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Din avgränsning ger 572 träffar.

• 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

• 2011:03 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

• 2016:02 Technical Note, An updated review of the creep ductility of copper including the effect of phosphorus

  Background The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of a reposi-tory for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information on specific...

  Innehållstyp: Publikationer

• 2015:48 Technical Note, Supplementary review of SKB’s further RFI response

  Bakgrund Strålsäkerhetsmyndigheten (SSM) granskar Svensk Kärnbränslehantering AB:s (SKB) ansökningar enligt lagen (1984:3) om kärnteknisk verksamhet om uppförande, innehav och drift av ett slutförvar för använt kärnbränsle och av en inkapslingsanläggning. Som en del i granskningen ger SSM konsulter uppdrag för att inhämta...

  Innehållstyp: Publikationer

• 2016:23 Technical Note, Modelling of the thermal evolution of the KBS-3 repository at Forsmark and associated induced seismic activity

  Main Review Phase Introduction The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of the KBS-3 repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain...

  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

• 2016:05 Technical Note, Assessment of SKB TR-14-15 Assessment of SKB TR-14-15 “Possible influence from stray currents from high voltage DC power transmission on copper canisters”

  The general objective of the present project is to provide independent review comments for one area of SKB:s post closure safety analysis, SR-Site. With this in mind, the purpose of this report is to review SKB’s presentation on possible influence from stray currents from high voltage DC power transmission on a repository for nuclear fuel. Laust B Pedersen SSM English The general objective of...

  Innehållstyp: Publikationer

• 2015:40 Technical Note, Assessment of flow-related transport parameters used in the SR-Site safety case

  Joel E. Geier SSM English...

  Innehållstyp: Publikationer