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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...

    Innehållstyp: Publikationer
  • 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...

    Innehållstyp: Publikationer
  • 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...

    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
  • 2012:61 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...

    Innehållstyp: Publikationer
  • 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...

    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
  • 2011:34 Evolution of hydrogen by copper in ultrapure water without dissolved oxygen

    One result from this research was that the experimental difficulties of repeating Hultqvist and co-workers work are considerable and were initially underestimated. The main challenge was to obtain satisfactory tightness of all connectors involved in the experimental set-up. The problems with leakage resulted in that the research program originally planned for in this project had to be reduced...

    Innehållstyp: Publikationer
  • 2011:10e Review and evaluation of the Swedish Nuclear Fuel and Waste Management Company’s RD&D Programme 2010. Statement to the Government and summary of the review report

    In accordance with Section 25 of the Ordinance (1984:14) on Nuclear Activities (Nuclear Activities Ordinance), the Swedish Radiation Safety Authority (SSM) shall review and assess the research, development and demonstration programme (RD&D programme) that the reactor licensees are obligated to establish in accordance with the Act (1984:3) on Nuclear Activities (Nuclear Activities Act).

    Innehållstyp: Publikationer
  • 2012:06 Decommissioning Cost Assessment

    The future costs for dismantling, decommissioning and handling of associated radioactive waste of nuclear installations represents substantial liabilities. It is the generations that benefits from the use of nuclear installations that shall carry the financial burden. Nuclear waste programmes have occasionally encountered set-backs related to the trust from society. This has resulted in...

    Innehållstyp: Publikationer