Filtered generated 754 hits.
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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 -
2007:11 Review of Quality Assurance in SKBs Repository Research 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. As a preparation for SR-Site SKB has recently produced the SRCan safety assessment, which is currently in review. The assessment of long-term safety is based on a broad range of...
Content type: Publications -
2007:12 Development of a constitutive model for the plastic deformation and creep of copper and its use in the estimate of the creep life of the copper canister
The copper-iron canister for disposal of nuclear waste in the Swedish Programme has a design life exceeding 100,000 years. Whilst the operating temperature and operating stress are modest, the very long design life does require that the likely creep performance of the canister should be investigated. Many studies have been carried out by SKB but these have all involved very short duration...
Content type: Publications -
2006:17 Three Dimensional Modelling of a KBS-3 Canister for Spent Nuclear Fuel some migration studies
António Pereira SKI English...
Content type: Publications -
2006:36 Mechanical Integrity of Canisters Using a Fracture Mechanics Approach
This report presents the methods and results of a research project for Swedish Nuclear Power Inspectorate (SKI) about numerical modeling of mechanical integrity of cast-iron canisters for the final disposal of spent nuclear fuel in Sweden, using combined boundary element (BEM) and finite element (FEM) methods The objectives of the project are: 1) to investigate the possibility of initiation...
Content type: Publications -
2005:21 DECOVALEX III PROJECT Thermal-Hydrological Modeling of the Yucca Mountain Project Drift Scale Test
Robin N. Datta with contributions from Sebastia Olivella, Claudia Gonzalez, Antonio Gens, Miguel Luna, Ronald T. Green, Scott L. Painter SKI English...
Content type: Publications -
2005:24 DECOVALEX III/BENCHPAR PROJECTS Implications of Thermal-Hydro-Mechanical Coupling on the Near-Field Safety of a Nuclear Waste Repository
L. Jing, T.S. Nguyen SKI English...
Content type: Publications -
2005:22 DECOVALEX III PROJECT Thermal-Mechanical Modeling of the Yucca Mountain Project Drift Scale Test
Robin N. Datta with contributions from: Sebastia Olivella, Claudia Gonzalez, Antonio Gens, Alain Millard, Jonny Rutqvist, Sui-Min Hsiung, Asadul H. Chowdhury SKI English...
Content type: Publications -
2005:65 Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Cos RD&D Programme 2004
SKI English...
Content type: Publications -
02:02 R2/R0-WTR Decommissioning Cost Comparison and Benchmarking Analysis
Dr. Geoff Varley, Chris Rusch SKI English...
Content type: Publications