Filtered generated 761 hits.
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2007:21 On tentative decommissioning cost analysis with specific authentic cost calculations with the application of the Omega code on a case linked to the Intermediate storage facility for spent fuel in Sweden
Marek Vasko, Vladimir Daniska, Frantisek Ondra, Peter Bezak, Kristina Kristofova, Peter Tatransky, Matej Zachar, Staffan Lindskog SKI English...
Content type: Publications -
2005:30 BENCHPAR PROJECT How to Incorporate Thermal-Hydro-Mechanical Coupled Processes into Performance Assessments and Design Studies for Radioactive Waste Disposal in Geological Formations
O. Stephansson, J.A. Hudson, J. Andersson SKI English...
Content type: Publications -
2006:31 An Applied Study on the Decontamination and Decommissioning of Hot Cell Facilities in the United States and Comparison with the Studsvik Facility for Solid and Liquid Waste
Dr. Geoff Varley 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 -
2006:07 Coupled Transport/Reaction Modelling of Copper Canister Corrosion Aided by Microbial Processes
Jinsong Liu SKI English...
Content type: Publications -
2006:11 Engineered Barrier System Assessment of the Corrosion Properties of Copper Canisters
SKI English...
Content type: Publications -
93:06 CRACKER A Program Coupling Chemistry and Transport, Version 92-11
A. Emrén SKI English...
Content type: Publications -
91:12 Radionuclide Migration within Fractured Rock: The Impact of Colloids upon Geosphere Calculations
P. Grindrod SKI English...
Content type: Publications -
1990:18 Some Estimates of the Total NuclideInventory in the Year 2100 from Swedish Nuclear Power Production
The total nuclide inventory in spent fuel from the swedish nuclear power programme has been estimated for three cases. All reactors were arrumed to operate until the year 2010 and then shut down simultaneously. All fuel used was assumed to be based on enriched natural uranium. The reactors were assumed to shut down after 25 years of commercial operation, but not later than in the year 2010.
Content type: Publications -
2016:27 Validation of fatigue fracture mechanics approaches
Background In a previous study (SSM research report 2015:38) fatigue experiments were performed on welded austenitic stainless steel piping components. The fatigue experiments offer an opportunity to evaluate fatigue flaw tolerance assessments used in industry, which are based on the fracture mechanical approach implemented in ProSACC. Objective The present study aims to validate the used...
Content type: Publications