Search

Filtered generated 289 hits.

Sort on:

Relevance Date
  • 2007:06 Probabilistic Safety Goals - Phase 1 -Status and Experiences in Sweden and Finland

    Based on a series of interviews and on literature reviews as well as on a limited interna- tional over-view, the project has described the history and current status of safety goals in Sweden and Finland. A number of issues were discussed more in detail, including the status of the safety goals in view of the fact that they are often exceeded, strategies for handling violations of safety...

    Content type: Publications
  • 2011:29 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stage 17

    This report constitutes Stage 17 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Results up to Stage 16 were reported in SKI and SSM reports, as listed below and in the Summary. The results have also been published in international journals and have been included in both licentiate- and doctor’s degrees.

    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
  • 2011:17 Structural Health Monitoring of Piping in Nuclear Power Plants – A Review of Efficiency of Existing Methods

    SSM needs to acquire knowledge about new applied Non-Destructive Engineering (NDE) techniques and their efficiency. One area that is discussed more frequently is Structural Health Monitoring (SHM). SSM needs to investigate the international experiences of SHM from the nuclear industry. SSM also wants to have more information about the capabilities and the limitations of NDE methods The first...

    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
  • 2011:33 Mathematical modelling of ultrasonic testing of components with defects close to a non-planar surface

    The report describes work that has been performed in order to model ultrasonic testing of components that contain a defect close to a non-planar surface. The studies have been performed in both 2D and 3D, and in 2D in both the anti-plane (SH) and the in-plane (P-SV). The results show that the presence of a non-planar back wall can reduce the detectability of defects close to the surface. The...

    Content type: Publications
  • 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
  • 2011:19 Experimental evaluation of influence from residual stresses on crack initiation and ductile crack growth at high primary loads

    Cracked components are usually subjected to loads causing both primary and secondary stresses, e.g. welding components. Engineering assessment approaches, such as the ASME XI code and the R6 procedure, are commonly used to conduct integrity assessment of such components. There has been an ongoing debate how to treat secondary stresses using engineering assessment methods. The nature of these...

    Content type: Publications
  • 2012:71 Identification of Brittle Deformation Zones and Weakness Zones

    In preparation for the review of Swedish Nuclear Fuel and Waste Management Company’s (SKB) license application for disposal of spent nuclear fuel, Swedish Radiation Safety Authority (SSM) is conducting studies to evaluate the performance of the multi-barrier principle on which the KBS-3 concept is based. Copper canisters containing the spent nuclear fuel are placed into granitic bedrock at...

    Content type: Publications
  • 2012:61 Geochemical Constraints on Buffer Pore Water Evolution and Implications for Erosion

    Mineralogical data from the Forsmark Site show that smectite and calcite occur at all depths in Forsmark fractures, with no evidence for removal/dissolution by previous glacial episodes. This natural analogue information implies that these minerals may not have been eroded/dissolved during previous glacial episodes. Available thermodynamic data suggest that repository-depth Forsmark...

    Content type: Publications