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  • 2021:04 Calibration of models for cladding tube high-temperature creep and rupture in the FRAPTRAN-QT-1.5 program

    SSM perspective Background The Swedish Radiation Safety Authority (SSM) follows the research on fuel performance closely. One aspect that is currently being studied in several research projects is the ... risk of release of fragmented fuel into the primary coolant in case of an accident. This risk depends on complex conditions where one is the possibility and size of a rupture of the fuel rod cladding tube...

    Innehållstyp: Publikationer
  • Årsredovisning 2011

    robusta, men identifierar också områden där det går att ytterligare stärka anläggningarnas robusthet. SSM bedömer att inga av de nu identifierade bristerna och åtgärdsbehoven är av sådan karaktär att anläggningarnas ... bedömningar har sammanställts i en nationell rapport som lämnades till EU-kommissionen vid årsskiftet. SSM har också som organisation kunnat dra lärdomar av olyckan i Fukus- hima. Vi har identifierat förbättringsområden...

    Innehållstyp: Dokument
  • 99:18 SKI:s och SSI:s granskning av SKB:s systemredovisning i FUD-program 98

    flera tillfällen samt att detaljeringsgraden beror av tillfället. SKB delar denna uppfattning, se t.ex. s 1-5 i SKBs rapport Systemredovisning av djupförvaring enligt KBS-3-metoden, (SKB, 1998). Ur SKIs och ... SKB Rapport R-98-11, Svensk Kärnbränslehantering AB, Stockholm, 1998. Ekendahl A-M och Pettersson S, Säkerheten vid transport av inkapslat bränsle, SKB Rapport R-98-14, Svensk Kärnbränslehantering AB...

    Innehållstyp: Dokument
  • 2010:46 Development of the PRO-LOCA Probabilistic Fracture Mechanics Code, MERIT Final Report

    Swedish Radiation Safety Authority, SSM. The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the SSM. Background The MERIT project ... more of a research code than a regulatory tool. Effects on SSM supervisory and regulatory task The results of this project will be used by SSM for the assessment of detec- ted cracks in nuclear piping...

    Innehållstyp: Dokument
  • 2013:27 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures

    Authors: Peter Segle Jessica Strömbro Alexander Wulff Johan Kölfors Albin Larsson Robert Persson SSM perspective Background The design codes for anchorage of equipment in concrete structures have ... 349-06 code open up today for a more detailed analysis where the beneficial impact of rein- forcement on anchor capacity can be taken into account. How this analysis can be done is, however, not explicitly...

    Innehållstyp: Dokument
  • 2010:16 Guidance to Risk-Informed Evaluation of Technical Specifications using PSA

    Radiation Safety Authority, SSM. The conclusions and viewpoints presented in the report are those of the author/authors and do not necessarily coin- cide with those of the SSM. SSM Perspective Background ... operational modes and are part of the licensing basis for the plant. The original TS were ba- sed on deterministic analyses and engineering judgments (and to some extent risk evaluations). Existing PSA...

    Innehållstyp: Dokument
  • 02:51 Nuclear Criticality Safety Assessment Using the SCALE Computer Code Package A demonstration based on an independent review of a real application

    Nuclear Criticality Safety Assessment Using the SCALE Computer Code Package A demonstration based on an independent review of a real application Dennis Mennerdahl June 1998 ISSN 1104–1374 ISRN SKI-R-02/51-SE ... Nuclear Criticality Safety Assessment Using the SCALE Computer Code Package A demonstration based on an independent review of a real application Dennis Mennerdahl E Mennerdahl Systems Starvägen 12 SE-183...

    Innehållstyp: Dokument
  • 2017:19 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures, Phase 2

    Phase 2 2017:19 Authors: Peter Segle Pär Ljustell Albin Larsson Johan Kölfors SSM 2017:19 SSM 2017:19 SSM perspective Background In the design of anchorage equipment in concrete structures ... ASCI 349-06 code opens up for a more detailed analysis where the beneficial impact of reinforcement on anchor capacity can be taken into account. How this analysis can be done is, however, not explicitly...

    Innehållstyp: Dokument
  • 2008:57 Discrete Feature Model (DFM) User Documentation

    SKI Perspective Background SKI engages consultants to perform scientific and technical assessments in order to obtain a good scientific and technical basis for monitoring the Swedish nuclear fuel and ...  or piecewise­planar  surface, described at each point   on its surface by effective 2­D parameters of transmissivityξ   T( ), storativity ξ S( ), and transport aperture ξ b( ). Typically these parame...

    Innehållstyp: Dokument
  • 2010:43 Displacement along extensive deformation zones at the two SKB sites: Forsmark and Laxemar

    Radiation Safety Authority, SSM. The conclusions and viewpoints present- ed in the report are those of the author/authors and do not necessarily coincide with those of the SSM. SSM Perspective This report ... Radiation Safety Authority, SSM. The conclusions and viewpoints presen- ted in the report are those of the authors and do not necessarily coincide with those of the SSM. Background The Fennoscandian...

    Innehållstyp: Dokument