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  • 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
  • 2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository

    PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...

    Innehållstyp: Publikationer
  • 2008:05 International Expert Review of SR-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can

    In 2006, SKB published a safety assessment (SR-Can) as part of its work to support a licence application for the construction of a final repository for spent nuclear fuel. The report represented the culmination of work conducted by SKB over several years, focusing on the goal of making the licence application in late 2009. Results from the SR-Can project have been documented in several...

    Innehållstyp: Publikationer
  • 2007:02 Strålmiljön i Sverige

    Rapporten beskriver, och redovisar resultat från, den strålmiljöövervakning som bedrivits i Sverige sedan 1950-talet. Genomsnittliga doser till befolkningen och till speciella befolkningsgrupper redovisas också. En stor del av övervakningen har rört nedfallet och spridningen i ekosystemen av radioaktiva ämnen från de atmosfäriska kärnvapenproven...

    Innehållstyp: Publikationer
  • 2020:13 Core data Research at Uppsala University

    SSM perspective Background This project is to support a research group at Uppsala University in the research field of nuclear data for applications. Nuclear data research is about measuring microscopic cross-sections and developing theoretical nuclear models to create evaluated nuclear data libraries. These nuclear data libraries are used in different applications such as, nuclear technology,...

    Innehållstyp: Publikationer
  • 2020:02 Models for axial gas flow and mixing in LWR fuel rods

    SSM perspective Background Fission gases inside a fuel rod plays an important role in the behaviour of the fuel, both during normal operation and during events and accidents. Fission gases are released from inside the fuel pellets to the gap between the pellet and the cladding tube and then flow to the plenum volume at the top of the fuel rod. In high burnup fuel, this axial flow to the...

    Innehållstyp: Publikationer
  • 2020:16 Estimates ofJ-integral and COD for circumferential through wall cracks under global bending including the effect of pipe end restraint

    SSM perspective Background Leak-before-break (LBB) piping assessments have shown that piping systems can withstand long through-wall cracks before pipe rupture is expected. This is somewhat because pipe ends are restrained. In LBB assessments analyses are often performed for a pipe segment uncoupled from the piping system, as pipe ends are assumed unrestrained. This assumption is conservative...

    Innehållstyp: Publikationer
  • 2023:11 Study of degradation of spent fuel’s structural material and core components under long-term wet storage

    SSM perspective Background Sweden is managing the spent nuclear fuel and core components from its commercial nuclear reactors with a national strategic plan. The fuel and core components are initially stored at the reactor site. After an on-site storage period to comply with transportation limits on decay heat and radiation, these materials are shipped to the Clab (Central Interim Storage...

    Innehållstyp: Publikationer
  • 2023:14 Effect of gamma-irradiation on the redox states of the structural iron in bentonite clay

    SSM perspective Background Bentonite clay is used as buffer and backfill material which form engineered barrier in the spent fuel repository. The buffer material surrounding the copper canister will be exposed to gamma and neutron radiations, especially during the first few hundred years after closure of the repository. The redox states of the structural iron in montmorillonite, the dominant...

    Innehållstyp: Publikationer
  • 2023:06 Instabila matrisdefekter i bestrålat reaktortankstål med höga nickel- och manganhalter

    Strålsäkerhetsmyndighetens perspektiv Bakgrund Reaktortankstål påverkas av neutronbestrålning så att omslagstemperaturen, omslag från sprött till segt brott, ökar och att segheten i det sega området minskar med ökad grad av bestrålning. För att kunna prediktera framtida försprödningsgrader har så kallade trendkurvor...

    Innehållstyp: Publikationer