Filtered generated 233 hits.
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2014:32 Technical Note, Assessment of the derivation and use of distribution coefficients and concentration ratios – Main Review Phase
This report presents a review of the approaches and databases which SKB have used to derive concentration ratios (CRs) and distribution coefficients (Kds) to consider if they are robustly derived and fit for purpose. Credible alternative approaches are also considered. The focus of this review are SKB reports R-10-28 and TR-10-07 which describe the available site specific data and the...
Content type: Publications -
2014:34 Technical Note, Modelling Comparison of Simple Reference Biosphere Models with LDF Models – Main Review Phase
This Technical Note describes the development of simple reference biosphere models as a means of exploring the Landscape Dose Factor (LDF) approach adopted by SKB in the SR-Site safety assessment for the proposed final disposal of spent nuclear fuel at the Forsmark site. The models are developed and described in a systematic manner, based on international guidance reflected in the...
Content type: Publications -
2014:39 Technical Note, “Wormhole” and Multiple Loss of Buffer Safety Function Scenarios
This Technical Notes reviewed the issues that may cause canister corrosion other than the cases evaluated by SKB, which may belong to “What-if” canister corrosion scenarios. This Notes, in particular, addressed two potential canister corrosion scenarios: “wormhole” formation and loss of multiple buffer safety functions. The “wormhole” scenario was hypothesized during the SSM Workshop on...
Content type: Publications -
2014:46 Technical Note, QA in SKB’s Groundwater Flow Modelling
The general objective of the project is to provide review comments on SKB’s postclosure safety analysis, SR-Site, for the proposed repository at Forsmark. The specific objective is to get an understanding and an assessment of SKB’s quality assurance of the groundwater flow modelling in connection to SR-Site. The reliability of the results of the groundwater flow modelling depends inter alia...
Content type: Publications -
2013:27 Numerical simulations of headed anchors break in reinforced and non-reinforced concrete structures
The design codes for anchorage of equipment in concrete structures have been developed since the time the Swedish power plants were designed. Furthermore, the design basis has been updated and in some cases new mechanical loads have been added. As a consequence, it can be difficult for some anchorages to meet the requirements of today. In the design of anchorage equipment the beneficial effect...
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 -
2010:08 Development of COLLAGE 3
The issue of colloid-facilitated radionuclide transport (CFRT) was last addressed by the Swedish nuclear regulators (SKI at that time, now integrated into SSM) in 2001 – 2002. SKI had commissioned the Collage code with subsequent development as Collage 2. This code was employed to investigate the potential role for colloids to have been involved in the transport of radionuclides at the Nevada...
Content type: Publications -
2009:22 Alternative modelling of brittle structures in a sub-area of the SKB candidate area at Forsmark, eastern Sweden
A reasonable understanding of the character of the bedrock hosting a deep geological repository, i.e. the natural barrier, is an important component in the safety assessment of the deep geological repository for spent nuclear fuel. The structures in the rock, together with the regional stress field, affect the mechanical stability of the bedrock and the ground water transport within the...
Content type: Publications -
2010:17 Quality Assurance Review of SKB’s Copper Corrosion Experiments
SKB is preparing a license application for the construction of a final repository for spent nuclear fuel in Sweden. This application will be supported by the safety assessment SR-Site for the post-closure phase. The assessment of long-term safety is based on a broad range of experimental results from laboratory scale, intermediate scale and up to full scale experiments. It is essential that...
Content type: Publications -
2009:32 On Younger Stakeholders and Decommissioning of Nuclear Facilities
An appropriate balance in this regard must be based on a proper understanding of the values and value functions of younger citizens. Such information must thus be an integral part of the knowledge base to be used when plans and processes are being developed for dismantling and decommissioning of nuclear power plants and other older nuclear facilities. In the present project, empirical data...
Content type: Publications