Filtered generated 377 hits.
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2010:12 An Evaluation of Models of Bentonite Pore Water Evolution
The pore-water composition of a KBS-3 bentonite buffer may gradually change as a result of reaction between groundwater and buffer minerals. The rather minor occurrences of the most rapidly reacting minerals in the buffer will have the most immediate and observable influences, but contributions from slow reactions of the main bulk clay phases cannot be ruled out. The performance implication...
Content type: Publications -
2010:09 Copper Thermodynamics in the Repository Environment up to 130˚C
The mechanisms of copper corrosion for a KBS-3 repository for spent nuclear fuel need to be known with a high level of confidence. This is because the overall rate of copper canister corrosion (accounting for corroding species concentrations, geochemical conditions and the mass transport through surrounding barriers) provides an essential performance indicator in safety assessment. A...
Content type: Publications -
2010:05 Discrete-Feature Model Implementation of SDM-Site Forsmark
SSM has been following the investigations of the two candidate sites for a repository for spent nuclear fuel that the Swedish Nuclear Fuel and Waste Management Company (SKB) have been undertaking. SKB has reported the results of the investigations as site descriptive models. These models will be used to underpin the safety analysis following the license application of the repository planned...
Content type: Publications -
2009:35 Evaluation of SKB/Posiva’s report on the horizontal alternative of the KBS-3 method
The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. The method has two design alternatives: the vertical (KBS-3V) and the horizontal (KBS-3H). SKB and Posiva have conducted a joint research, development and demonstration (RD&D) programme in 2002-2007 with the overall aim of establishing whether the KBS-3H represents a...
Content type: Publications -
2012:57 Technical Note, Shear movement of near-field rock due to large earthquakes
This technical note is part of a set of reviews for Swedish Radiation Safety Authority (SSM) by external experts to assist with the Initial Review Phase. The overall goal of the Initial Review Phase is for SSM to achieve a broad coverage of the information provided in SR-Site and its supporting references and in particular to identify where complementary information or clarifications need to...
Content type: Publications -
2012:67 Technical Note, Hydrogeological modelling of the Forsmark site
A modelling study has been conducted using discrete-fracture network (DFN) models in combination with discrete-feature hydrogeological modelling methods for representation of other potentially conductive features such as the disturbed zone around repository tunnels. The principal results consist of hydraulic and transport property estimates for discrete-fracture network (DFN) models on block...
Content type: Publications -
2013:13 Review of Dismantling Costs - Nuclear Installations
In this study three reviews of cost assessments for some smaller nuclear installations are presented for which nuclear waste liabilities shall be accrued according to the Financing Act (Lag (2006:647) om finasiella åtgärder för hanteringen av restprodukter från kärnteknisk verksamhet). It is expected that these reviews will contribute to develop premium quality assessments...
Content type: Publications -
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