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Din avgränsning ger 278 träffar.

• 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

• 2015:08 Technical Note, Rheological properties of the Bentonite Buffer

  Objectives of the project The general objective of the project is to provide review comments on SKB’s postclosure safety analysis, SR-Site, for the proposed repository at Forsmark. This technical note reviews SKB:s reporting of the rheological and geomechanical properties of buffer bentonite, both at high and low densities. Göran Sällfors, GeoForce AB, Göteborg SSM English Objectives of...

  Innehållstyp: Publikationer

• 2015:41 Technical Note, Hydrogeological aspects of future human actions for a repository at Forsmark

  Joel E. Geier SSM English...

  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

• 2010:12 An Evaluation of Models of Bentonite Pore Water Evolution

  The pore-water composition of a KBS-3 bentonite buffer may gradually change as a result of reaction between groundwater and buffer minerals. The rather minor occurrences of the most rapidly reacting minerals in the buffer will have the most immediate and observable influences, but contributions from slow reactions of the main bulk clay phases cannot be ruled out. The performance implication...

  Innehållstyp: Publikationer

• 2010:09 Copper Thermodynamics in the Repository Environment up to 130˚C

  The mechanisms of copper corrosion for a KBS-3 repository for spent nuclear fuel need to be known with a high level of confidence. This is because the overall rate of copper canister corrosion (accounting for corroding species concentrations, geochemical conditions and the mass transport through surrounding barriers) provides an essential performance indicator in safety assessment. A...

  Innehållstyp: Publikationer

• 2009:28 Biogeochemistry of Redox at Repository Depth and Implications for the Canister

  The present groundwater chemical conditions at the candidate sites for a spent nuclear fuel repository in Sweden (the Forsmark and Laxemar sites) and processes affecting its future evolution comprise essential conditions for the evaluation of barrier performance and long-term safety. This report reviews available chemical sampling information from the site investigations at the candidate...

  Innehållstyp: Publikationer

• 2010:05 Discrete-Feature Model Implementation of SDM-Site Forsmark

  SSM has been following the investigations of the two candidate sites for a repository for spent nuclear fuel that the Swedish Nuclear Fuel and Waste Management Company (SKB) have been undertaking. SKB has reported the results of the investigations as site descriptive models. These models will be used to underpin the safety analysis following the license application of the repository planned...

  Innehållstyp: Publikationer

• 2009:35 Evaluation of SKB/Posiva’s report on the horizontal alternative of the KBS-3 method

  The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. The method has two design alternatives: the vertical (KBS-3V) and the horizontal (KBS-3H). SKB and Posiva have conducted a joint research, development and demonstration (RD&D) programme in 2002-2007 with the overall aim of establishing whether the KBS-3H represents a...

  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