Filtered generated 90 hits.
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2007:25 Safety Management Characteristics Reflected in Interviews at Swedish Nuclear Power Plants: A System Perspective Approach
184 kB...
Content type: Documents -
2007:02 Stakeholder involvement in Swedish nuclear waste management
324 kB...
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2007:09 DECOVALEX-THMC - Task C
872 kB...
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2007:17 Spent Fuel Dissolution and Source Term Modelling in Safety Assessment
640 kB...
Content type: Documents -
2007:12 Rapport från SSI:s vetenskapliga råd om ultraviolett strålning 2006
442 kB...
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2007:15 Evaluation of the FRAPTRAN -1.3 Computer Cod
The FRAPTRAN-1.3 computer code has been evaluated regarding its applicability, modelling capability, user friendliness, source code structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under reactor power and coolant transients, such as overpower transients, reactivity initiated accidents (RIA),...
Content type: Publications -
2007:26 Safety Culture Enhancement Project Final Report
At the International Conference on Safety Culture in Nuclear Installations, organized by IAEA in 2002, one concluding remark was that the regulators should encourage a sincere interest in safety culture among licensees. In line with this SKI wanted to explore a proactive path to encourage the licensees in their safety culture work. SKI also had the ambition to gain more information on the MTO...
Content type: Publications -
2007:31e Safety and Radiation Protection at Swedish Nuclear Power Plants 2006
Safety related problems in the electric systems of the Forsmark 1 reactor were the dominant event in Swedish nuclear power plants in 2006. The incident has had a significant impact on our attitude towards the reliability of how safety systems function both in Sweden and abroad. In connection with SKI’s review of the incident it was found that the company’s management system was not...
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 -
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