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  • 2014:22 Technical Note, Workshop on seismic hazard at Forsmark

    This report describes the outcome of the workshop organized by SSM on seismic hazard at Forsmark that was held in Stockholm on the 4 and 5 of June, 2013. The report summarizes the issues discussed and extracts the essential viewpoints that have been expressed. It should not be considered as a comprehensive record of all the discussions at the workshop and individual statements made by...

    Innehållstyp: Publikationer
  • 2014:12 Granskning och utvärdering av SKB:sredovisning av Fud-program 2013

    Enligt förordningen (1984:14) om kärnteknisk verksamhet (kärnteknikförordningen) ska Strålsäkerhetsmyndigheten (SSM) granska och utvärdera det program för forskning, utveckling och demonstration med mera (Fud-program) som reaktorinnehavarna enligt lagen (1984:3) om kärnteknisk verksamhet (kärntekniklagen) ska upprätta. Svensk Kärnbränslehantering...

    Innehållstyp: Publikationer
  • 1999:51 Kostnadsberäkning av diupförvaringav det använda kärnbränslet

    Enligt finansieringslagen skall kärnkraftföretagen, i praktiken Svensk Kärnbränslehantering AB (SKB), årligen till Statens kärnkraftinspektion (SKI) lämna en beräkning över kostnaderna för att omhänderta det använda kärnbränslet och för avvecklingen och rivningen av kärnkraftverken. Efter att SKI granskat och värderat...

    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
  • 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
  • 2010:18 Radionuclide Transport: Preparation During 2009 for the SR-Site Review

    Post-closure safety assessments for nuclear waste repositories involve radioecological modelling for an underground source term. Following several decades of research and development, the Swedish Nuclear Waste Management Company (SKB) is approaching a phase of license application. According to SKB’s plans, an application to construct a geological repository will be submitted by the end of...

    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