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  • 2014:22 Technical Note, Workshop on seismic hazard at Forsmark

    This report describes the outcome of the workshop organized by SSM on seismic hazard at Forsmark that was held in Stockholm on the 4 and 5 of June, 2013. The report summarizes the issues discussed and extracts the essential viewpoints that have been expressed. It should not be considered as a comprehensive record of all the discussions at the workshop and individual statements made by...

    Innehållstyp: Publikationer
  • 2014:50 Technical Note, A Study of Availability of Fuel Data for Sweden’s Spent Nuclear Fuel

    The study covers all types spent fuel planned to be placed in the final repository. It was carried out by selecting a sample of spent fuel and investigating the information available at the Nuclear Power Plants (NPP’s) in Sweden, the Central interim storage facility (Clab) and Studsvik. The results indicate that the required data is available and can be obtained for fuel unloaded after 1980.

    Innehållstyp: Publikationer
  • 2015:25 Design Guide for Nuclear Civil Structures (DNB)

    The Swedish Radiation Safety Authority (SSM) and the Swedish licensees have previously in a jointly funded research project developed a design guide for civil structures at Swedish nuclear facilities to be based on Eurocodes, DNB. The report was published in January 2014 as SSM Report 2014:06. To further improve DNB and to ensure that the fundamentals of the recommendations will be applied...

    Innehållstyp: Publikationer
  • 2012:53 Technical Note, Review of Engineering Geology and Rock Engineering aspects of the operation and closure of a KBS-3 repository at the Forsmark site – Initial Review Phase

    SRK Consulting (UK) Limited (SRK) has reviewed the Engineering Geology and Rock Engineering aspects of the operation and closure of a KBS-3 repository at the Forsmark site in Sweden. The review assignment is part of a Swedish Radiation Safety Authority (SSM) Initial Review Phase. The review was carried out by David Saiang (PhD) on behalf of SRK. Therefore some of the views expressed in the...

    Innehållstyp: Publikationer
  • 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.

    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
  • 2011:22 Infiltration of dilute groundwaters and resulting groundwater compositions at repository depth

    The planned Swedish concept for final disposal of spent nuclear fuel includes copper canisters placed in deposition holes at about 500 m depth in granitic bedrock. The copper canisters will be surrounded by bentonite buffer with the objective of inhibiting groundwater flow adjacent to the canister. It has been discovered that dilute glacial melt-water may induce erosion of the buffer material.

    Innehållstyp: Publikationer
  • 2010:25 Modelling Coupled Processes in the Evolution of Repository Engineered Barrier Systems using QPAC-EBS

    Currently in Sweden, the SR-Site safety assessment for a spent nuclear fuel repository is being developed by the Swedish Nuclear Fuel and Waste Management Company (SKB). The planned SSM review of this work requires access to a sufficient modelling capability to assess the combined performance of the engineered barriers (spent fuel canister, buffer and backfill) and the natural geosphere...

    Innehållstyp: Publikationer
  • 2010:43 Displacement along extensive deformation zones at the two SKB sites: Forsmark and Laxemar

    The Fennoscandian shield is distinguished by that the exposed bedrock is mainly composed of Precambrian metamorphic and igneous rocks older than a billion or one and a half billion years with few easily distinguished testimonies for the younger history. Large parts of the present ground surface closely coincides with a late Precambrian denudation surface; the sub-Cambrian peneplain.

    Innehållstyp: Publikationer
  • 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