Sök

Din avgränsning ger 751 träffar.

Sortera på:

Relevans Datum
  • 2012:24 Technical Note, Initial Review of SR-Site Main Report

    The Swedish Radiation Safety Authority (SSM) is reviewing a license application, which has been submitted by Svensk Kärnbränslehantering AB (SKB), for a repository for the final disposal of spent nuclear fuel. SKB’s Application includes an assessment of the long-term safety of the proposed repository. The assessment is known as SR-Site. This technical note records the findings from a...

    Innehållstyp: Publikationer
  • 2012:13 Technical Note, A review of the creep ductility of copper for nuclear waste canister application

    SKB has presented insufficient evidence to justify their position that the OFP copper has an adequate creep ductility during long term storage. Their large body of experiments only serves to prove that the creep ductility is sufficient for much shorter time spans than the intended storage times. There is a clear need for a credible theory of creep brittleness of OFP copper which will permit...

    Innehållstyp: Publikationer
  • 2012:10 Technical Note, Review of the Geomicrobiological Aspects of SKB’s Licence Application for a Spent Nuclear Fuel Repository in Forsmark, Sweden

    The Swedish Radiation Safety Authority (SSM) reviews the Swedish Nuclear Fuel Company’s (SKB) applications under the Act on Nuclear Activities (SFS 1984:3) for the construction and operation of a repository for spent nuclear fuel and for an encapsulation facility. As part of the review, SSM commissions consultants to carry out work in order to obtain information on specific issues. The...

    Innehållstyp: Publikationer
  • 2012:29 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill – Geochemical processes

    De dokument i SR-Site som är relevanta till detta granskningsområde bedöms vara generellt i tillräckligt hög kvalitet för att utgöra underlagsmaterial för vidare granskning i huvudgranskningsfasen av SSM:s GLS- (granskning av långsiktig säkerhet) projekt. Behov av kompletterande information eller förtydliganden har dock identifierats inom...

    Innehållstyp: Publikationer
  • 2012:26 Technical Note, Initial review of chemical and erosional processes within the buffer and backfill - Chemical erosion processes

    The SR-Site documentation relevant to this review topic was found to be of sufficiently high quality overall to justify further consideration in the Main Review Phase of SSM’s PCS (Post-closure safety) project. Several specific topics for which complementary information and clarifications should be requested from SKB were also identified (Appendix 2). Specific review topics for consideration...

    Innehållstyp: Publikationer
  • 1997:05 SKI SITE-94

    The Swedish Industry program for deep geological disposal of spent nuclear fuel and high-level radioactive waste is now in the early stages of the site selection process, with feasibility studies underway in 5 to 10 municipalities. According to the Swedish Nuclear Fuel and Waste Management Co., SKB (SKB RD&D Programme, 1995), the ongoing siting process involves selection of two sites for...

    Innehållstyp: Publikationer
  • 2016:25 Licensing of safety critical software for nuclear reactors

    – Common position of international nuclear regulators and authorised technical support organisations – Revision 2015...

    Innehållstyp: Publikationer
  • 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 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...

    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 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...

    Innehållstyp: Publikationer
  • 1990:18 Some Estimates of the Total NuclideInventory in the Year 2100 from Swedish Nuclear Power Production

    The total nuclide inventory in spent fuel from the swedish nuclear power programme has been estimated for three cases. All reactors were arrumed to operate until the year 2010 and then shut down simultaneously. All fuel used was assumed to be based on enriched natural uranium. The reactors were assumed to shut down after 25 years of commercial operation, but not later than in the year 2010.

    Innehållstyp: Publikationer