The solubility of (uo2)3(po4)2.4h2o(s) and the formation of u(vi) phosphate complexes : their influence in uranium speciation in natural waters

Alpha-radiolysis effects on UO2 alteration in water

In the Canadian research and development program on fuel storage, used CANDU (Canada deuterium uranium) UO2fuel bundles are being exposed in experimental vessels to both dry and moisture-saturated ...

Differences in oxidation behavior of used CANDU fuel during prolonged storage in moisture-saturated air and dry air at 150 °C

https://www.wipp.energy.gov/library/CRA/2009_CRA/references/Others/Diaz_Arocas_Grambow_1998_Solid_liquid_Phase_Equilibria.pdf

Solid-liquid Phase Equilibria of U(VI) in NaCl Solutions ☆

The leaching of the spent fuel matrix (UO{sub 2}) is function of the radiolytic products formation. The effect of each radiolytic product on the leaching process is not totally understood. In the literature, the influence of H{sub 2}O{sub 2} on the dissolution process is described from the qualitative point of view, and most of the studies were performed for pH values from 8 to 12. In this paper the authors report on the effect of the H{sub 2}O{sub 2} in the leaching process of UO{sub 2} by dissolution experiments at various H{sub 2}O{sub 2} concentrations. Also, the influence of S/V ratio (surface area exposed to the leaching media) on the UO{sub 2} leaching and secondary phases formation was tested. The formation of secondary phases on the UO{sub 2} surface was identified. Solid phases characterization was carried out by X-ray Photoelectron Spectrometry (XPS), X-ray Diffraction (XRD) and Scanning Electron Microscopy (SEM) techniques. By XPS studies the secondary phase formed corresponded to a U(VI) phase. By XRD analyses the solid was identified as studtite, UO{sub 4}{center_dot}4H{sub 2}O. A comparison of the U(VI) phases formed in spent fuel and UO{sub 2} leaching experiments in various media has been carried out.

https://www.cambridge.org/core/services/aop-cambridge-core/content/view/S1946427400345626

Effect of Secondary Phases Formation in the Leaching of UO2 Under Simulated Radiolytic Products

Samples of used UO/sub 2/ fuel exposed to air-saturated water at 25/sup 0/C for eight years have been examined using electron microscopy and X-ray diffraction techniques. The results, in conjunction with solution analysis data, show evidence for a UO/sub 3/ x 2H/sub 2/O precipitate on the fuel surface, and confirm the importance of grain-boundary leaching in controlling Cs-137 release. Studies of used-fuel dissolution under both oxidizing and reducing conditions at 150/sup 0/C show significantly lower radionuclide release to solution for reducing conditions, illustrating the potential importance of redox chemistry in determining the long-term stability of used fuel after disposal.

Dissolution of used CANDU fuel at various temperatures and redox conditions

In the context of the Canadian Nuclear Fuel Waste Management Program, experiments were performed in which whole, intentionally defected used CANDU™ fuel elements were exposed to deoxygenated saline solutions at 100°C for 484 days. Results suggest that both90Sr and99Tc are preferentially released from grain boundaries and that85Kr release is a good measure of the extent of grain-boundary dissolution. Severe grain-boundary attack in particular areas of the fuel is also evident from scanning electron microscope observations. It is hypothesized that such localized attack is related to fuel porosity. Because of its poor corrosion performance in saline solutions, the Zircaloy sheath cannot be considered as a radionuclide release barrier.

Leaching of Whole, Defected Used Candu™ Fuel Elements in Saline Solutions Under Argon Pressure

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Dissolution of used CANDU fuel at various temperatures and redox conditions

Leaching of Whole, Defected Used Candu™ Fuel Elements in Saline Solutions Under Argon Pressure