Filtered generated 401 hits.
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2007:14 Review of experimental data for modelling LWR fuel cladding behaviour under loss of coolant accident conditions
This project has contributed to the research goal of giving a basis for SKIs supervision by means of evaluating experimental data and modelling the nuclear fuel cladding during a design base accident. The project has also contributed to the research goal to develop the competence about licensing of fuel at high burnup, which is an important safety issue. The results are useful as such, but...
Content type: Publications -
2007:39 Influence of Crack Morphology on Leak Before Break Margins
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...
Content type: Publications -
2007:37 Identification of Common Cause Initiating Events Using the NEA IRS Database
The study carried out within the framework of this project is a continuation of work conducted for SKI in 1998 on the identification of Common Cause Initiators based on operational events documented in the NEA Incident Reporting System (IRS). This project covered the events reported in the IRS database with the incident date in the period of 1980- 01-01 – 2006-11-15. The events of highest...
Content type: Publications -
2007:24 Safety Management in Non-Nuclear Contexts Examples from Swedish Railway Regulatory and Company Perspectives
The authors describe important features of safety management and the results are modelled according to the systems perspective developed. These are definitions of safety management, the structure of the organizations, organizational change, regulatory and operational activities, safety strategy, threats to safety, information management and feedback, incident and accident reporting, and...
Content type: Publications -
2007:25 Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach
The study used the themes identified in an earlier study: definitions of safety management, the structure of the organizations, organizational change, regulatory and operational activities, safety strategy, threats to safety, information management and feedback, incident and accident reminders on different aspects of safety management in the nuclear context. reporting, and measurement of...
Content type: Publications -
2007:41 Dependency Analysis Guidence, Nordic/German Working Group on Common cause Failure analysis Phaase 1 project report: Comparison and application to test cases
The report “Nordic/German Working Group on Common cause Failure analysis. Phase 1 project report: Comparisons and application to test cases” presents a common attempt by the authorities and the utilities to create a methodology and experience base for defence and analysis of dependent failures. The performed benchmark application has shown that how the data is interpreted is of significant...
Content type: Publications -
2025:01 Safety Concept Evaluation with Failure Tolerance Analysis
SSM perspective Background One of the most important design principles to achieve high safety function dependability is the use of redundancy to be single-fault tolerant. In turn, redundancies become effective by applying additional design principles such as physical and functional separation and diversity. License holders of nuclear power reactors must demonstrate that requirements are met,...
Content type: Publications -
2025:03 APRI-11 – Final Report
SSM perspective Background The Swedish Radiation Safety Authority together with the Swedish Power companies operating nuclear power reactors in Sweden have since early 1990’s provided financial support for severe accident research at KTH and Chalmers. The research was initiated almost directly after the installation of severe accident management system and strategy, as filtered containment...
Content type: Publications -
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 -
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