Publications

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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
  • 2007:41 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
  • 2007:39 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
  • 2006:15e Safety and Radiation Protection at Swedish Nuclear Power Plants 2005

    The safety philosophy upon which the Swedish Nuclear Power Inspectorate’s (SKI) supervisory and regulatory activities are based assume that multiple physical barriers will exist and that a plant-specific defence-in-depth system will be implemented at each plant and that the licensee bears the undivided responsibility for safety. The physical barriers are situated between the radioactive...

    Content type: Publications
  • 2006:36 Mechanical Integrity of Canisters Using a Fracture Mechanics Approach

    This report presents the methods and results of a research project for Swedish Nuclear Power Inspectorate (SKI) about numerical modeling of mechanical integrity of cast-iron canisters for the final disposal of spent nuclear fuel in Sweden, using combined boundary element (BEM) and finite element (FEM) methods The objectives of the project are: 1) to investigate the possibility of initiation...

    Content type: Publications
  • 2005:32e Safety and Radiation Protection at Swedish Nuclear Power Plants 2004

    The safety philosophy upon which the Swedish Nuclear Power Inspectorate’s (SKI) supervisory and regulatory activities are based assume that multiple physical barriers will exist and that a plant-specific defence-in-depth approach will be implemented at each plant. The physical barriers are situated between the radioactive material and the plant personnel and surroundings. In the case of...

    Content type: Publications
  • 2005:60 Research and Service Experience with Environmentally-Assisted Cracking in Carbon and Low-Alloy Steels in High-Temperature Water

    In this report, the most relevant aspects of research and service experience with environmentally assisted cracking of carbon and low-alloy steels in high-temperature water are reviewed, with special emphasis on the primary pressure-boundary components of boiling water reactors. The main factors controlling the susceptibility to environmentally assisted cracking under light water reactor...

    Content type: Publications