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  • 2015:43 Robust structural verification of pressurized nuclear components subjected to ratcheting

    2015:43 ISSN: 2000-0456 Available at www.stralsakerhetsmyndigheten.se Robust structural verification of pressurized nuclear components subjected to ratcheting 2015:43 Author: Mikael Möller Andreas ... Pressurized components in nuclear applications that are subjected to cyclic loading may exhibit progressive deformation, so called structural ratcheting. If the component is made out of a material that are...

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

    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 ... report of the project was is- sued in 2011. Objectives The primary objective has been to issue recommendations of best prac- tices when performing probabilistic analysis of a reactor pressure vessel containing...

    Innehållstyp: Publikationer
  • 2015:43 Robust structural verification of pressurized nuclear components subjected to ratcheting

    Pressurized components in nuclear applications that are subjected to cyclic loading may exhibit progressive deformation, so called structural ratcheting. If the component is made out of a material that are ... ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and material models currently used for structural verification of pressurized nuclear components...

    Innehållstyp: Publikationer
  • 2015:07 TEM-lamella lift-out from the crack tip region of Alloy 600 for high resolution electron microscopy examination

    contributes to the development of a method for high-quality TEM lamella preparation from crack tip regions of nuclear materials. A standard compact tension (CT) specimen of Alloy 600 previously tested for ... corrosion crack growth in simulated PWR primary water was used to demonstrate the benefit of the proposed method. This report describes the procedure for cutting the CT specimen in order to access the crack...

    Innehållstyp: Publikationer
  • 2015:47 GEMA-Site 1: Model description and example application

    Background In 2011 the Swedish Nuclear Fuel and Waste Management Company (SKB) submitted an assessment of the long-term safety of a KBS-3 geological disposal facility for spent nuclear fuel in Forsmark ... application of SKB to build such a final disposal facility. The biosphere dose assessment carried out as part of SR-Site features a highly detailed model of the evolution of the landscape in Forsmark area...

    Innehållstyp: Dokument
  • 2015:53 Ductile tearing – Micromechanical analyses and experimental study

    perspective Background In a previous published research work (SSM 2014:28) it was studied how the Gurson model will be used to predict ductile crack growth at the presence of secondary stresses, e.g ... initiation of crack growth in specimens containing residual stresses. Since the initiation of crack growth is rarely critical for ductile materials, it was of interest to predict the correlation of load-deformation...

    Innehållstyp: Dokument
  • 2015:22 Technical Note, Further modelling and sensitivity study using the GEMA-Site “alternative biosphere models” and review of material from SKB’s RFI response

    Further modelling and sensitivity study using the GEMA-Site “alternative biosphere models” and review of material from SKB’s RFI response Main Review Phase 2015:22 Author: Ryk Kłos SSM 2015:22 SSM ... construction and operation of a repository for spent nuclear fuel and for an encapsu- lation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information...

    Innehållstyp: Dokument
  • 2015:47 GEMA-Site 1: Model description and example application

    Background In 2011 the Swedish Nuclear Fuel and Waste Management Company (SKB) submitted an assessment of the long-term safety of a KBS-3 geological disposal facility for spent nuclear fuel in Forsmark, ... application of SKB to build such a final disposal facility. The biosphere dose assessment carried out as part of SR-Site features a highly detailed model of the evolution of the landscape in Forsmark area...

    Innehållstyp: Publikationer
  • 2015:54 Retinal injuries from handheld lasers: An updated report

    perspective Background The safety limits that exist for human exposure of laser radiation are essential to reduce the risk of injuries. These values, however, give very little information on what tissue ... related to the impairment of the vision. This type of relation- ship between an imaginary exposure and a subsequent disability is very useful in the risk assessments that are made in the authority’s supervi-...

    Innehållstyp: Dokument
  • 2015:32 Safe and responsible management of spent nuclear fuel and radioactive waste in Sweden - National Plan

    The National Plan describes the general principles (national policies), the legislative, regulatory and organizational framework (national framework) as well as the strategies (national ... strategies (national programme and systems) that control the safe and responsible management of spent nuclear fuel and of all types of radioactive waste in Sweden, now and in the future. Flavio Lanaro (project...

    Innehållstyp: Publikationer