Forskningsrapporter

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  • 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
  • 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
  • 2008:33 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
  • 2008:13 Rekommendationer för analys av spänningsrespons i rörsystem utsatta för termohydrauliska transienter

    Snabba termohydrauliska transienta förlopp, t.ex. vattenslag på grund av momentant rörbrott eller ventilstängning, leder till strukturbelastningar som är högfrekventa i sin natur. För dessa laster finns inga enkla analyskriterier att tillgå för att påvisa fullständigheten i den beräknade spänningsresponsen i röret. De mest väsentliga...

    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
  • 2008:09 The Generalised Ecosystem Modelling Approach in radiological assessment

    An independent modelling capability is required by SSI in order to evaluate dose assessments carried out in Sweden by, amongst others, SKB. The main focus is the evaluation of the long-term radiological safety of radioactive waste repositories for both spent fuel and low-level radioactive waste. To meet the requirement for an independent modelling tool for use in biosphere dose assessments,...

    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
  • 2008:05 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
  • 2008:10 User’s manual for Ecolego Toolbox and the Discretization Block

    The CLIMB modelling team (Catchment LInked Models of radiological effects in the Biosphere) was instituted in 2004 to provide SSI with an independent modelling capability when reviewing SKB’s assessment of long-term safety for a geological repository. Modelling in CLIMB covers all aspects of performance assessment (PA) from near-field releases to radiological consequences in the surface...

    Innehållstyp: Publikationer