Reports

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  • 2012:55 Technical Note, Review of SKB’s Radionuclide Transport Methodology

    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 consider whether SKB’s methodology to abstract FEPs (features, events, processes), as well as site information and other data, into assessment models for radionuclide transport is appropriate and sufficient for its...

    Content type: Publications
  • 2012:54 Technical Note, Initial Review Phase for SKB´s safety assessment SR-Site: Geological structures and deformation zones, from site investigation to safety assessment

    The site selected by the Swedish Nuclear Fuel and Management Co (SKB) for location of a deep geological repository, i.e. a storage for spent nuclear fuel at about 500 m depth in Precambrian metamorphosed rocks. The location of the site is Forsmark at the northern coast of Uppland and 122 km north of Stockholm. In geological terms Forsmark is located in the central part of the Fennoscandian...

    Content type: Publications
  • 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...

    Content type: Publications
  • 2012:52 Technical Note, Shear movement of near-field rock due to large earthquakes

    The review assignment concentrates on the possible impact of large earthquakes on the shear deformation of large fractures in the repository volume. For this purpose a general review of some of SKB‘s top-level reports was carried out. The reports draw a generally consistent and to a considerable extend comprehensive picture of the potential impact on the repository integrity in case of the...

    Content type: Publications
  • 2012:51 Technical Note, Rock Mechanics related to long-term repository and site evolution

    In general, SKB demonstrates that they have accumulated a significant set of hydraulic, mechanical and thermal data that is essential for constructing a deep geological repository. The method of data acquisition is robust using the internationally- recognized and suggested methods. The methodology of safety assessment is firmly established by applying the state-of-the-art technology and...

    Content type: Publications
  • 2012:50 Fatigue Margins for Austenitic Stainless Steels in ASME Boiler and Pressure Vessel Code – A Literature Study

    Knowledge about the margins against fatigue failure in nuclear piping systems is essential. Therefore, the margins in the ASME Boiler and Pressure Vessel Code (section III) fatigue design procedure for austenitic steels, type 304/316, as applied to real components have been investigated in this literature study. It is concluded that the current knowledge about the margins in ASME for...

    Content type: Publications
  • 2012:49 Hydrogeological characteristics of sites for low- and intermediate-level waste disposal

    The Forsmark area with its selected two sites and the Laxemar-Simpevarp area with its two sites are broadly similar in terms of lithology, rock ages, and tectonic histories. The two areas differ in terms of degree of deformation, and tectonic fabric. Some lithologic and tectonic differences are noticeable between the two sites in the Forsmark area and between the two sites in the...

    Content type: Publications
  • 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.

    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...

    Content type: Publications
  • 2012:46 Technical Note, Review of Landscape Models used in SR-Site

    As part of SSM’s Initial Review phase of SKB’s SR-Site safety assessment for the proposed final disposal of spent nuclear fuel at the Forsmark site, Quintessa was given the assignment to consider whether the landscape models and supporting data utilised by SKB are appropriate and fit for purpose.  This Technical Note summarises the findings of Quintessa’s review. SKB’s approach to the...

    Content type: Publications