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  • 2010:09 Copper Thermodynamics in the Repository Environment up to 130˚C

    The mechanisms of copper corrosion for a KBS-3 repository for spent nuclear fuel need to be known with a high level of confidence. This is because the overall rate of copper canister corrosion (accounting for corroding species concentrations, geochemical conditions and the mass transport through surrounding barriers) provides an essential performance indicator in safety assessment. A...

    Innehållstyp: Publikationer
  • 2010:05 Discrete-Feature Model Implementation of SDM-Site Forsmark

    SSM has been following the investigations of the two candidate sites for a repository for spent nuclear fuel that the Swedish Nuclear Fuel and Waste Management Company (SKB) have been undertaking. SKB has reported the results of the investigations as site descriptive models. These models will be used to underpin the safety analysis following the license application of the repository planned...

    Innehållstyp: Publikationer
  • 2010:18 Radionuclide Transport: Preparation During 2009 for the SR-Site Review

    Post-closure safety assessments for nuclear waste repositories involve radioecological modelling for an underground source term. Following several decades of research and development, the Swedish Nuclear Waste Management Company (SKB) is approaching a phase of license application. According to SKB’s plans, an application to construct a geological repository will be submitted by the end of...

    Innehållstyp: Publikationer
  • 2009:35 Evaluation of SKB/Posiva’s report on the horizontal alternative of the KBS-3 method

    The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. The method has two design alternatives: the vertical (KBS-3V) and the horizontal (KBS-3H). SKB and Posiva have conducted a joint research, development and demonstration (RD&D) programme in 2002-2007 with the overall aim of establishing whether the KBS-3H represents a...

    Innehållstyp: Publikationer
  • 2010:31 Buffer erosion: An overview of concepts and potential safety consequences

    In its safety analysis SR-Can, SKB reported preliminary results and conclusions on the mechanisms of bentonite colloid formation and stability, with a rough estimate of the consequences of loss of bentonite buffer by erosion. With the review of SR-Can the authorities (SKI and SSI) commented that erosion of the buffer had the greatest safety significance, that the understanding of the...

    Innehållstyp: Publikationer
  • 2018:21 Research on Resaturation of Bentonite Buffer

    Background Resaturation processes in the bentonite buffer in a KBS-3 type repository for spent nuclear fuel are complicated and are often illustrated, analysed and modelled multi-disciplinarily as coupled thermal (T), hydrological (H) and mechanical (M) processes with multi-phase flow, elastoplastic evolution in a swelling porous medium. Previous THM-modelling showed that the re-saturation...

    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
  • 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
  • 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
  • 2000:13 Utvärdering av omgivningskontrollprogrammet vid kärnkraftverken och Studsvik

    De kärntekniska anläggningarna utför årligen omgivningskontroll i närområdet enligt ett program utarbetat av SSI. En mer omfattande utvärdering av programmet har genomförts baserat på närmare 20 års erfarenheter och mätdata. Resultaten visar att i den terrestra miljön detekteras de högsta halterna och det största antalet...

    Innehållstyp: Publikationer