Din avgränsning ger 302 träffar.
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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 -
2009:16 Influence of Hardening Model on Weld Residual Stress Distribution
Weld residual stresses have a large influence on the behavior of cracks growing under normal operation loads and on the leakage-flow from a through-wall crack. Accurate prediction of these events is important in order to arrive at proper conclusions when assessing detected flaws, for inspection planning and for assessment of leak-before-break margins. Therefore, it is very important to have...
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 -
2009:17 Effect of Welding Residual Stresses on Crack Opening Displacement and Crack-Tip Parameters
Weld residual stresses have a large influence on the behavior of cracks growing under normal operation loads and on the leakage-flow from a through-wall crack. Accurate prediction of these events is important in order to arrive at proper conclusions when assessing detected flaws, for inspection planning and for assessment of leak-before-break margins. The fracture mechanical treatment of weld...
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 -
2009:25 APRI-6 Accident Phenomenaof Risk Importance
Kunskap om de fenomen som kan uppträda vid svåra haverier i en kärnkraftanläggning är viktig förutsättning för att kunna förutse anläggningens beteende, för att kunna utforma rutiner och instruktioner för haverihantering, för beredskapsplaneringen samt för att få god kvalitet på haverianalyser och riskstudier. De svenska...
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 -
2009:12 Evaluating safety-critical organizations – emphasis on the nuclear industry
The regulator identified a few years ago a need for a better understanding of and a deeper knowledge on methods for evaluating safety critical organisations. There is a need for solid assessment methods in the process of management of organisational changes as well as in continuously performed assessment of organisations such as nuclear power plants. A considerable body of literature exists...
Innehållstyp: Publikationer -
2009:33 Workshop on spent fuel performance, radionuclide chemistry and geosphere transport parameters, Lidingö 2008: Overview and evaluation of recent SKB procedures
The safety assessment for disposal of spent nuclear fuel canister in the Swedish bedrock should thoroughly address the time period after a containment failure. Such a failure could be expected as a result of corrosion damage or mechanical failure due to rock movement. This report mainly covers some issues connected to parameters used for radionuclide transport calculations in the areas of...
Innehållstyp: Publikationer -
2018:25 UO2 fuel oxidation and fission gas release
Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance closely. One aspect that has been the main question of several research projects is the fragmentation of fuel pellets during abnormal heat up. In this project the oxidation of UO2 is scrutinized and its effect on pellet fragmentation, fission gas release and damage of fuel rods has been...
Innehållstyp: Publikationer