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2005:60 Research and Service Experience with Environmentally-Assisted Cracking in Carbon and Low-Alloy Steels in High-Temperature Water
In this report, the most relevant aspects of research and service experience with environmentally assisted cracking of carbon and low-alloy steels in high-temperature water are reviewed, with special emphasis ... respect to crack initiation and crack growth. The adequacy and conservatism of the current BWRVIP-60 stress corrosion cracking disposition curves, ASME III fatigue design curves, and ASME XI reference fatigue...
Content type: Publications -
2005:09 Comment on the Long-Term Chemical and Mineralogical Stability of the Buffer
Randy Arthur, Mick Apted, Mike Stenhouse SKI English...
Content type: Publications -
2005:04 Assuring Competency in Nuclear Power Plants: Regulatory Policy and Practice
Nancy E. Durbin, Barbara Melber SKI English...
Content type: Publications -
2005:38 A Model Study of Costs Estimates of Decontamination and Decommissioning with an Emphasis to Derive Cost Functions for Alpha-Contaminated Material Using OMEGA Code
Kristina Kristofova, Vladimir Daniska, Frantisek Ondra, Ivan Rehak, Marek Vasko 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 -
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...
Content type: Publications -
2005:61 Review and Assessment of SCC Experiments with RPV Steels in Oskarshamn 2 and 3 (ABB Report SBR 99-020)
results fit well to the experimental background knowledge and have basically confirmed the excellent service record of properly fabricated carbon and low alloy steel primary pressure-boundary components, where ... cracking in the thickwalled reactor pressure vessel is expected as long as prolonged and severe chloride excursions are avoided and the number of plant transients is limited. Although there is no direct evidence...
Content type: Publications -
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...
Content type: Publications -
2005:05 Review of SKB's Code Documentation and Testing
T.W. Hicks SKI English...
Content type: Publications