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  • 2010:22 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 16

    This report constitutes Stage 16 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Results up to Stage 15 were reported in SKI and SSM reports, as listed below and in the Summary. The results have also been published in international journals and have been included in both licentiate- and doctor’s degrees.

    Innehållstyp: Publikationer
  • 1995:19 Non-destructive Assay of Spent BWR Fuel with High-resolution Gamma-ray Spectroscopy

    A method, based on high-resolution gamma-ray spectroscopy, has been developed for verification of burnup, cooling time, power history and, to some extent, the initial enrichment of spent BWR fuel. It is shown that, provided that the power history is known and corrected for, bumup and cooling time can be verified with accuracies within 3% and 60 days, respectively, for cooling times up to about...

    Innehållstyp: Publikationer
  • 2010:45 Evaluation of models for cyclic plastic deformation – A literature study

    Analysis of nuclear components subjected to cyclic plastic deformation is normally based on the American standard ASME III. With the focus to improve the modeling of the stress-strain response under non-monotonic loading, several models for the analysis of cyclic plastic deformation have been developed in recent years. However, experience shows that the analysis and evaluation of plastic...

    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
  • 2008:04 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
  • 2008:30 A model for fission gas release from mixed oxide nuclear fuel

    Nuclear fuel containing mixed oxide (MOX) pellets have been used since the 1960's. MOX fuel pellets are made from a mixture of uranium and plutonium oxide. MOX allows the large quantities of fissile isotopes produced and remaining in spent nuclear fuel from light water reactors to be recycled. Producing MOX fuel can be seen as a method to more efficiently use the natural uranium since...

    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
  • 2008:33 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
  • 2010:01 Licensing of safety critical softwarefor nuclear reactors

    – Common position of seven European nuclear regulators and authorised technical support organisations...

    Innehållstyp: Publikationer