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Din avgränsning ger 571 träffar.

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

  This report 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 stress 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...

  Innehållstyp: Publikationer

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

  Background 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 deformation hardening, it may also exhibit material ratcheting. The combined effects of structural- and material ratcheting are not taken into account in the methods and 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

• 2016:25 Licensing of safety critical software for nuclear reactors

  – Common position of international nuclear regulators and authorised technical support organisations – Revision 2015...

  Innehållstyp: Publikationer

• 2016:29 Evaluation of the Swedish participation in the Halden Reactor Project 2006–2014

  This is a report on the evaluation of the Swedish participation in the Halden Reactor Project 2006-2014. The study has consisted in evaluating the types and extent of added value from the Swedish participation in the Halden Reactor Project, and to determine what additional added value the participation could supply for the Swedish authority. It can be concluded from the study that the impacts...

  Innehållstyp: Publikationer

• 2016:27 Validation of fatigue fracture mechanics approaches

  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 evaluate fatigue flaw tolerance assessments used in industry, which are based on the fracture mechanical approach implemented in ProSACC. Objective The present study aims to validate the used...

  Innehållstyp: Publikationer

• 1990:18 Some Estimates of the Total NuclideInventory in the Year 2100 from Swedish Nuclear Power Production

  The total nuclide inventory in spent fuel from the swedish nuclear power programme has been estimated for three cases. All reactors were arrumed to operate until the year 2010 and then shut down simultaneously. All fuel used was assumed to be based on enriched natural uranium. The reactors were assumed to shut down after 25 years of commercial operation, but not later than in the year 2010.

  Innehållstyp: Publikationer

• 96:41 SKIs utvärdering av SKBs FUD-program 95

  Sammanställning av remissvar...

  Innehållstyp: Publikationer

• 96:49 SKIs utvärdering av SKBs FUD-program 95

  Sammanfattning och slutsatser...

  Innehållstyp: Publikationer

• 96:48 SKIs utvärdering av SKBs FUD-program 95

  Gransknings-PM...

  Innehållstyp: Publikationer