Din avgränsning ger 301 träffar.
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2007:23 On Safety Management, A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety
The authors present the theoretical framework. There they also discuss the pros of using the system perspective to build a useful frame of reference of safety management using non- nuclear organizations; this as a way to create models useful for the nuclear power industry but based on general understanding of the concept of safety management. The chosen organizations are used extensively to...
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 -
02:4 Qualification of Electrical Components in Nuclear Power Plants. Management of Ageing
The work was finished and reported in Swedish in a limited publication 2000, Ingemansson Rapport H-14061-r-I. As the performed work was regarded to be of more general interest it is published again as a research report by the Swedish Nuclear Power Inspectorate. To be used in the international cooperation in nuclear safety it was also translated into English by the inspectorate, which is this...
Innehållstyp: Publikationer -
2001:23 Interactions of Severe Accident Researchand Regulatory Positions (ISARRP)
This project, started on April 1, 1999, had the specific objectives of determining whether; (i) the focus of the severe accidents (SA) research is consistent with that of the regulatory authorities, (ii) the results obtained so far by SA research satisfy the regulatory concerns, (iii) the future programs, envisaged will address the potential regulatory needs into next century, and (iv) how...
Innehållstyp: Publikationer -
2014:15 Multivariatanalys av radioaktivitetsdata från utsläpp till luft och vatten från Studsviksanläggningarna och i omgivningen av Studsvik
Syftet med denna studie var att undersöka korrelationer mellan uppmätt utsläppt radioaktivitet från Studsviksanläggningarna och uppmätta halter radioaktivitet i omgivningen av Co-60, Cs-134, Cs-137, Eu-152, Eu-154 och Mn-54. Ett mål var att se hur olika provslag i omgivningen av Studsvik fungerar som indikatorer för den uppmätta utsläppta radioaktiviteten.
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 -
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 -
2009:38 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stages 14 and 15
This report constitutes Stages 14 and 15 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Stage 14 was a full one-year project, whereas Stage 15 consisted of a half-year project. Results up to Stage 13 were reported in SKI reports, as listed below and in the Summary. The results have also been published in...
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 -
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