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Din avgränsning ger 571 träffar.

• 2010:28 GEMA3D – landscape modelling for dose assessments

  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

• 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

• 2010:30 INSITE Summary Report

  SSM and its predecessor SKI employed a team of earth scientists who followed and reviewed SKB’s investigations of the potential spent nuclear fuel repository sites at Forsmark and Laxemar. This group was named INSITE (INdependent Site Investigation Tracking and Evaluation) and began its work in 2002 and completed its task with the review of the final versions SKB’s site descriptive models,...

  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