Symposium Scientific Basis for Nuclear Waste Management XXVII
Research Article
Preface
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Posiva's Site Investigations Programme
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Site Investigations of Potential Repository Sites in Sweden
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Development of Siting Factors and Commencement of Open Solicitation for Preliminary Investigation Areas of HLW disposal in Japan
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Study on a Decision Making Methodology with Uncertainties in the Selection Process of Preliminary Investigation Areas
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Key Scientific Issues Related to the Evolution of Spent Nuclear Fuel in Long Term Dry Storage and Geological Disposal
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Quantitative Assessment of the Instant Release Fraction (IRF) for Fission Gases and Volatile Elements as a Function of Burnup and Time under Geological Disposal Conditions
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Behavior of Uranium Dioxide: Chemistry and Catalysis in the UO2-water System
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Measurement of Dissolution Rates of UO2 Matrix with the Isotope Dilution Method
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Corrosion Behavior of Pre-oxidized High Burnup Spent Fuel in Salt Brine
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Static Dissolution of α-doped UO2 in Boom Clay Conditions: Preliminary Results
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A New Modelling of the Kinetics of Uranium Dioxide Oxidation in Air
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Surface Site Densities of Uranium Oxides: UO2, U3O8
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Analogues for the Corrosion-induced Expansion of Iron in HLW containers
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Dissolution of UO2 by One- and Two-Electron Oxidants
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The Oxidative Dissolution Mechanism of Uranium Dioxide. The Effect of pH and Oxygen Partial Pressure
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Spent Fuel Leaching under Anoxic Conditions and the Effect of Canister Materials
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Leaching Behavior of Unirradiated High Temperature Reactor (HTR) UO2-ThO2 Mixed Oxides Fuel Particles
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Microgravimetric Corrosion Studies on UO2
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The Uptake of Strontium by Calcium Silicate Hydrates under High pH Conditions: An Experimental Approach to Distinguish Adsorption from Co-precipitation Processes
- Published online by Cambridge University Press: 01 February 2011, A101
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