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Din avgränsning ger 573 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

• 2008:23 SKI’s and SSI’s review of SKB’s safety report SR-Can

  This report summarises the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) joint review of the Swedish Nuclear Fuel & Waste Management Co’s (SKB) safety report SR-Can, on post-closure safety for a KBS-3 spent nuclear fuel repository at Forsmark and Laxemar respectively (SKB TR-06-09). As of 1 July 2008 the Swedish Radiation Safety...

  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

• 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

• 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

• Tubbrott i en tryckvattenreaktor

  Svenska tryckvattenreaktorer har tre ånggeneratorer som innehåller tusentals tuber. Tuberna är en säkerhetsbarriär mellan kärnkraftverkets primär- och sekundärkrets.Om en tub går av måste reaktorn stoppas och den skadade ånggeneratorn isoleras. Faktabladet beskriver vad som händer vid ett tubbrott i en tryckvattenreaktor.

  Innehållstyp: Publikationer

• Snabbstopp i en tryckvattenreaktor

  Faktabladet beskriver hur en tryckvattenreaktor snabbstoppas för att omedelbart avbryta kärnklyvningen. Reaktorn kan snabbstoppas både automatiskt och manuellt.

  Innehållstyp: Publikationer

• Inneslutningen i en kokvattenreaktor

  Reaktorinneslutningen är en av de säkerhetsbarriärer som skyddar omgivningen från radioaktiva utsläpp vid en olycka. Faktabladet beskriver hur inneslutningen i svenska kokvattenreaktorer är konstruerade för detta.

  Innehållstyp: Publikationer

• Bränslebyte i kokvattenreaktor

  Faktabladet beskriver hur bränslets byts i en kokvattenreaktor. Cirka en femtedel av bränsleelementen i en reaktor byts årligen. Bytet görs under den årliga revisionen, när reaktorn är avställd.

  Innehållstyp: Publikationer