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  • 2012:36 Technical Note, Documentation and Traceability of Data in SKB’s Safety Assessment SR-Site: Initial Review Phase

    On 16th March 2011SKB applied for a licence to construct and operate a spent nuclear fuel encapsulation facility in Oskarshamn Municipality and a final repository for the encapsulated fuel at Forsmark in Östhammar Municipality. SKB’s SR-Site safety assessment for the spent fuel repository is currently being reviewed by the Swedish Radiation Safety Authority, SSM, and its external experts...

    Content type: Publications
  • 2011:12 Analysis of Barrier Performance: Modelling of Copper corrosion scenarios with and without buffer erosion

    The purpose of this project was to develop a numerical modelling capacity to address the corrosion of the copper canister under gradually changing transport conditions caused by buffer erosion and removal of buffer mass. Due to the complexity of this task, such a model cannot be realistic in all respects, but the present effort should address the feasibility of solving numerical and...

    Content type: Publications
  • 2012:44 Technical Note, Review of Matrix Diffusion and related properties of intact rock in SKB’s Licence Application for a Spent Nuclear Fuel Repository in Forsmark, Sweden

    This report summarizes a review of SKB’s theoretical development of matrix diffusion, its associated processes and parameters, and the data supporting calculations of matrix diffusion. In addition to diffusion, this review covers matrix porosity, the formation factor, matrix diffusivity, penetration depth, and measurement of some of these parameters with electrical methods. Sorption and the...

    Content type: Publications
  • 2012:47 C-14 Long-Term Dose Assessment: Data Review, Scenario Development, and Model Comparison

    BIOPROTA (www.bioprota.org) is an international collaboration forum which seeks to provide a transparent and traceable basis for the choices of parameter values, as well as for the wider interpretation of information used in assessments. Particular emphasis is placed on data required for the assessment of long-lived radionuclide migration and accumulation in the biosphere, and the associated...

    Content type: Publications
  • 2012:62 Technical Note, Review of the MARFA Code

    As part of SSM’s Initial Review Phase of SKB’s SR-Site safety assessment of the final disposal of spent nuclear fuel at the Forsmark site, Quintessa has been requested by SSM to review SKB’s MARFA code and consider whether the technical arguments and assumptions used for developing the code are sound, appropriate and adequate to support its use in SR-Site. This Technical Note summarises the...

    Content type: Publications
  • 2012:15 Technical Note, A review of the mechanical integrity of the canister

    An introductory review of SR-Site has been conducted with respect to the mechanical integrity of the canister. The review is focused on the copper canister and the nodular cast iron insert. Review results show that a number of loads and loading scenarios for the copper canister has not been analysed by SKB. The importance of sufficient creep ductility of the copper material and sufficient...

    Content type: Publications
  • 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...

    Content type: Publications
  • 2009:30 A Review of Evidence for Corrosion of Copper by water

    The planned spent nuclear fuel repository in Sweden relies on a copper cast iron canister as the primary engineered barrier. The corrosion behaviour of copper in the expected environment needs to be thoroughly understood as a basis for the post-closure safety analysis. It has been shown that corrosion may indeed be the primary canister degradation process during the utilised assessment period...

    Content type: Publications
  • 2010:40 Rock-block characterization on regional to local scales for two SKB sites in Forsmark – Uppland and Laxemar – eastern Småland, south-eastern Sweden

    To get an overall impression of the general structural setting of a landscape, a remote study of bedrock structures should include studies of the geomorphology at various scales. Thematic maps improve the general understanding of an area. Digital elevation data in 500m, 50m and 10m grids were used for rock-block interpretations at regional, semi-regional and local scales of areas around the...

    Content type: Publications
  • 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...

    Content type: Publications