Waste Management Co (SKB) submitted a license application for construction of a geological repository for spent nuclear fuel according to the KBS-3 method, comprising of copper canisters, bentonite buffer, backfill and surrounding crystalline bedrock. The post-closure safety assessment of the repository, SR-Site, has been reviewed by the Swedish...

  Innehållstyp: Publikationer

• 2015:25 Design Guide for Nuclear Civil Structures (DNB)

  The Swedish Radiation Safety Authority (SSM) and the Swedish licensees have previously in a jointly funded research project developed a design guide for civil structures at Swedish nuclear facilities to be based on Eurocodes, DNB. The report was published in January 2014 as SSM Report 2014:06. To further improve DNB and to ensure that the fundamentals of the recommendations will be applied...

  Innehållstyp: Publikationer

• SSMFS 2018:2 Strålsäkerhetsmyndighetens föreskrifter om anmälningspliktiga verksamheter

  SSMFS 2018:2 har upphävt SSMFS 2008:5, 2008:40 och 2012:1. I SSMFS 2018:2 har ändringar förts in genom SSMFS 2019:1, SSMFS 2019:4 och SSMFS 2025:2.

  Innehållstyp: Publikationer

• 2013:28 Brine intrusion by upconing for a high-level nuclear waste repository at Forsmark. Scoping calculations

  The objective of this study is to evaluate the possibility of salt-water migration to the spent nuclear repository. This objective is motivated by the adverse impacts of water with too high salinity entering the repository and by the uncertainty of the relevant hydraulic and hydrogeochemical conditions at the Forsmark site at great depths. To analyse density dependent flow and salt transport...

  Innehållstyp: Publikationer

• 2012:71 Identification of Brittle Deformation Zones and Weakness Zones

  In preparation for the review of Swedish Nuclear Fuel and Waste Management Company’s (SKB) license application for disposal of spent nuclear fuel, Swedish Radiation Safety Authority (SSM) is conducting studies to evaluate the performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at...

  Innehållstyp: Publikationer

• 2012:61 Geochemical Constraints on Buffer Pore Water Evolution and Implications for Erosion

  Mineralogical data from the Forsmark Site show that smectite and calcite occur at all depths in Forsmark fractures, with no evidence for removal/dissolution by previous glacial episodes. This natural analogue information implies that these minerals may not have been eroded/dissolved during previous glacial episodes. Available thermodynamic data suggest that repository-depth Forsmark...

  Innehållstyp: Publikationer

• 2009:33 Workshop on spent fuel performance, radionuclide chemistry and geosphere transport parameters, Lidingö 2008: Overview and evaluation of recent SKB procedures

  The safety assessment for disposal of spent nuclear fuel canister in the Swedish bedrock should thoroughly address the time period after a containment failure. Such a failure could be expected as a result of corrosion damage or mechanical failure due to rock movement. This report mainly covers some issues connected to parameters used for radionuclide transport calculations in the areas of...

  Innehållstyp: Publikationer

• 2009:19 Review of SKB’s Quality Assurance Programme

  SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. The assessment of long-term safety is based on a broad range of experimental results from laboratory scale, intermediate scale and up to full scale experiments. It is essential that...

  Innehållstyp: Publikationer

• 2009:09 Analysis of three sets of SWIW tracer test data using a two-population complex fracture model for matrix diffusion and sorption

  For the non-sorbing tracer uranine, both the finite and the semi-infinite populations play a distinct role in controlling BTC. For the sorbing tracers Cs and Rb the finite population does not saturate, but acts essentially semi-infinite, thus the BTC behaviour is comparable to that obtained for a model containing only a semi-infinite rock matrix. The ability to match BTC for both sorbing and...

  Innehållstyp: Publikationer

• 2010:25 Modelling Coupled Processes in the Evolution of Repository Engineered Barrier Systems using QPAC-EBS

  Currently in Sweden, the SR-Site safety assessment for a spent nuclear fuel repository is being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB). The planned SSM review of this work requires access to a sufficient modelling capability to assess the combined performance of the engineered barriers (spent fuel canister, buffer and backfill) and the natural geosphere...

  Innehållstyp: Publikationer