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Din avgränsning ger 112 träffar.

• 2009:35 Evaluation of SKB/Posiva’s report on the horizontal alternative of the KBS-3 method

  The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. The method has two design alternatives: the vertical (KBS-3V) and the horizontal (KBS-3H). SKB and Posiva have conducted a joint research, development and demonstration (RD&D) programme in 2002-2007 with the overall aim of establishing whether the KBS-3H represents a...

  Innehållstyp: Publikationer

• 2009:09 Analysis of three sets of SWIW tracer test data using a two-population complex fracture model for matrix diffusion and sorption

  For the non-sorbing tracer uranine, both the finite and the semi-infinite populations play a distinct role in controlling BTC. For the sorbing tracers Cs and Rb the finite population does not saturate, but acts essentially semi-infinite, thus the BTC behaviour is comparable to that obtained for a model containing only a semi-infinite rock matrix. The ability to match BTC for both sorbing and...

  Innehållstyp: Publikationer

• 2011:09 Is Copper Immune to Corrosion When in Contact With Water and Aqueous Solutions?

  The KBS-3concept implies that spent nuclear fuel is placed in copper canisters surrounded by clay and finally placed approximately 500 m down from surface into granitic bedrock, in order to isolate the spent nuclear fuel from humans and environment for very long time scales (i.e. millions of years). The concept is based on the multi-barrier principle, in this respect the barriers are the...

  Innehållstyp: Publikationer

• 2010:33 Lineament interpretation Short review and methodology

  This report concerns a study which was initially conducted for the Swedish Nuclear Power Inspectorate (SKI), which is now merged into the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the author and do not necessarily coincide with those of the SSM. In the characterization of a site that may have potential for hosting a...

  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

• 2018:21 Research on Resaturation of Bentonite Buffer

  Background Resaturation processes in the bentonite buffer in a KBS-3 type repository for spent nuclear fuel are complicated and are often illustrated, analysed and modelled multi-disciplinarily as coupled thermal (T), hydrological (H) and mechanical (M) processes with multi-phase flow, elastoplastic evolution in a swelling porous medium. Previous THM-modelling showed that the re-saturation...

  Innehållstyp: Publikationer

• Strålskyddsexpertfunktion

  Tillståndspliktiga verksamheter med joniserande strålning ska ha tillgång till en strål­skydds­expert­funktion enligt 3 kap. 13 § i Strål­säkerhets­myndig­hetens föreskrifter (SSMFS 2018:1) om grundläggande bestämmelser för tillstånds­pliktig verksamhet med joniserande strålning.

  Innehållstyp: Artiklar

• Att arbeta strålsäkert

  Den som har tillstånd att driva verksamhet med joniserande strålning är också den som har ansvaret för personalens strålskydd. Informationen på den här sidan är främst riktad till dig som är tillståndshavare. Du måste följa Strål­säker­hets­myndig­hetens föreskrifter och se till att personalen...

  Innehållstyp: Artiklar

• 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

• 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