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  • 2012:59 Technical Note, Initial review phase – Dose Assessment Methodology

    This report has been prepared as part of the Initial Review Phase of SKB’s SR-Site performance assessment of the long-term safety of the KBS-3 geological disposal facility (GDF) proposed for construction at Forsmark. The review addresses the methodology employed in the dose assessment calculations of SR-Site. In this respect the review has a natural focus upon biosphere modelling aspects of...

    Content type: Publications
  • 2013:16 Technical Note, Assessment of PWR fuel depletion and of neutron multiplication factors for intact PWR fuel copper canisters – main review phase

    SKB (Svensk Kärnbränslehantering AB) in 2011 applied to the Swedish government for approval of a proposed solution for disposal of used fuel from Swedish nuclear power reactors and some relatively minor quantities of other fissile material. This Technical Note contains results of a recent review of the SKB methods used to determine the influence of reactor depletion on keff of intact...

    Content type: Publications
  • 2012:65 Technical Note, Review of the Nuclear Criticality Safety of SKB’s Licensing Application for a Spent Nuclear Fuel Repository in Sweden

    The Swedish Nuclear Fuel and Waste Management Company in 2011 applied to the Swedish government for approval of a proposed solution for disposal of used fuel from Swedish nuclear power reactors and some relatively minor quantities of other fissile material. This Technical Note contains results of a recent nuclear criticality safety review of the overall prospects of the application being able...

    Content type: Publications
  • 2012:61 Geochemical Constraints on Buffer Pore Water Evolution and Implications for Erosion

    Mineralogical data from the Forsmark Site show that smectite and calcite occur at all depths in Forsmark fractures, with no evidence for removal/dissolution by previous glacial episodes. This natural analogue information implies that these minerals may not have been eroded/dissolved during previous glacial episodes. Available thermodynamic data suggest that repository-depth Forsmark...

    Content type: Publications
  • 2012:43 Technical Note, Literature review of groundwater flow in permafrost

    The Swedish Radiation Safety Authority (SSM) assigned the task of compiling the state of the knowledge with respect to groundwater flow in permafrost conditions. In particular, the study was to consider whether (i) the main processes related to groundwater flow in permafrost were understood, (ii) appropriate field data was available, and (iii) current models appropriately represent the...

    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
  • 2012:46 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
  • 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
  • Technical Note

    Tecnical Note About Technical Note Under the Act on Nuclear Activities, the Swedish Radiation Safety Authority (SSM) reviews SKB’s applications concerning a repository for spent nuclear fuel and an encapsulation facility. As part of this review work, SSM commissions consultants to obtain information and provide expert opinions on specific issues. SSM’s Technical Note series reports on these...

    Content type: Regular Pages
  • 2012:42 Technical Note, Initial review of physical properties and processes of the buffer and backfill – Installation and initial state

    The technical note briefly summarises the proposed designs and functions of the buffer and backfill, and examines SKB’s progress in manufacturing, installing and testing its proposed solutions. In brief, the review suggests that there are some procedural and practical engineering aspects (e.g., quality assurance procedures, backfilling rates) and several physical processes to do with the...

    Content type: Publications