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  • 2009:16 Influence of Hardening Model on Weld Residual Stress Distribution

    Weld residual stresses have a large influence on the behavior of cracks growing under normal operation loads and on the leakage-flow from a through-wall crack. Accurate prediction of these events is important in order to arrive at proper conclusions when assessing detected flaws, for inspection planning and for assessment of leak-before-break margins. Therefore, it is very important to have...

    Innehållstyp: Publikationer
  • 2009:38 Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods, Stages 14 and 15

    This report constitutes Stages 14 and 15 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. Stage 14 was a full one-year project, whereas Stage 15 consisted of a half-year project. Results up to Stage 13 were reported in SKI reports, as listed below and in the Summary. The results have also been published in...

    Innehållstyp: Publikationer
  • 2011:04 Evaluation of the Technical Basis for New Proposals of Fatigue Design of Nuclear Components

    During the recent years fatigue analysis procedures for nuclear components have been investigated. The most common method so far has been the American code ASME III. The basis for the current design procedures in ASME III is quite old and has now been evaluated against modern data leading to the proposal of modified design curves. Also the effect of the environment has been the subject of...

    Innehållstyp: Publikationer
  • 2011:30 A fatigue analysis including environmental effects for a pipe system in a Swedish BWR

    The effect of the environment on fatigue design has been the subject of intense study in USA, Japan and elsewhere. Several reports indicate a potentially large influence of the environment, leading to the proposal of entirely new analysis procedures. SSM has in an earlier project sponsored research to evaluate the technical basis for these proposals, see SSM Research Report 2011:04. In the...

    Innehållstyp: Publikationer
  • 2010:45 Evaluation of models for cyclic plastic deformation – A literature study

    Analysis of nuclear components subjected to cyclic plastic deformation is normally based on the American standard ASME III. With the focus to improve the modeling of the stress-strain response under non-monotonic loading, several models for the analysis of cyclic plastic deformation have been developed in recent years. However, experience shows that the analysis and evaluation of plastic...

    Innehållstyp: Publikationer
  • 2014:33 Technical Note, Reproduction of SKB’s Canister Failure Calculations - What-If and ‘Residual’ Scenario to Illustrate Barrier Functions

    The Swedish Nuclear Fuel and Waste Management Company (SKB) included analysis of a range of scenarios in its SR-Site report.  SKB grouped these scenarios into two categories—main and residual.  The main scenario included a likely scenario (corrosion failure) and a less probable scenario (seismicity-induced shear failure).  The residual scenario included two unlikely scenarios—isostatic-load...

    Innehållstyp: Publikationer
  • 2012:53 Technical Note, Review of Engineering Geology and Rock Engineering aspects of the operation and closure of a KBS-3 repository at the Forsmark site – Initial Review Phase

    SRK Consulting (UK) Limited (SRK) has reviewed the Engineering Geology and Rock Engineering aspects of the operation and closure of a KBS-3 repository at the Forsmark site in Sweden. The review assignment is part of a Swedish Radiation Safety Authority (SSM) Initial Review Phase. The review was carried out by David Saiang (PhD) on behalf of SRK. Therefore some of the views expressed in the...

    Innehållstyp: Publikationer
  • 2015:48 Technical Note, Supplementary review of SKB’s further RFI response

    Bakgrund Strålsäkerhetsmyndigheten (SSM) granskar Svensk Kärnbränslehantering AB:s (SKB) ansökningar enligt lagen (1984:3) om kärnteknisk verksamhet om uppförande, innehav och drift av ett slutförvar för använt kärnbränsle och av en inkapslingsanläggning. Som en del i granskningen ger SSM konsulter uppdrag för att inhämta...

    Innehållstyp: Publikationer
  • 2014:22 Technical Note, Workshop on seismic hazard at Forsmark

    This report describes the outcome of the workshop organized by SSM on seismic hazard at Forsmark that was held in Stockholm on the 4 and 5 of June, 2013. The report summarizes the issues discussed and extracts the essential viewpoints that have been expressed. It should not be considered as a comprehensive record of all the discussions at the workshop and individual statements made by...

    Innehållstyp: Publikationer
  • 2014:50 Technical Note, A Study of Availability of Fuel Data for Sweden’s Spent Nuclear Fuel

    The study covers all types spent fuel planned to be placed in the final repository. It was carried out by selecting a sample of spent fuel and investigating the information available at the Nuclear Power Plants (NPP’s) in Sweden, the Central interim storage facility (Clab) and Studsvik. The results indicate that the required data is available and can be obtained for fuel unloaded after 1980.

    Innehållstyp: Publikationer