Visar 4414 sökträffar på ””
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2012:12 APRI-7 Accident Phenomena of Risk Importance. En lägesrapport om forskningen inom området svåra haverier under åren 2009-2011
Kunskap om de fenomen som kan uppträda vid svåra haverier i en kärnkraftanläggning är en 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. Sedan...
Innehållstyp: Publikationer -
2013:29 Regulatory Approaches in Nuclear Power Supervision
The objective of this follow-up study was to support SSM in further understanding regulatory approaches and how they can be combined as part of effective strategies. The survey was intended to assist SSM in identifying current standards, experiences, and practices in the regulation of nuclear power plants. The results will also be valuable for the participating authorities as well as other...
Innehållstyp: Publikationer -
2011:24 Utredning och kartläggning av tillfällen då människan räddat och förbättrat en situation där automatiken inte räckt till eller fungerat fel
ÅF har genomfört en litteraturstudie och beskrivit en aktuell bild över rådande automations-filosofier och på vilket sätt människan påverkas av olika nivåer av automation. De har även kartlagt och beskrivit tre händelser inom kärnkraftsindustrin där människan ingripit och räddat eller förbättrat en situation där...
Innehållstyp: Publikationer -
2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions
We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...
Innehållstyp: Publikationer -
2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components
During the recent years fatigue analysis procedures for nuclear components have been investigated. The most common method so far has been the American code ASME III. The basis for the current design procedures in ASME III is quite old and has now been evaluated against modern data leading to the proposal of modified design curves. Also the effect of the environment has been the subject of...
Innehållstyp: Publikationer -
2011:30 A fatigue analysis including environmental effects for a pipe system in a Swedish BWR
The effect of the environment on fatigue design has been the subject of intense study in USA, Japan and elsewhere. Several reports indicate a potentially large influence of the environment, leading to the proposal of entirely new analysis procedures. SSM has in an earlier project sponsored research to evaluate the technical basis for these proposals, see SSM Research Report 2011:04. In the...
Innehållstyp: Publikationer -
2013:04 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 18
The program executed in Stage 18 consists of the following three parts: Application of CoreSim with a two-dimensional model of vibrating fuel assemblies, for the calculation of ex-core detector noise throughout a fuel cycle; An investigation of the neutron noise, induced by propagating perturbations, in various thermal and fast reactor systems, in two-group theory; A consistent derivation of...
Innehållstyp: Publikationer -
2007:20 Internationellt samarbete inom OECD/NEA 2006 avseende nukleär kriticitetssäkerhet
Deltagande i internationellt samarbete inom OECD/NEA:s Nuclear Science Committee och dess Working Party on Nuclear Criticality Safety har fortsatt under 2006 med stöd av SKI. Inga stora projekt där jag varit mycket aktiv har pågått. Däremot har jag deltagit i arbetet genom granskning av förslag till slutrapporter, vid bedömning av nya projekt samt i fortsatt...
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 -
2007:43 ProLBB - A Probabilistic Approach to LeakBefore Break Demonstration
The SKI regulation SKIFS 2004:2 allows for the use of Leak Before Break (LBB) as one way to provide assurance that adequate protection exists against the local dynamic consequences of a pipe break. The way to demonstrate that LBB prevails relies on a deterministic procedure for which a leakage crack is postulated in certain sections of the pipe based on the leak detection capability of the...
Innehållstyp: Publikationer