Abstract
In this work we have studied oxidative dissolution of pure UO2 and ADOPT (UO2 doped with Al and Cr) pellets using H2O2 and gammaradiolysis to induce the process. There is a small but significant difference in the oxidative dissolution rate of UO2 and ADOPT pellets, respectively. However, the difference in oxidative dissolution yield is insignificant. Leaching experiments were also performed on in-reactor irradiated ADOPT and UO2 pellets under oxidizing conditions. The results indicate that the U(VI) release is slightly slower from the ADOPT pellet compared to the UO2. This could be attributed to differences in exposed surface area. However, fission products with low UO2 solubility display a higher relative release from ADOPT fuel compared to standard UO2-fuel. This is attributed to a lower matrix solubility imposed by the dopants in ADOPT fuel. The release of Cs is higher from UO2 which is attributed to the larger grain size of ADOPT.
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