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

    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 ... encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information and provide expert opinions on specific scientific and technical issues. The results from...

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

    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 ... high voltage cables on copper corrosion (SSM 2012). SKB therefore has performed an extended study of the effects of high voltage DC power transmission as support for answering SSM. This study has been...

    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 ... aspect is that conventional methods of evaluating control rooms and issues need to be reexamined. SSM has previously provided funding for several individual research projects regarding evaluation of control...

    Innehållstyp: Publikationer
  • 2016:05 Technical Note, Assessment of SKB TR-14-15 Assessment of SKB TR-14-15 “Possible influence from stray currents from high voltage DC power transmission on copper canisters”

    independent review comments for one area of SKB:s post closure safety analysis, SR-Site. With this in mind, the purpose of this report is to review SKB’s presentation on possible influence from stray currents from ... power transmission on a repository for nuclear fuel. Laust B Pedersen SSM English The general objective of the present project is to provide independent review comments for one area of SKB:s post closure safety...

    Innehållstyp: Publikationer
  • 2016:02 Technical Note, An updated review of the creep ductility of copper including the effect of phosphorus

    Background 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 ... As part of the review, SSM commissions consultants to carry out work in order to obtain information on specific issues. The results from the consultants’ tasks are reported in SSM’s Technical Note series...

    Innehållstyp: Publikationer
  • 2016:26 Ensemble for deterministic sampling with 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 DS ensembles are presented, which can encode ... have potential for uncertainty quantification at SSM, in the nuclear power industry and with heavy calculations done in other field. Arne Sahlberg SSM English The aim of this project is to find a reliable...

    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 ... increased the understanding of fatigue critical points in welds, as well as it has increased knowledge on where fatigue cracks initiated and how propagation occur in the welded austenitic stainless steel pipes...

    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 ... 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 fatigue flaw...

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

    methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors. An undesirable ... (WENRA). The major result of the work is the identification of consensus and common technical positions on a set of important licensing issues raised by the design and operation of computer based systems used...

    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 ... continue funding the participation in the Halden Reactor Project. Additionally, the Swedish authority’s funding of research infrastructures in general should be safeguarded by acknowledging this type of investment...

    Innehållstyp: Publikationer