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Din avgränsning ger 571 träffar.

• 2016:39 Recommended residual stress profiles for stainless steel pipe welds

  Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to analyze stainless steel pipe welds to obtain good estimations of weld residual stress (WRS) distributions. Detailed knowledge of the residual stress field in different types of welds is important since they can have substantial influence on...

  Innehållstyp: Publikationer

• 2015:44 Krav på funktion, konstruktion och provning av reaktorinneslutningar

  Bakgrund I Sverige behöver SSM skaffa vidare kunskap inom olika områden inom nukleära byggnadskonstruktioner bl.a. reaktorinneslutningar. Syfte Syftet med projektet "Krav på funktion, konstruktion och provning av reaktorinneslutningar" är att sammanställa information för att belysa viktiga reaktorinneslutningsfrågor vid byggnation. Den sammanställda...

  Innehållstyp: Publikationer

• 2015:11 Investigation of the Distribution of Phosphorus in Copper

  Two copper alloys containing different amounts of phosphorus, 6 and 80 wtppm, respectively, have been investigated. The matrix of both alloys was analysed using atom probe tomography (APT). The matrix P concentration in the 80 wtppm P mate- rial was about the same as the bulk concentration and it was therefore concluded that the majority of the P atoms resides in the matrix. Grain boundaries...

  Innehållstyp: Publikationer

• 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

• 2016:27 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

• 1997:05 SKI SITE-94

  The Swedish Industry program for deep geological disposal of spent nuclear fuel and high-level radioactive waste is now in the early stages of the site selection process, with feasibility studies underway in 5 to 10 municipalities. According to the Swedish Nuclear Fuel and Waste Management Co., SKB (SKB RD&D Programme, 1995), the ongoing siting process involves selection of two sites for...

  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