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Din avgränsning ger 159 träffar.

• 2015:30 Technical Note, Rock Mechanics - Assessing the likelihood and extent of fracture growth in the KBS-3 repository at Forsmark

  work concerns the evaluation of the likelihood and extent of fracture growth around the deposition tunnels and holes of the planned KBS-3 repository at Forsmark. The issues of the isostatic, shear and thermal ... and evolution of rock fractures around the KBS-3 repository at Forsmark are addressed. Hereby, the thermal, glacial and earthquake scenarios are considered. The likelihood and extent of fracture growth...

  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

• 2015:49 Technical Note, Independent Modelling of Engineered Barrier Evolution and Coupled THMC: Canister Corrosion Calculations in SR-Site

  Projektets syfte Projektet syftar till att granska olika beräkningsfall för korrosion av kopparkapseln som rapporterats i SKB TR-10-66 och som sammanfattas i SKB TR-11-01. Arbetet omfattar en analys av beräkningsfall relaterade till korrosionshastigheten för intakt buffert, delvis eroderad buffert och för advektiva förhållanden i bufferten. Målsättningen...

  Innehållstyp: Publikationer

• 2012:41 Technical Note, Hydrogeological conditions at the Forsmark site

  hydrogeological site description and groundwater models employed in support of SR-Site, in many ways, represent advances in the state of the art for crystalline bedrock where groundwater moves mainly through ... scales from kilometres down to a meter, as well as excavated portions of the repository including backfilled tunnels and deposition holes. The models used include representations of key physical processes that...

  Innehållstyp: Publikationer

• 2012:58 Technical Note, Independent radionuclide transport modelling – Reproducing results for main scenarios

  As part of the initial technical review of SR-Site, we applied a simplified model to approximate Swedish Nuclear Fuel and Waste Management Company (SKB) computations related to the transport of radionuclides ... radionuclides at the planned KBS–3 repository at the Forsmark site in Sweden. The objective was to provide insights and recommendations to the Swedish Radiation Safety Authority (SSM) on potential clarifications...

  Innehållstyp: Publikationer

• Strålsäkerhetsmyndigheten granskar slutförvaret

  Kärnbränslehantering AB (SKB) in sin ansökan om att få bygga ett slutförvar för använt kärnbränsle i Forsmark i Östhammars kommun till Strålsäkerhetsmyndigheten. Förutom slutförvarsansökan lämnade SKB även in en kompletterad ... bygga en inkapslingsanläggning i Oskarshamns kommun till myndigheten samt en ansökan för hela slutförvarssystemet till mark- och miljödomstolen. Det är regeringen som fattar beslut om SKB ska få tillstånd...

  Innehållstyp: Publikationer

• 2015:25 Design Guide for Nuclear Civil Structures (DNB)

  have previously in a jointly funded research project developed a design guide for civil structures at Swedish nuclear facilities to be based on Eurocodes, DNB. The report was published in January 2014 as ... ensure that the fundamentals of the recommendations will be applied correctly, has SSM commissioned Scanscot Technology AB to further develop and clarify certain parts of the report. Ola Jovall, Johan...

  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 ... 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 ... (Appendix 2). Specific review topics for consideration during the Main Review Phase are recommended in Appendix 3. Randy Arthur SSM English...

  Innehållstyp: Publikationer

• 2014:55 Technical Note, Further Reproduction of SKB’s Calculation Cases and Independent

  Som en del av säkerhetsanalysen SR-Site presenterar SKB modellresultat som illustrerar kapseln och buffertens säkerhetsfunktioner. I var och en av de fem beräkningsfallen är delar ... av de fem beräkningsfallen är delar av kapsel och/eller buffert frånvarande i modellen av slutförvarssystemet. Modellresultaten jämförs inte med säkerhetskriterier eftersom beräkningsfallen innehåller...

  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 ... estimating risk/dose related to this scenario involve the release of radionuclide from the spent fuel surfaces due to radio-lytic oxidative dissolution of the UO2-matrix, inte- raction between radionu-clides and...

  Innehållstyp: Publikationer