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  • 2012:46 Technical Note, Review of Landscape Models used in SR-Site

    As part of SSM’s Initial Review phase of SKB’s SR-Site safety assessment for the proposed final disposal of spent nuclear fuel at the Forsmark site, Quintessa was given the assignment to consider whether the landscape models and supporting data utilised by SKB are appropriate and fit for purpose. This Technical Note summarises the findings of Quintessa’s review. SKB’s approach to the...

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • Strålsäkerhetsmyndighetens yttranden 2018 och 2016

    Strålsäkerhetsmyndighetens lämnade sitt yttrande till regeringen om ett slutförvar för använt kärnbränsle i januari 2018. Redan 2016 hade myndigheten lämnat ett remissyttrande till Mark-och miljödomstolen vid Nacka tingsrätt i en parallell process. ...

    Innehållstyp: Artiklar
  • 2014:23 Technical Note, Workshop on Rock Mechanics Issues and their Implications for Groundwater Flow – Main Review Phase

    This report describes the outcome of the workshop organized by SSM on Rock Mechanics and Hydrogeology that was held in Stockholm on the 30/9 and 1/10, 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
  • Andra aktörer i slutförvarsfrågan

    Strålsäkerhetsmyndigheten har ett samlat ansvar för strålskydd och kärnsäkerhet. Myndigheten granskar Svensk Kärnbränslehantering AB:s (SKB) arbete med att bygga och driva slutförvar. Flera aktörer är, eller har varit engagerade i frågan om ett slutförvar för använt kärnbränsle. Det gäller bland annat andra...

    Innehållstyp: Artiklar
  • 1997:05 SKI SITE-94

    The Swedish Industry program for deep geological disposal of spent nuclear fuel and high-level radioactive waste is now in the early stages of the site selection process, with feasibility studies underway in 5 to 10 municipalities. According to the Swedish Nuclear Fuel and Waste Management Co., SKB (SKB RD&D Programme, 1995), the ongoing siting process involves selection of two sites for...

    Innehållstyp: Publikationer
  • 2006:01 Formella expertbedömningar av jordskalv efter nedisning i Sverige

    Statens strålskyddsinstitut, Statens kärnkraftinspektion och Svensk Kärnbränslehantering AB har tillsammans genomfört ett projekt med formella expertutfrågningar i ämnet jordskalv i Sverige i samband med nedisning. Efter ett brett nomineringsförvarande har 5 experter valts ut av en urvalskommitté av 4 professorer inom området. De 5 experterna har...

    Innehållstyp: Publikationer
  • 2014:57 Technical Note, Issues in the Corrosion of Copper in a Swedish High Level Nuclear Waste Repository: Phase III. Role of Sulphide Ion in Anodic and Cathodic Processes

    The most important findings of this research project show that: In the case when the bentonite buffer between the copper canister and the granitic rock is not damaged, we can neglect the possibility of general corrosion damage being a threat to canister integrity over a 100,000 year storage period. However, if the bentonite buffer is damaged for any reason, and does not act as an engineered...

    Innehållstyp: Publikationer
  • 2008:08 SSI:s independent consequence calculations in support of the regulatory review of the SR-Can safety assessment

    With the publication of the SR-Can report at the end of 2006, Swedish Nuclear Fuel and Waste Management Co (SKB) have presented a complete assessment of long-term safety for a KBS-3 repository. The SR-Can project demonstrates progress in SKB’s capabilities in respect of the methodology for assessment of long-term safety in support of a licence application for a final repository. According to...

    Innehållstyp: Publikationer