Dissolution of irradiated fuel: a radiolytic mass balance study (original) (raw)

We have studied the production of H2,O 2 and H202 by radiolysis of the leach solution in a closed system containing fragments of irradiated PWR fuel and distilled water purged with argon. The experimental data is not reflected in the release of U(VI) to the solution, clearly indicating that most of the oxidant production has been taken up by the UO2 spent fuel surface. This proves that the UO 2 surface constitutes a major redox buffer capacity to prevent radiolytic oxidation under repository conditions. 0022-3115/95/$09.50