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  • 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 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...

    Innehållstyp: Publikationer
  • 2010:34 The understanding of the formation of valleys and its implication on site characterization: Moredalen and Pukedalen, south-eastern Sweden

    This report concerns a study which was initially conducted for the Swedish Nuclear Power Inspectorate (SKI), which is now merged into the Swedish Radiation Safety Authority (SSM). The conclusions and viewpoints presented in the report are those of the authors and do not necessarily coincide with those of the SSM. In south-eastern Sweden, there are a number of over-deepened narrow valleys,...

    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
  • 2018:15 Review of Geochemical Data Utilisation in SR-Site Safety Assessment

    The Swedish Radiation Safety Authority (SSM) reviews and follows associated research related to the Swedish Nuclear Fuel Company’s (SKB) work with establishing a repository for spent nuclear fuel and an encapsulation facility.

    Innehållstyp: Publikationer
  • 2018:08 Calculated radiological consequences of applying European clearance levels to scrap metal from the decommissioning of Swedish nuclear facilities

    Background Many practices involving radioactive substances generate materials with potential or known radioactive contamination. Clearance of materials means a decision that such materials can be released from regulatory control and used or disposed of without restrictions from a radiation protection point of view. According to regulations issued by the SSM, such decisions must be based on...

    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 have been characterised by an increased use of PSA models and results, and by major extensions of existing PSA models. The aim of this document is to describe PSA in Sweden with respect to...

    Innehållstyp: Publikationer
  • 1995:72 Kopparkorrosion i rent syrefritt vatten

    Kopparkorrosion i rent vatten har studerats. Undersökningen är bl a föranledd av artiklar publicerade i Corrosion Science. I dessa artiklar presenterades resultat som visar att koppar kan korrodera i rent vatten i frånvaro av löst syrgas. Koppar oxideras i stället direkt av vattnet under bildning av vätgas. Kvartsprovrör innehållande rent vatten och...

    Innehållstyp: Publikationer
  • 1997:40 Aging of Electrical Components in Nuclear Power Plants

    The purpose of the study reported in SKl Technical Report 93:39 was to evaluate qualification methods for application to components intended to be installed in the containment of nuclear power plants. The study included application of Arrhenius' criterion for thermal aging as well as methodologies for updating (curve-matching, ongoing qualification). This report reviews the results of...

    Innehållstyp: Publikationer
  • 1997:12 Study of International Published Experiences in Joining Copper and Copper-alloys

    This study has revealed a number of joining processes to be used when manufacturing copper-canisters for the final storage of high level nuclear waste. However, the decision on which material and which joining process to be used has to be based on the design criterions. The welding procedure has to be qualified i.e, it shall be demonstrated whether the procedure is capable of fulfilling...

    Innehållstyp: Publikationer
  • 2019:23 Participation in the European Committee for Standardization's workshop regarding civil structures

    SSM perspective Background During the period 2014-2018, a CEN1 workshop (Phase 2 Prospective Group 3 civil works) have been carried out. The aim of the workshop is to provide a base founded on the French standard in order to be able to establish a possible future European standard for the design of civil structures at nuclear power plants. The workshop has identied which additional...

    Innehållstyp: Publikationer