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  • Strålsäkerhetsmyndighetens svar på regeringens remisser

    Regeringen fattade beslut om att godkänna ett slutförvar för använt kärnbränsle i januari 2022. Strålsäkerhetsmyndigheten svarade på regeringens remisser 2019–2021 inför beslutet. ...

    Innehållstyp: Artiklar
  • 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
  • Extern granskning: Technical note och Internationell granskning

    Som en del av Strålsäkerhetsmyndighetens granskning 2011–2018 tog myndigheten hjälp av externa granskare för avgränsade frågor. Det genomfördes även en internationell expertgranskning som samordnades av The Nuclear Energy Agency (NEA).

    Innehållstyp: Artiklar
  • 2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions

    We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...

    Innehållstyp: Publikationer
  • 2011:16 Modelling of ultrasonic testing of cracks in cladding

    During the last two decades, SSM has supported research to develop a model for the non-destructive test situation based on ultrasonic technique. Such a model is important in many ways, for example to supplement and plan experimental studies and to perform parametric studies in qualification situation. Modeling can be a useful tool when the inspection system shall be technically justified.

    Innehållstyp: Publikationer
  • 2011:13 Investigation of Discrete-Fracture Network Conceptual Model Uncertainty at Forsmark

    Flow modelling using alternative assumptions regarding conceptual and parametric uncertainty in the spatial and structural relationships among fractures indicates elevated flow rates and groundwater velocities to deposition holes compared to SKB’s flow modelling results. Simulated sampling of fractures in boreholes does not indicate any reason to exclude the proposed spatial and structural...

    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
  • 2015:48 Technical Note, Supplementary review of SKB’s further RFI response

    Bakgrund Strålsäkerhetsmyndigheten (SSM) granskar Svensk Kärnbränslehantering AB:s (SKB) ansökningar enligt lagen (1984:3) om kärnteknisk verksamhet om uppförande, innehav och drift av ett slutförvar för använt kärnbränsle och av en inkapslingsanläggning. Som en del i granskningen ger SSM konsulter uppdrag för att inhämta...

    Innehållstyp: Publikationer
  • 2014:48 Technical Note, Independent assessment of groundwater sulphide content in the long-te

    Groundwater sulphide content is a key factor in the determination of canister lifetimes because of its role in corrosion of copper. SKB has based the canister lifetime analysis on a distribution of measured sulphide concentrations which are assumed to apply throughout the long-term analysis period. The distribution is based on expert judgement in the selection of samples that are regarded as...

    Innehållstyp: Publikationer
  • 2014:41 Technical Note, Review of Radionuclide Abstraction and Selection in the SKB Safety Case -Main Review Phase

    As part of the Swedish Radiation Safety Authority (SSM) review of the Swedish Nuclear Fuel and Waste Management Company (SKB) SR-Site safety assessment for a spent nuclear fuel repository in Sweden, this technical note documents the Center for Nuclear Waste Regulatory Analyses (CNWRA®) review of the abstraction and selection of radionuclides in the SKB safety case. Specifically, CNWRA...

    Innehållstyp: Publikationer