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Din avgränsning ger 25 träffar.

• 2008:12 Independent Calculations for the SRCan Assessment

  External review contribution in support of SKI's and SSI's review of SR-Can The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear...

  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

• 2008:31 Driftklarhetsbeslut i kärnkraftanläggningar – del 2

  Med anledning av avregleringen av elmarknaden i slutet av 1990-talet och den ökade fokuseringen på ekonomi och effektiviseringar av verksamheterna vid de kärntekniska anläggningarna i Sverige lät SKI genomföra en studie av hur tillståndshavarna Ringhals AB, OKG Aktiebolag och Forsmarks Kraft AB integrerar ekonomi och säkerhet i sina ledningssystem (SKI Rapport...

  Innehållstyp: Publikationer

• 2008:32 Erfarenheter från International CCF Data Exchangeprojektet (ICDE), Rev 0

  Rapporten ger grundläggande information om common cause failure (CCF) konceptet och insikter från drifterfarenheter om inträffade CCF-händelser i säkerhetsrelaterade komponenter i såväl utländska som inhemska kärnkraftanläggningar. De drifterfarenheter som förmedlas i rapporten är avsedda att utgöra ett planeringshjälpmedel...

  Innehållstyp: Publikationer

• SSM Report 2008:01 A combined deterministic and probabilistic procedure for safety assessment of components with cracks – Handbook

  SSM has supported research work for the further development of a previously developed procedure/handbook (SKI Report 99:49) for assessment of detected cracks and tolerance for defect analysis. During the operative use of the handbook it was identified needs to update the deterministic part of the procedure and to introduce a new probabilistic flaw evaluation procedure. Another identified need...

  Innehållstyp: Publikationer

• 2008:04 Driftklarhetsbeslut i kärnkraftanläggningar - Vilka faktorer påverkar beslutsfattandet?

  Med anledning av avregleringen av elmarknaden i slutet av 1990-talet och den ökade fokuseringen å ekonomi och effektiviseringar av verksamheterna vid de kärntekniska anläggningarna i Sverige lät SKI genomföra en studie av hur tillståndshavarna Ringhals AB, OKG Aktiebolag och Forsmarks Kraft AB integrerar ekonomi och säkerhet i sina ledningssystem (SKI Ra...

  Innehållstyp: Publikationer

• 2008:33 Risk-informed assessment of defence in depth, LOCA example

  The methods that are used today in PSA are applicable for evaluating defence-in-depth levels 1 and 2. Failure data can be determined through: human reliability analysis, riskinformed in-service-inspection methodology, system reliability analysis and directly from plant specific failure data for the components. Many DID activities against LOCA are not explicitly modelled in typical...

  Innehållstyp: Publikationer

• 2008:07 Modelling of long term geochemical evolution and study of mechanical perturbation of bentonite buffer of a KBS-3 repository

  PART I: The Swedish Nuclear Fuel and Waste Management Co. (SKB) has recently completed a safety assessment project named SR-Can, related to the KBS-3 disposal concept. In this concept, the waste packages are surrounded by a buffer made of either MX-80 or Deponit CA-N bentonite. Interactions between the buffer and groundwater may modify the buffer composition and thus its containment...

  Innehållstyp: Publikationer

• 2008:05 International Expert Review of SR-Can: Safety Assessment Methodology - External review contribution in support of SSI's and SKI's review of SR-Can

  In 2006, SKB published a safety assessment (SR-Can) as part of its work to support a licence application for the construction of a final repository for spent nuclear fuel. The report represented the culmination of work conducted by SKB over several years, focusing on the goal of making the licence application in late 2009. Results from the SR-Can project have been documented in several...

  Innehållstyp: Publikationer

• 2008:08 SSI:s independent consequence calculations in support of the regulatory review of the SR-Can safety assessment

  With the publication of the SR-Can report at the end of 2006, Swedish Nuclear Fuel and Waste Management Co (SKB) have presented a complete assessment of long-term safety for a KBS-3 repository. The SR-Can project demonstrates progress in SKB’s capabilities in respect of the methodology for assessment of long-term safety in support of a licence application for a final repository. According to...

  Innehållstyp: Publikationer