Din avgränsning ger 300 träffar.
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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...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2005:65 Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Cos RD&D Programme 2004
SKI English...
Innehållstyp: Publikationer -
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...
Innehållstyp: Publikationer -
2005:09 Comment on the Long-Term Chemical and Mineralogical Stability of the Buffer
Randy Arthur, Mick Apted, Mike Stenhouse SKI English...
Innehållstyp: Publikationer -
2005:63 Safety-Related Contractor Activities at Nuclear Power Plants - New Challenges for Regulatory Oversight
Alan Chockie SKI English...
Innehållstyp: Publikationer -
2005:34 An Applied Study on the Decontamination and Decommissioning of the Map Tube Facility 317 Area Argonne National Laboratory, Chicago
Geoff Varley, Chris Rusch SKI English...
Innehållstyp: Publikationer -
2005:58 The Swedish Concept for Disposal of Spent Nuclear Fuel: Differences Between Vertical and Horizontal Waste Canister Emplacement
D. G. Bennett, T. W. Hicks SKI English...
Innehållstyp: Publikationer -
2005:05 Review of SKB's Code Documentation and Testing
T.W. Hicks SKI English...
Innehållstyp: Publikationer -
2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)
Although the extent of cracking was rather surprising for a bolt-loaded specimen, the average stress corrosion crack growth rate of 0.5 mm/year over the five-year testing period does not represent an immediate concern. The overwhelming part of crack growth can have occurred during a 20 day chloride transient during the third year of exposure because of a condenser leakage after an outage. The...
Innehållstyp: Publikationer