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2005:65 Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Cos RD&D Programme 2004
SKI English...
Content type: Publications -
01:45 Composition of Whiskers Grown on Copper in Repository Environment
Hans-Peter Hermansson, Peeter Tarkpea, Stellan Holgersson SKI English...
Content type: Publications -
02:02 R2/R0-WTR Decommissioning Cost Comparison and Benchmarking Analysis
Dr. Geoff Varley, Chris Rusch SKI English...
Content type: Publications -
01:24 Final Disposal of Spent Nuclear Fuel in Sweden
Hólmfríður Bjarnadóttir, Tuija Hilding-Rydevik SKI English...
Content type: Publications -
01:03 SKIs and SSIs Joint Review of SKBs Safety Assessment Report, SR 97
SKI,SSI English...
Content type: Publications -
02:53 SFR 1 Vault Database
David Savage, Mike Stenhouse SKI English...
Content type: Publications -
2016:04 Uncertainty assessment of the SCANAIR V_7_5 computer program in analyses of BWR reactivity initiated accidents
In this work, we assess uncertainties that can be expected in computational analyses of boiling water reactor reactivity initiated accidents with the SCANAIR V_7_5 computer program. The work is intended to supplement a similar uncertainty assessment, focussed on pressurized water reactor accidents, which is currently being organized as an international benchmark exercise by the OECD Nuclear...
Content type: Publications -
2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA
Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to evaluate the PRO-LOCA code. It is a computer code, developed by Battelle in the USA, in which the leak- and rupture probabilities of piping in nuclear power plants are analysed. The pipe systems may contain the damage mechanisms fatigue and/or...
Content type: Publications -
2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA
No guidance documents for risk-informed analysis and assessment of changes in Limiting Conditions for Operation (LCO:s) in TS (Technical Specifications) have been available in the Nordic countries. In the U.S. several guidance documents, primarily developed by the owners groups for PWRs and BWRs, exist. Guidance for analysis of TS changes in this report generally follows the U.S. Regulatory...
Content type: Publications -
2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3
In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...
Content type: Publications