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Din avgränsning ger 276 träffar.

• 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

• 2018:05 Clab och inkapslingsanläggningen (Clink)

  Beredning inför regeringens prövning Slutförvaring av använt kärnbränsle...

  Innehållstyp: Publikationer

• 2018:03 Remissammanställning

  Beredning inför regeringens prövning Slutförvaring av använt kärnbränsle...

  Innehållstyp: Publikationer

• 2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents

  Ali R. Massih, Lars Olof Jernkvist SSM English...

  Innehållstyp: Publikationer

• SSMFS 2018:2 Strålsäkerhetsmyndighetens föreskrifter om anmälningspliktiga verksamheter

  SSMFS 2018:2 har upphävt SSMFS 2008:5, 2008:40 och 2012:1. I SSMFS 2018:2 har ändringar förts in genom SSMFS 2019:1, SSMFS 2019:4 och SSMFS 2025:2.

  Innehållstyp: Publikationer

• 2008:09 The Generalised Ecosystem Modelling Approach in radiological assessment

  An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments,...

  Innehållstyp: Publikationer

• 2017:30 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – consequence analysis

  Main review phase...

  Innehållstyp: Publikationer

• 2017:31 SSM’s external experts’ review of SKB’s safety assessment SR-PSU – rock engineering and concrete barriers

  Main review phase...

  Innehållstyp: Publikationer

• 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

• 2003:19 Nuclear Waste Separation and Transmutation Research with Special Focus on Russian Transmutation Projects Sponsored by ISTC

  Henri Condé, Waclaw Gudowski, Jan Blomgren, Jan-Olov Liljenzin, Nils Olsson, Curt Mileikovsky, Jan Wallenius. March 2003 SKI English...

  Innehållstyp: Publikationer