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  • 2017:27 Översyn av beredskapszoner

    Sammanfattning Den 22 oktober 2015 gav regeringen Strålsäkerhetsmyndigheten (SSM) i uppdrag att, i samråd med Myndigheten för samhällsskydd och beredskap (MSB), berörda länsstyrelser samt andra berörda myndigheter och aktörer, genomföra en översyn av de beredskapszoner som gäller för verksamheter med joniserande strålning. SSM...

    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
  • 2015:28 Utvärdering av materialdata för befintliga betongkonstruktioner - med inriktning på verifiering av förankringar vid kärntekniska anläggningar

    Bakgrund I de Svenska kärnkraftverken finns ett stort antal fästplattor som är ingjutna alternativt eftermonterade. Fästplattan består av en förankringsplatta med tillhörande betonginfästning. Kapaciteten för flera av de viktigare brottmoderna för betonginfästningar styrs av hållfastheten hos omgivande betong. Betongens hållfasthet...

    Innehållstyp: Publikationer
  • 2015:37 Models for axial relocation of fragmented and pulverized fuel pellets in distending fuel rods and its effects on fuel rod heat load

    Haverifall med kylmedelsförlust (LOCA) i lättvattenreaktorer kan leda till överhettning av bränslestavar, utvidgning av stavarnas kapslingsrör, samt axiell omflyttning av bränslekutsfragment i de delar av stavarna som expanderat. Bränsleomflyttningen kan koncentrera värmebelastningen till en begränsad del av stavarna och därigenom öka risken...

    Innehållstyp: Publikationer
  • 2008:12 Independent Calculations for the SRCan Assessment

    External review contribution in support of SKI's and SSI's review of SR-Can The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear...

    Innehållstyp: Publikationer
  • 2008:10 International Expert Review of SR-Can: Engineered Barrier Issues

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has recently submitted a license application for the construction of a spent fuel encapsulation plant. SKB plans to submit a further license application in 2009 for the construction of a repository for the disposal spent nuclear fuel. In connection with the first of these applications, SKB published a safety report, known as SR-Can,...

    Innehållstyp: Publikationer
  • 2007:29 Intercomparison of Cement Solid-Solution Models

    Many concepts for the geological storage of radioactive waste incorporate cement based materials, which act to provide a chemical barrier, impede groundwater flow or provide structural integrity of the underground structures. Thus, it is important to understand the long-term behaviour of these materials when modelling scenarios for the potential release and migration of radionuclides. In the...

    Innehållstyp: Publikationer
  • 2007:09 DECOVALEX-THMC - Task C

    This report describes the results of Task C1 of the international DECOVALEX– THMC project devoted to Excavation Damage Zone (EDZ) in argillaceous rock at the Tournemire site in France. Task C of the project is aimed to understand the physical phenomena induced by excavation in the argillaceous rock. The task is to develop adequate numerical models for interpretation of observed damaged zones...

    Innehållstyp: Publikationer