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  • 2017:36 Topical Peer Review 2017 Ageing Management Swedish National Assessment Report

    Executive summary The European Union’s Nuclear Safety Directive 2014/87/EURATOM (NSD) requires the member states to undertake topical peer reviews (TPR) every 6 years with the first starting in 2017. The ... topic for the first topical peer review is ageing management. The Swedish Radiation Safety Authority (SSM) by the provision of the act of nuclear activities (1984:3) can decide by injunction that licensees...

    Innehållstyp: Publikationer
  • 96:40 Status and Use of PSA in Sweden

    The performance and use of PSA:s in Sweden goes back about two decades. During all of this time, the field of PSA has been developing intensively, both internationally and within Sweden. The latest years ... current trends. The aim has been to include a reasonable amount of detail, both on the methods and results in PSA:s performed and on the numerous supporting research programs dealing with various aspects of...

    Innehållstyp: Publikationer
  • 2012:17 Technical Note, Corrosion of copper canister

    corrosion is treated in SKB´s safety assessment as being only dependent on oxygen gas and thus easily estimated by an oxygen mass-balance calculation. This simple model has no scientific support since several ... accelerating effect on copper corrosion. Any corrosion model describing the gaseous copper corrosion period must therefore be based on experimental data. Peter Szakálos and Seshadri Seetharaman SSM English It is...

    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) ... 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 Flow Code...

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

    shear loading due to SKB’s thermal, glacial and earthquake loading scenarios for the KBS-3 repository at Forsmark. In the first part of the report, SKB’s laboratory experiments on shear fracture dilation ... dilation and extensive literature review on shear fracture dilation in-situ and in laboratory under moderate normal stress show that dilation can become important even under moderate normal stress of about 20...

    Innehållstyp: Publikationer
  • 2010:38 The feasibility of Backfilling a Repository of Spent Fuel: An Assessment of Recent Developments by SKB

    In the Review Statement and Evaluation of SKB’s RD & D programme 2007 (SKI Report 2008:48E), the former Swedish Nuclear Power Inspectorate (SKI) commented that considerable work remained to be done for ... for knowledge of both practical management issues on backfilling and analysis of long-term backfill evolution to reach the same level as for the canister and the buffer. SKI considered that the backfill...

    Innehållstyp: Publikationer
  • 2007:02e Radiation Environment in Sweden, summary

    and dose calculations within the field of radiation. The report shows that people’s behaviour in the form of their exposure to the sun and smoking has a major impact on the risk of suffering radiation injuries ... and dose calculations within the field of radiation. The report shows that people’s behaviour in the form of their exposure to the sun and smoking has a major impact on the risk of suffering radiation injuries...

    Innehållstyp: Publikationer
  • 2011:21 Workshop on spent fuel performance and radionuclide chemistry -Rånäs 2010: Assessment of some outstanding issues

    The safety assessment for final disposal of spent nuclear fuel has to comprehensively address the stage when containment barriers have failed and when radionuclide releases occur to the ... 7-9/6-2010 Paul Brown, Christian Ekberg, Christophe Jégou, Günther Meinrath, Heino Nitsche and Bo Strömberg SSM English The safety assessment for final disposal of spent nuclear fuel has to comprehensively address...

    Innehållstyp: Publikationer
  • 2009:33 Workshop on spent fuel performance, radionuclide chemistry and geosphere transport parameters, Lidingö 2008: Overview and evaluation of recent SKB procedures

    suggestions for methodology development and to develop review capability within the SSM. The authors conclude that SKB’s treatment of uncertainty in speciation calculations has improved, but that additional ... featured in SKB safety assessment, but it is not clear that the use of such distributions is based on a firm understanding of its properties. Regarding fuel performance, while safety assessment parameters...

    Innehållstyp: Publikationer
  • 2017:20 Assessment of inertia effects on transient clad-to-coolant heat transfer and coolant flow under reactivity initiated accidents

    In this report, simple hydrodynamic models are used for studying the effects of coolant inertia on fuel-to-coolant heat transfer and coolant flow under reactivity initiated accidents in light water reactors ... SCANAIR fuel rod analysis program. The results of our study suggest that inertia has a negligible impact on the growth kinetics of the continuous vapour film that forms between the fuel rod cladding tube and...

    Innehållstyp: Publikationer