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  • 2009:26 Tillämpning av stabil spricktillväxt vid brottmekanisk bedömning av defekter i sega material

    Vid brottmekaniska analyser studeras i huvudsak haverimekanismerna sprött brott och plastisk kollaps samt kombinationen av dessa. Den styrande mekanismen bestäms av komponentens materialegenskaper, styrande belastning och defektens geometri. Proceduren enligt SKI-rapport 99:49 är idag en av de mest använda metoderna vid brottmekaniska analyser. Proceduren som baseras på...

    Innehållstyp: Publikationer
  • 2009:15 Improvement and Validation of Weld Residual Stress Modelling Procedure

    Weld residual stresses have a large influence on the behavior of cracks growing under normal operation loads and on the leakage-flow from a through-wall crack. Accurate prediction of these events is important in order to arrive at proper conclusions when assessing detected flaws, for inspection planning and for assessment of leak-before-break margins. Therefore, it is very important to have...

    Innehållstyp: Publikationer
  • 2009:10 Regleringen av matarvattenflödet i en BWR. Med exempel från Forsmark 2

    Säkerheten i kärntekniska anläggningar ska upprätthållas genom att radiologiska olyckor förebyggs. I reaktorer sker detta genom att det finns flerfaldiga barriärer och ett så kallat djupförsvar. I djupförsvaret ingår att åtgärder vidtas för att tillförsäkra lugn och störningsfri drift utan transienter som kan...

    Innehållstyp: Publikationer
  • 2009:13e 2009 assessment of radiation safety in the Swedish nuclear power plants

    This report has been prepared by order of the Swedish government in accordance with the “Governmental directive for the financial year 2009 regarding the Swedish Radiation Safety Authority”. The Swedish Radiation Safety Authority has through its supervision ensured a comprehensive basis for this overall assessment of radiation safety. The overall conclusion is that the radiation safety,...

    Innehållstyp: Publikationer
  • 2009:13 2008 års bedömning av strålsäkerheten vid de svenska kärnkraftsanläggningarna

    Strålsäkerhetsmyndigheten har genom tillsyn säkerställt ett brett underlag för denna samlade strålsäkerhetsvärderingen. Den samlade bedömningen är att strålsäkerhetsläget, dvs. kärnsäkerheten, det fysiska skyddet inkl. kärnämneskontroll och strålskyddet, vid de svenska kärnkraftverken upprätthålls...

    Innehållstyp: Publikationer
  • 2009:05 Survey on requirements for independent reviews and inspections of electrical and I&C equipment

    This survey is a first step to support the work to develop the Swedish regulations in the area of independent review and inspection in the process supporting implementation of electrical equipment in nuclear power plants. The report consists of a summary of different regulations in the area and also an analysis of the differences between the electrical and mechanical field especially in the...

    Innehållstyp: Publikationer
  • 2009:32 On Younger Stakeholders and Decommissioning of Nuclear Facilities

    An appropriate balance in this regard must be based on a proper understanding of the values and value functions of younger citizens. Such information must thus be an integral part of the knowledge base to be used when plans and processes are being developed for dismantling and decommissioning of nuclear power plants and other older nuclear facilities. In the present project, empirical data...

    Innehållstyp: Publikationer
  • 2009:31 A Review of the Decommissioning Costs of the Ranstad Site

    The main objective of this study has been to review the future cost to decommission and dismantling the industrial area at the site of the old uranium mine at Ranstad in Sweden. Analyses of some detailed comparative empirical information have been used in the context of preliminary “bench-marking” studies. The estimated costs for decommissioning of the old uranium mine in Ranstad have been...

    Innehållstyp: Publikationer
  • 2009:30 A Review of Evidence for Corrosion of Copper by water

    The planned spent nuclear fuel repository in Sweden relies on a copper cast iron canister as the primary engineered barrier. The corrosion behaviour of copper in the expected environment needs to be thoroughly understood as a basis for the post-closure safety analysis. It has been shown that corrosion may indeed be the primary canister degradation process during the utilised assessment period...

    Innehållstyp: Publikationer