Filtered generated 403 hits.
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1997:40 Aging of Electrical Components in Nuclear Power Plants
The purpose of the study reported in SKl Technical Report 93:39 was to evaluate qualification methods for application to components intended to be installed in the containment of nuclear power plants. The study included application of Arrhenius' criterion for thermal aging as well as methodologies for updating (curve-matching, ongoing qualification). This report reviews the results of...
Content type: Publications -
1997:12 Study of International Published Experiences in Joining Copper and Copper-alloys
This study has revealed a number of joining processes to be used when manufacturing copper-canisters for the final storage of high level nuclear waste. However, the decision on which material and which joining process to be used has to be based on the design criterions. The welding procedure has to be qualified i.e, it shall be demonstrated whether the procedure is capable of fulfilling...
Content type: Publications -
99:08 Human Factors Aspects of Non-Destructive Testing in the Nuclear Power Context
J. Enkvist, A. Edland, O. Svenson SKI English...
Content type: Publications -
99:34 APRI 3 - Accident Phenomena of Risk Importance
SKI English...
Content type: Publications -
1995:60 Reliability of Piping System Components -Volume 3: A Bibliography of Technical Papers and Reports Related to Piping Reliability
Reflecting on older analysis practices, passive components failures seldom receive explicit treatment in PSA. to expand the usefulness of PSA and to raise the realism in plant and system models the Swedish Nuclear power Inspectorate has undertaken a multi-year research project to establish a comprehensive passive components database, validate failure rate parameter estimates and model...
Content type: Publications -
2024:10 Computational analysis of high-burnup fuel rod behaviour in PWR large-break LOCA
SSM perspective Background Quantum Technologies AB (QT) has for many years developed computational models for the thermomechanical behaviour of nuclear fuel in events such as LOCA and RIA. The research projects have been based on evaluations of tests on nuclear fuel in Halden Reactor Project (HRP) and Studsvik Cladding Integrity Project (SCIP). The models developed by QT enable analyses and...
Content type: Publications -
2025:08 Carbon-14 in the marine environment of Ringhals nuclear power plant
Report for project SSM2022-4035...
Content type: Publications -
New wide call to strengthen research in nuclear power, waste management, radiation protection and nuclear non-proliferation
The Swedish Radiation Safety Authority is launching a wide research call covering four areas within radiation safety, including skills supply, nuclear non-proliferation, and the final disposal of nuclear waste. In total, the authority plans to allocate SEK 81 million for research during the period 2026–2031. International institutions are also eligible to apply for funding from one of the...
Content type: News -
Final repository for radioactive waste and spent nuclear fuel
One of the duties of the Swedish Radiation Safety Authority is to review the final disposal applications submitted to the Authority by Svensk Kärnbränslehantering AB (SKB). We review the applications with reference to the Swedish Act on Nuclear Activities and against our regulations, and issue pronouncements to the Swedish Government, which then makes licensing decisions.
Content type: Regular Pages -
2026:06 A Human Reliability Analysis (HRA) Taxonomy for Small Modular Reactors (SMR) – Part 1 of 2: Mapping the SMR landscape
SSM perspective Background Small Modular Reactors (SMRs) are typically presented as a solution for safe and reliable energy, requiring less time to construct than the traditional large reactors. The inherent safety features, higher levels of automation and increased reliance on passive safety are often held as reasons for fewer operators being needed in the daily operations and for handling...
Content type: Publications