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Din avgränsning ger 14 träffar.

• 2016:31 Measures and method characteristics for early evaluation of safe operation in nuclear power plant control room systems

  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 ... 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 rooms. Both...

  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 DS ensembles are presented, which can encode up to four moments and represent any kind of probability distribution...

  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 ... 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 from...

  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

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

  Innehållstyp: Publikationer

• 2016:04 Uncertainty assessment of the SCANAIR V_7_5 computer program in analyses of BWR reactivity initiated accidents

  In this work, we assess uncertainties that can be expected in computational analyses of boiling water reactor reactivity initiated accidents with the SCANAIR V_7_5 computer program. The work is intended ... intended to supplement a similar uncertainty assessment, focussed on pressurized water reactor accidents, which is currently being organized as an international benchmark exercise by the OECD Nuclear Energy...

  Innehållstyp: Publikationer

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

  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 ... information regarding the effect of stray currents from high voltage cables on copper corrosion (SSM 2012). SKB therefore has performed an extended study of the effects of high voltage DC power transmission...

  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 ... examine the obtained fatigue cracks with an optical microscope. Objective The present study performs a fractographical examination of the obtained fatigue cracks with the aim of determine where fatigue cracks...

  Innehållstyp: Publikationer

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

  construction and operation of a reposi-tory for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information ... reported in SSM’s Technical Note series. Objective This project is part of SSM:s review of SKB:s license application for final disposal of spent nuclear fuel. The assignment concerns review of creep mechanisms...

  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”

  The general objective of the present project is to provide 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 high voltage DC power transmission on a repository for nuclear fuel. Laust B Pedersen SSM English...

  Innehållstyp: Publikationer