Abstract
ABSTRACTThe uranium and plutonium chemistry relevant for spent fuel leach studies is discussed. Model calculations are evaluated by comparison with the results of spent UO2fuel leaching obtained in the Swedish SKB program. The thermodynamic data were found to agree sufficiently with the measured solution concentrations that it can be assumed that in oxic natural waters, leachate uranium from spent fuel would be uranyl carbonate complexes in the solution (or hydroxo complexes in the absence of carbonate) while schoepite would be the solubility limiting solid. For plutonium, PuO2+would be the solution species and Pu(OH)4the solubility limiting solid.
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