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Din avgränsning ger 565 träffar.

• 2013:25 Anpassning av utbildning till följd av anläggningsförändringar

  Studien baseras på dokumentstudier och intervjuer av personer inom kärnkraftindustrin men även med motsvarande roller inom flyg, petrokemi och massaindustri. De intervjuade har nyckelroller inom simulatorträningen i respektive industri. Inom kärnkraften har personer från ett verk samt från verkens gemensamma utbildningsorganisation intervjuats. De undersökta...

  Innehållstyp: Publikationer

• 2013:29 Regulatory Approaches in Nuclear Power Supervision

  The objective of this follow-up study was to support SSM in further understanding regulatory approaches and how they can be combined as part of effective strategies. The survey was intended to assist SSM in identifying current standards, experiences, and practices in the regulation of nuclear power plants. The results will also be valuable for the participating authorities as well as other...

  Innehållstyp: Publikationer

• 2014:06 Dimensionering av nukleära byggnadskonstruktioner (DNB)

  Syftet med detta projekt är att baserat på Eurokoderna ta fram principer och regler för analys och dimensionering av reaktorinneslutningar och andra byggnadskonstruktioner vid svenska kärnkraftanläggningar. I rapporten beskrivs bl.a. följande: Grundläggande dimensioneringsprinciper kopplade till Boverkets föreskrifter och allmänna råd om tillämpning...

  Innehållstyp: Publikationer

• 2013:24 Modelling of nuclear fuel cladding under loss-of-coolant accident conditions

  We present a unified model for calculation of zirconium alloy fuel cladding rupture during a postulated loss-of-coolant accident in light water reactors. The model treats the Zr alloy solid-to-solid phase transformation kinetics, cladding creep deformation, oxidation and rupture as a function of temperature and time in an integrated fashion during the transient. The fuel cladding material...

  Innehållstyp: Publikationer

• 2015:46 Assessment of data and criteria for cladding burst in loss-of-coolant accidents

  Ali R. Massih, Lars Olof Jernkvist SSM English...

  Innehållstyp: Publikationer

• 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

• 2008:30 A model for fission gas release from mixed oxide nuclear fuel

  Nuclear fuel containing mixed oxide (MOX) pellets have been used since the 1960's. MOX fuel pellets are made from a mixture of uranium and plutonium oxide. MOX allows the large quantities of fissile isotopes produced and remaining in spent nuclear fuel from light water reactors to be recycled. Producing MOX fuel can be seen as a method to more efficiently use the natural uranium since...

  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

• SSM Report 2008:01 A combined deterministic and probabilistic procedure for safety assessment of components with cracks – Handbook

  SSM has supported research work for the further development of a previously developed procedure/handbook (SKI Report 99:49) for assessment of detected cracks and tolerance for defect analysis. During the operative use of the handbook it was identified needs to update the deterministic part of the procedure and to introduce a new probabilistic flaw evaluation procedure. Another identified need...

  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