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  • 2012:48 Technical Note, Use of Solubility Limits in the SR-Site Safety Assessment

    In a radioactive waste disposal environment, in some potential situations (scenarios) a disposed canister containing spent fuel may be breached and the fuel may come into contact with groundwater. The ... concentration of a radioactive element such as uranium may rise to a level where the solution is saturated. No more of the radioactive element may dissolve and a precipitated solid may be formed. In this situation...

    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
  • 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
  • 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
  • 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
  • 2013:37 Technical Note, Rock Mechanics – Evolution of fracture transmissivity within different scenarios in SR-Site – Main Review Phase

    The current review assignment consists of a literature review and independent modeling for assessing the importance of fracture transmissivity change especially driven by shear loading due to SKB’s thermal ... repository at Forsmark. In the first part of the report, SKB’s laboratory experiments on shear fracture dilation and extensive literature review on shear fracture dilation in-situ and in laboratory under moderate...

    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
  • 2008:47 Selected Models for Key Processes in a Nuclear Waste Repository

    conceptual design of the disposal of spent nuclear fuel in Sweden is based on a multibarrier system. In the KBS-3 concept, the bentonite buffer is a barrier with the primary purpose of surrounding and protecting ... minimise the water exchange with the surrounding rock and protect the canister against mechanical damages caused by possible shear movements in the immediate surroundings. For a number of years, the researchers...

    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