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Din avgränsning ger 751 träffar.

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  • 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
  • Inneslutningen i en tryckvattenreaktor

    Reaktorinneslutningen är en av de säkerhetsbarriärer som skyddar omgivningen från radioaktiva utsläpp vid en olycka.

    Innehållstyp: Artiklar
  • 2019:25 Maskulinitet, risk och säkerhet vid ett svenskt kärnkraftverk

    SSM perspektiv Bakgrund Likt anställda vid ett järnverk, ett pappersbruk eller en oljeplattform omges även personalen vid ett kärnkraftverk av olika slags risker som hanteras genom ett mer eller mindre lyckosamt säkerhetsarbete. Kärnkraften är en högriskbransch och riskerna för de personer som arbetar inom den har inte enbart med reaktorn och den radioaktiva...

    Innehållstyp: Publikationer
  • 2019:29 Myndighetsstöd: Artificiell Intelligens – tillämpning inom kärnkraften

    SSM perspektiv Bakgrund Området artificiell intelligens (AI) genomgår en omfattande utveckling och stora satsningar görs inom FoU på olika håll runt om i världen. Vinnova fick under 2017 i uppdrag av regeringen att genomföra en kartläggning och analys av hur väl artificiell intelligens (AI) och maskininlärning kommer till användning i svensk...

    Innehållstyp: Publikationer
  • 2019:27 Effect of residual stress on ductile fracture at low primary loads – Numerical study

    SSM perspective Background Present report is a continuation of earlier work reported in SSM2009:27 regarding an analysis strategy for fracture assessment of defects in ductile material and SSM2011:19 on the influence from residual stresses on crack initiation and ductile crack growth at high primary loads. The Swedish procedure for safety assessment of components with defects is documented in...

    Innehållstyp: Publikationer
  • 2019:01 Research within technical safeguard at Uppsala university during 2016-20

    Summary Uppsala University has since January 2016 undertaken an extensive research programme in technical nuclear safeguards within the framework of contract SSM2016-661, including in total 3 PhD students and 7 senior researchers. This report marks the final reporting covered by this contract. The executed research covers the following projects; (1) Methodologies for safeguards assessment of...

    Innehållstyp: Publikationer
  • 2011:21 Workshop on spent fuel performance and radionuclide chemistry -Rånäs 2010: Assessment of some outstanding issues

    The safety assessment for final disposal of spent nuclear fuel has to comprehensively address the stage when containment barriers have failed and when radionuclide releases occur to the surrounding groundwater at repository depth. Essential processes for estimating risk/dose related to this scenario involve the release of radionuclide from the spent fuel surfaces due to radio-lytic oxidative...

    Innehållstyp: Publikationer
  • 2011:03 On Decommissioning Cost for Nuclear Power Plants

    This research report summarizes what has changed over the latest 15 years concerning actual and estimated costs for the D&D of nuclear power plants that have been shut down permanently. It also reports on the availability of detailed information for actual nuclear power plant D&D cost breakdowns. The results will be one supporting document in the review of the estimates submitted for...

    Innehållstyp: Publikationer
  • 2009:33 Workshop on spent fuel performance, radionuclide chemistry and geosphere transport parameters, Lidingö 2008: Overview and evaluation of recent SKB procedures

    The safety assessment for disposal of spent nuclear fuel canister in the Swedish bedrock should thoroughly address the time period after a containment failure. Such a failure could be expected as a result of corrosion damage or mechanical failure due to rock movement. This report mainly covers some issues connected to parameters used for radionuclide transport calculations in the areas of...

    Innehållstyp: Publikationer
  • 2009:19 Review of SKB’s Quality Assurance Programme

    SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. The assessment of long-term safety is based on a broad range of experimental results from laboratory scale, intermediate scale and up to full scale experiments. It is essential that...

    Innehållstyp: Publikationer