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  • 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
  • 2017:09 Evaluation of the Swedish participation in the Nordic Nuclear Safety Research (NKS) collaboration

    Background NKS is a Nordic collaboration promoting cooperation on nuclear safety and emergency preparedness research. The research program is primarily funded by Nordic radiation safety authorities and ... and responsible ministries. The main purpose of NKS is to finance joint Nordic activities and initiatives, including seminars and workshops, technical reports, exercises and scientific articles. Both radiation...

    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
  • 2017:11 Extended Common Load Model: A tool for dependent failure modelling in highly redundant structures

    treatment of dependent failures is one of the most controversial subjects in reliability and risk analyses. The difficulties are specially underlined in the case of highly redundant systems, when the number ... number of redundant components or trains exceeds four. The Common Load Model (CLM), originally defined in the 70’ies, differs from other CCF models, as it relies on a specific physical analogy. The model...

    Innehållstyp: Publikationer
  • 2007:23 On Safety Management, A Frame of Reference for Studies of Safety Management with Examples From Non-Nuclear Contexts of Relevance for Nuclear Safety

    There they also discuss the pros of using the system perspective to build a useful frame of reference of safety management using non- nuclear organizations; this as a way to create models useful for the ... industry but based on general understanding of the concept of safety management. The chosen organizations are used extensively to illustrate the concept of safety management. Some central themes for the...

    Innehållstyp: Publikationer
  • 2021:03 Updated radiological risk assessment for the “Radon” type surface disposal facility in Chisinau, Moldova

    Sweden and the Republic of Moldova in nuclear and radiological safety and security has been ongoing since 2010, focusing on activities aimed at strengthening the institutional capacity of the National Agency ... Agency for Regulation of Nuclear and Radiological Activities in Moldova (NARNRA) as well as infrastructure development in radioactive waste management, handling and treatment at the Radioactive Waste Management...

    Innehållstyp: Publikationer
  • 2010:42 Using the EPRI Risk-Informed ISI Methodology on Piping Systems in Forsmark 3

    In the SSM regulation SSMFS 2008:13, it is stated that the selection of locations for inspection of mechanical components shall be based upon the risk for core damage or the risk of release of radioactive ... quantitative measures of the relative risk are allowed to be used. So far only the PWRs in Sweden are using a quantitative procedure to evaluate the risk whereas all the BWRs are using a qualitative risk procedure...

    Innehållstyp: Publikationer
  • 2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)

    Although the extent of cracking was rather surprising for a bolt-loaded specimen, the average stress corrosion crack growth rate of 0.5 mm/year over the five-year testing period does not represent an immediate ... immediate concern. The overwhelming part of crack growth can have occurred during a 20 day chloride transient during the third year of exposure because of a condenser leakage after an outage. The test...

    Innehållstyp: Publikationer
  • 2017:34 Human capability to cope with unexpected events

    Background In the light of the Fukushima accident, it stood clear that the challenge of the unexpected is of great importance to both regulators and licensees. For SSM, as for many other national regulators ... regulators, there was a selfevident need to learn more about the capabilities and actions of people when the unexpected arises and conditions are potentially extreme. A task group was set up within the OECD/NEA's...

    Innehållstyp: Publikationer
  • 2012:02 Evaluation of activity build-up experiments

    understand how the water chemistry affects the activity build-up on surfaces in different systems in Swedish nuclear power plants, which in turn provides information on conditions required to reduce the radiation ... about water chemistry conditions preferred to minimize the activity build-up. A number of experiments have previously been performed at Studsvik Nuclear AB. The effects on the activity build-up from iron, nickel...

    Innehållstyp: Publikationer