Din avgränsning ger 259 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

  Innehållstyp: Publikationer

• 2016:37 PARTRIDGE project: Review and evaluation of the probabilistic fracture mechanics code PRO-LOCA

  Background The Swedish Radiation Safety Authority (SSM) and the Swedish nuclear power plant owners have financed Inspecta Technology in Sweden to evaluate the PRO-LOCA code. It is a computer code, developed by Battelle in the USA, in which the leak- and rupture probabilities of piping in

  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

  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

  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

  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.

  Innehållstyp: Publikationer

• 2016:26 Ensemble for deterministic sampling with positive weights

  The aim of this project is to find a reliable method for determining an ensemble for Deterministic Sampling with only positive weights. This report is intended to work as a presentation of the project, as well as to work as a beginner’s guide to DS. In the report several methods for generating

  Innehållstyp: Publikationer

• 2016:23 Technical Note, Modelling of the thermal evolution of the KBS-3 repository at Forsmark and associated induced seismic activity

  Main Review Phase Introduction The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of the KBS-3 repository for spent nuclear fuel and for an encapsulation

  Innehållstyp: Publikationer

• 2016:16 Technical Note, Possible influence from stray currents from high voltage DC power transmission on copper canisters

  Main Review Phase Introduction As part of the Swedish Radiation Safety Authority’s (SSM) review of the Swedish Nuclear Fuel and Waste management company (SKB) license application for a final storage for spent nuclear fuel, SSM has asked for complementary information regarding the effect of

  Innehållstyp: Publikationer