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  • 2007:19 An Applied Study of Implementation of the Advanced Decommissioning Costing Methodology for Intermediate Storage Facility for Spent Fuel in Studsvik, Sweden with special emphasis to the application of the Omega code

    The aim of this applied study has been to describe in a systematic way an appropriate methodological sequence for cost estimation of crucial parameters in decontamination and decommission processes. The work has been limited to older nuclear installations and facilities. Furthermore, it may be envisaged that the process of estimating the parameters of decommissioning is one of the main issues...

    Innehållstyp: Publikationer
  • 2009:22 Alternative modelling of brittle structures in a sub-area of the SKB candidate area at Forsmark, eastern Sweden

    A reasonable understanding of the character of the bedrock hosting a deep geological repository, i.e. the natural barrier, is an important component in the safety assessment of the deep geological repository for spent nuclear fuel. The structures in the rock, together with the regional stress field, affect the mechanical stability of the bedrock and the ground water transport within the...

    Innehållstyp: Publikationer
  • 2010:23 On Decommissioning Costs of the Ranstad Site

    A demanding task for the present generation is to assure that appropriate financial resources are injected into the Swedish Nuclear Waste Fund. It will thereby be possible for coming generations to undertake efficient measures in the decommissioning and dismantling of older nuclear facilities. To undertake such measures in the context of Swedish as well as European environmental and health...

    Innehållstyp: Publikationer
  • 2012:25 Workshop on Seismology

    This report summarizes the issues discussed at the workshop and extracts the essential viewpoints that have been expressed. The report is not to consider as a comprehensive record of all the discussions at the workshop and individual statements made by workshop participants should be regarded as opinions rather than proven facts. This report includes, apart from the workshop synthesis, the...

    Innehållstyp: Publikationer
  • 2006:36 Mechanical Integrity of Canisters Using a Fracture Mechanics Approach

    This report presents the methods and results of a research project for Swedish Nuclear Power Inspectorate (SKI) about numerical modeling of mechanical integrity of cast-iron canisters for the final disposal of spent nuclear fuel in Sweden, using combined boundary element (BEM) and finite element (FEM) methods The objectives of the project are: 1) to investigate the possibility of initiation...

    Innehållstyp: Publikationer
  • 2019:15 3D Thermo-Mechanical Coupled Modelling of Thermo-Seismic Response of a Fractured Rock Mass related to the Final Disposal of Spent Nuclear Fuel and Nuclear Waste in Hard Rock

    SSM perspective Background When assessing the long-term safety of a repository for spent nuclear fuel it is important to consider future earthquakes. Previous studies by Yoon et al. (2014, SSM Report 2014:59) and (2016, SSM Report 2016:23) investigated the fracture responses due to heat and earthquakes at major deformation zones using a 2D thermo-mechanical coupled model that uses a Particle...

    Innehållstyp: Publikationer
  • 2020:07 Fibre Clogging in Nuclear Power Plants

    SSM perspective Background Emergency core cooling systems in boiling- and pressurized water reactors use strainers. Their purpose is to out foreign material suspended in the cooling water so this material does not reach the reactor. After the 1992 event at Barsebäck nuclear power plant when the strainers of the emergency cooling system was clogged due to fibers in the cooling water, all...

    Innehållstyp: Publikationer
  • 2021:01 In situ NMR condition monitoring of cable insulations in Nuclear Power Plants

    SSM perspective Background As the nuclear power plants are ageing, it is important to verify that every component installed can function safely in the intended environment. Cables are among the most common components in a nuclear power plant and are required to function during normal operation as well as in the event of an accident. There is a need within the nuclear industry for...

    Innehållstyp: Publikationer
  • 2021:02 On Water Induced Sensitization of Ni (Fe,Cr) alloys towards Stress Corrosion Cracking in LWR Piping from 1st Principles Modelling

    SSM perspective Background In Swedish Light Water Reactors (LWR), stress corrosion cracking of reactor components and welds occurs from time to time. As the nuclear power plants are ageing, it is essential to study and further understand the mechanism for environmentally induced sensitization. Natural cracking is a phenomenon that is difficult to predict and very hard to study since it occurs...

    Innehållstyp: Publikationer
  • Hälsodeklaration för arbete med joniserande strålning

    Strålsäkerhetsmyndighetens föreskrifter (SSMFS 2018:1) om grundläggande bestämmelser för tillståndspliktig verksamhet med joniserande strålning ställer krav på ett giltigt tjänstbarhetsintyg. Läkarundersökningen görs med ett intervall som bestäms av läkaren i samråd med arbetstagaren. Däremellan...

    Innehållstyp: Publikationer