Surface and electrochemical controls on UO2 dissolution under anoxic conditions

Abstract The escape of radionuclides from underground spent nuclear fuel disposal facilities will likely result from anoxic dissolution of spent nuclear fuel by intruding groundwater. Anoxic dissolution of various forms of uranium dioxide (UO 2 ), namely bulk pellet, powder and thin film, has been investigated. Long-duration static batch dissolution experiments were designed to investigate the release of uranium ions in deionized water and any surface chemistry that may occur on the UO 2 surface. The dissolved uranium concentration for anoxic dissolution of nearly stoichiometric UO 2 was found to be of the order of 10 −9  mol/l for the three different sample types. Further, clusters (∼500 nm) of homogenous uranium-containing precipitates of ∼20–100 nm grains were observed in thin film dissolution experiments. Such a low solubility of UO 2 across sample types and the observation of secondary phases in deionized water suggest that anoxic UO 2 dissolution does not only occur through a U(IV) (solid) to U(VI) (aqueous) process. Thus, we propose that dissolution of uranium under anoxic repository conditions may also proceed via U(IV) (solid) to U(IV) (aqueous) , with subsequent U(IV) (precipitates) in a less defective form. Quantitative analysis of surface-sensitive EBSD diffractograms was conducted to elucidate lattice-mismatch induced cracks observed in UO 2 thin film studies. Variable temperature anoxic dissolution was conducted, and no increased uranium concentration was observed in elevated temperatures.