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  • 2013:05 Acceleratordrivna subkritiska system - en analys med fokus på icke-spridning och exportkontroll

    Den nu resulterande rapporten beskriver översiktligt utrustning och komponenter som behövs för drift av ett acceleratordrivet subkritiskt system, där informationen är baserad på litteraturstudier. Rapporten berör också förutsättningarna för användning av ett sådant system för framställning av klyvbart material, ett resultat...

    Innehållstyp: Publikationer
  • 2015:04 DiD-PSA: Development of a Framework for Evaluation of the Defence-in-Depth with PSA

    The project declares an interpretation of the definitions of Defence in Depth given by IAEA which outline a framework to meet PSA. For each level of defence and combinations of levels, methods to give estimates from a PSA perspective are presented and discussed. One important result is the discussion of the basic definitions and the basis for defence-in-depth, as defined by IAEA, leading to...

    Innehållstyp: Publikationer
  • 2013:32 Upparbetning av utbränt kärnbränsle - En studie med fokus på exportkontroll

    Rapporten beskriver principerna för upparbetning samt egenskaperna hos utbränt kärnbränsle där sammansättningen hos det i reaktorn bildade plutoniumet är av avgörande betydelse för kärnvapenframställning till skillnad från civil upparbetning. Rapporten går igenom ett antal upparbetningsmetoder, både äldre metoder samt nya,...

    Innehållstyp: Publikationer
  • 2015:10 SafePhase: Safety culture challenges in design, construction, installation and commissioning phases of large nuclear power projects

    Different lifecycle phases of a nuclear power plant present new human-technology- organization challenges to regulators and licensees. Organizational processes and practices that have evolved in one phase of development might be dysfunctional for the next phase, and the definition of “good safety culture” in practice might be unclear. The objective of the SafePhase study is to improve the...

    Innehållstyp: Publikationer
  • 2015:09 PROSIR - Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel

    Following an OCDE round robin proposal, 16 participants from 9 countries (USA, Japan, Korea (6 participants), Sweden, Germany, Czech Republic, Spain, EC and France (3 participants)) have been involved in a round robin study called PROSIR, Probabilistic Structural Integrity of a PWR Reactor Pressure Vessel. The PROSIR project started already in 2003 and a final draft version of the main report...

    Innehållstyp: Publikationer
  • 2016:28 Fatigue fracture surface characterization and investigation

    Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to examine the obtained fatigue cracks with an optical microscope. Objective The present study performs a fractographical examination of the obtained fatigue cracks with the aim of determine where...

    Innehållstyp: Publikationer
  • 2016:31 Measures and method characteristics for early evaluation of safe operation in nuclear power plant control room systems

    The Swedish Radiation Safety Authority’s (SSM) experience is that there is a need to develop evaluation methods in parallel with the development of control rooms in conjunction with construction modifications and other changes. This includes more indepth analysis of the methods used today. Another aspect is that conventional methods of evaluating control rooms and issues need to be...

    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
  • 2014:18 Evaluation of the Halden IFA-650 loss-of-coolant accident experiments 2, 3 and 4

    The analytical tools, which are fuel rod computer codes, that Quantum Technologies AB use and develop, contain models of several of the phenomena that are acting on the nuclear fuel (cladding temperature, fission gas driven pressure, strain and stress in the cladding, rod rupture, etc.) and how the separate effects interact in the complex integrated manner. The codes are under constant...

    Innehållstyp: Publikationer