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  • 2012:16 El och kontrollutrustning i kärnkraftverk. Problematik vid utbyte av åldrad utrustning

    Studien visar på ett flertal områden som bör beaktas både hos tillståndshavarna och för framtida tillsynsstrategier för SSM. Flera av områdena har betydelse för säkerheten. Till exempel så framgår att konstruktionsprocessens efterlevnad och genomförande är mycket viktig för säkerheten. Genom att el- och kontrollutrustningen...

    Innehållstyp: Publikationer
  • 2012:07 Implementation of the Master Curve method in ProSACC

    Cleavage fracture toughness data display normally large amount of statistical scatter in the transition region. The cleavage toughness data in this region is specimen size-dependent, and should be treated statistically rather than deterministically. The Master Curve (MC) methodology is a procedure for mechanical testing and statistical analysis of fracture toughness of ferritic steels in the...

    Innehållstyp: Publikationer
  • 2012:01 Kontrollrumskonstruktion – Samverkan mellan olika aktörer under konstruktion av nya och moderniserade kontrollrum

    SSM har under senare år ställt högre krav på konstruktion och utformning av kärnkrafts-anläggningarna. Detta tillsammans med kärnkraftsindustrins uppgraderingar av effekten har medfört ett stort antal anläggningsändringar. En del av dessa anläggningsändringar har påverkan på kontrollrum och manöverutrustning samt på...

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • 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.

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • 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...

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

    The MERIT project has been an internationally financed program with the main purpose of developing probabilistic models for piping failure of nuclear components and to include these models in a probabilistic code named PRO-LOCA. The principal objective of the project has been to develop probabilistic models for piping failure of nuclear components and to include these models in a...

    Innehållstyp: Publikationer
  • Forskningsutlysning 2026

    Strålsäkerhetsmyndigheten (SSM) utlyser härmed forskningsmedel inom strålsäkerhet och nukleär icke-spridning. Totalt planerar SSM att avsätta 81 miljoner kronor för användning under 2026–2031. Ansökan ska vara SSM tillhanda senast den 21 april 2026.

  • 2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3

    In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive substances. Both qualitative and quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk...

    Innehållstyp: Publikationer