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Din avgränsning ger 1334 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

• 2011:31 Allocation of Decommissioning and Waste Liabilities

  A crucial task for the present generations is to ensure that environmental liabilities are identified sufficiently well so that it may be possible to accumulate the corresponding necessary financial assets in the Swedish Nuclear Waste Fund. Adequate funding will provide forthcoming generation’s with the financial means to decommission and dismantle older nuclear facilities that are part of...

  Innehållstyp: Publikationer

• 2011:07 Workshop on Regulatory Review and Safety Assessment Issues in Repository Licensing

  The Swedish Radiation safety Authority (SSM) is currently developing project plans for the review of the Swedish Nuclear Fuel and Waste Management Co’s (SKB) planned license application for a spent nuclear fuel repository in Forsmark and an encapsulation plant in Oskarshamn. In support of the development of these project plans, SSM has carried out several international workshops during 2010...

  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

• 2008:10 International Expert Review of SR-Can: Engineered Barrier Issues

  The Swedish Nuclear Fuel and Waste Management Company (SKB) has recently submitted a license application for the construction of a spent fuel encapsulation plant. SKB plans to submit a further license application in 2009 for the construction of a repository for the disposal spent nuclear fuel. In connection with the first of these applications, SKB published a safety report, known as SR-Can,...

  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

• 2008:48 SKI:s yttrande och utvärdering av SKB:s redovisning av Fud-program 2007

  Svensk Kärnbränslehantering AB, SKB, har lämnat in Fud-program 2007 till SKI för granskning enligt 12 § lagen (1984:3) om kärnteknisk verksamhet (kärntekniklagen). Baserat på SKI:s granskning och inkomna remissyttranden bedömer SKI att regeringen bör besluta: - Att reaktorinnehavarna, genom Svensk Kärnbränslehantering AB, har fullgjort...

  Innehållstyp: Publikationer

• 2007:29 Intercomparison of Cement Solid-Solution Models

  Many concepts for the geological storage of radioactive waste incorporate cement based materials, which act to provide a chemical barrier, impede groundwater flow or provide structural integrity of the underground structures. Thus, it is important to understand the long-term behaviour of these materials when modelling scenarios for the potential release and migration of radionuclides. In 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

• 2018:05 Clab och inkapslingsanläggningen (Clink)

  Beredning inför regeringens prövning Slutförvaring av använt kärnbränsle...

  Innehållstyp: Publikationer