Filtered generated 755 hits.
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2008:11 Discrete-Feature Modelling of Groundwater Flow and Solute Transport for SR-Can Review
Review External review contribution in support of SKI's and SSI's review of SR-Can. The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for...
Content type: Publications -
2008:08 Review of SKB:s Work on Coupled THM Processes Within SR-Can External review contribution in support of SKI:s and SSI:s
The work presented in this report is part of the Swedish Nuclear Power Inspectorate’s (SKI) and the Swedish Radiation Protection Authority’s (SSI) SR-Can review project. The Swedish Nuclear Fuel and Waste Management Co (SKB) plans to submit a license application for the construction of a repository for spent nuclear fuel in Sweden 2010. In support of this application SKB will present a safety...
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 -
2008:48E Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Co´s (SKB) RD&D Programme 2007
The review of the RD&D Programmes (Research, Development, Demonstration) prepared by the Swedish Nuclear Fuel and Waste Management Co (SKB) is a recurrent task that the Swedish Nuclear Power Inspectorate (SKI) must carry out as a regulatory authority with the support of reviewing bodies of which the most important is the Swedish Radiation Protection Authority (SSI). The review statement for...
Content type: Publications -
2008:47 Selected Models for Key Processes in a Nuclear Waste Repository
The conceptual design of the disposal of spent nuclear fuel in Sweden is based on a multibarrier system. In the KBS-3 concept, the bentonite buffer is a barrier with the primary purpose of surrounding and protecting the canister. The bentonite buffer is expected to prevent or minimise the water exchange with the surrounding rock and protect the canister against mechanical damages caused by...
Content type: Publications -
2009:08 Shear-induced Fracture Slip and Permeability Change - Implications for Long-term Performance of a Deep Geological Repository
Opening of fractures induced by shear dilation or normal deformation can be a significant source of fracture permeability change in jointed rock, which is important for the performance assessment of geological repositories for spent nuclear fuel. As the repository generates heat and later cools the fluid-carrying ability of the rocks becomes a dynamic variable during the lifespan of the...
Content type: Publications -
2015:49 Technical Note, Independent Modelling of Engineered Barrier Evolution and Coupled THMC: Canister Corrosion Calculations in SR-Site
Projektets syfte Projektet syftar till att granska olika beräkningsfall för korrosion av kopparkapseln som rapporterats i SKB TR-10-66 och som sammanfattas i SKB TR-11-01. Arbetet omfattar en analys av beräkningsfall relaterade till korrosionshastigheten för intakt buffert, delvis eroderad buffert och för advektiva förhållanden i bufferten. Målsättningen...
Content type: Publications -
2016:21 The effect of a glaciation on East Central Sweden: case studies on present glaciers and analyses of landform data
The Swedish Radiation Safety Authority reviews and assesses applications for geological repositories for nuclear waste. When assessing the long term safety of the repositories it is important to consider possible future developments of climate and climate-related processes. Especially the next glaciation is important for the review and assessment for the long term safety of the spent nuclear...
Content type: Publications -
2016:01 Literature Study on Sparse Channel Interpretation and Modeling
Channelling has been observed in laboratory and field experiments at various scales. However, it is still an open research issue whether a sparse channel network is likely to be a better model than the fracture network model for representing the flow system in fractured rocks. The present report presents a literature study to bring together information useful for addressing this issue.
Content type: Publications -
2016:30 Measurement of Parameter Values for Predicting Corrosion Phenomena on Copper in Swedish HLNW Repositories
Passivity breakdown and pitting on pure copper, the assumed material for the canisters for the isolation of high-level nuclear waste in Sweden, has been studied in simulated, sulphide- and chloride containing granitic rock groundwater and the data are interpreted in terms of the Point Defect Model (PDM). The results indicated that a sulphide barrier layer forms on the copper surface, and that...
Content type: Publications