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Din avgränsning ger 276 träffar.

• 2012:48 Technical Note, Use of Solubility Limits in the SR-Site Safety Assessment

  In a radioactive waste disposal environment, in some potential situations (scenarios) a disposed canister containing spent fuel may be breached and the fuel may come into contact with groundwater. The concentration of a radioactive element such as uranium may rise to a level where the solution is saturated. No more of the radioactive element may dissolve and a precipitated solid may be formed.

  Innehållstyp: Publikationer

• 2011:31 Allocation of Decommissioning and Waste Liabilities

  A crucial task for the present generations is to ensure that environmental liabilities are identified sufficiently well so that it may be possible to accumulate the corresponding necessary financial assets in the Swedish Nuclear Waste Fund. Adequate funding will provide forthcoming generation’s with the financial means to decommission and dismantle older nuclear facilities that are part of...

  Innehållstyp: Publikationer

• 2012:26 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill - Chemical erosion processes

  The SR-Site documentation relevant to this review topic was found to be of sufficiently high quality overall to justify further consideration in the Main Review Phase of SSM’s PCS (Post-closure safety) project. Several specific topics for which complementary information and clarifications should be requested from SKB were also identified (Appendix 2). Specific review topics for consideration...

  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

• 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

• 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

• 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

• 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

• 2025:02 INCLUDE: Including (local) stakeholder participation in the regulatory mission – a future challenge

  SSM perspektiv Bakgrund Det primära fokus för SSM:s kommunikation med intressenter i samband med slutförvaring av använt kärnbränsle och kärnavfall har under flera år legat på formella samrådsprocesser kring den svenska kärnkraftsindustrins forsknings- och utvecklingsprogram samt SKB:s tillståndsansökningar enligt kärntekniklagen.

  Innehållstyp: Publikationer