Title: Dissolution of irradiated fuel: a radiolytic mass balance study
Abstract: We have studied the production of H2,02 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 U02 spent fuel surface. This proves that the U02 surface constitutes a major redox buffer capacity to prevent radiolytic oxidation under repository conditions.
Publication Year: 1995
Publication Date: 1995-12-01
Language: en
Type: article
Indexed In: ['crossref']
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Cited By Count: 61
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