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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...
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 -
2005:58 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 -
2005:65 Review Statement and Evaluation of the Swedish Nuclear Fuel and Waste Management Cos RD&D Programme 2004
SKI English...
Content type: Publications -
2005:20 DECOVALEX III PROJECT Modelling of FEBEX In-Situ Test
E. E. Alonso J. Alcoverro SKI English...
Content type: Publications -
2005:59 Reactive-Transport Model of Buffer Cementation
Randy Arthur, Wei Zhou SKI English...
Content type: Publications -
2005:39 Large-Scale Groundwater Flow with FreeWater Surface Based on Data from SKB's Site Investigation in the Forsmark Area
Anders Wörman, Björn Sjögren, Lars Marklund 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)
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...
Content type: Publications -
2005:16 Assessment of Core Failure Limits for Light Water Reactor Fuel under Reactivity Initiated Accidents
Lars Olof Jernkvist, Ali R. Massih SKI English...
Content type: Publications