• Radiolysis and corrosion of 238Pu-doped UO2 pellets in chloride brine

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    • Keywords


      𝛼-Radiolysis; UO2; leaching; chloride brine; radiolysis products.

    • Abstract


      Deaerated 5 M NaCl solution is irradiated in the presence of UO2 pellets with a-radiation from 238Pu. Experiments are conducted with 238Pu doped pellets and others with 238Pu dissolved in the brine. The radiolysis products and yields of mobilized U and Pu from the oxidative dissolution of UO2 are determined. Results found for radiolysis products and for the oxidation/dissolution of pellets immersed in Pu containing brine are similar to results for Pu doped pellets, where the radiation chemical processes occur only in the liquid layer of some 10 𝜇m thickness adjacent to the pellet. The yield of radiolysis products is comparable to earlier results, that of mobilized U from the pellets is < 1% of the total amount of oxidized species. Thus, the radiation chemical yield (𝐺-value) for mobilized hexavalent U is < 0.01 ions/100 eV. In spite of the low radiation yield for the corrosion, the rate of UO2 dissolution is higher than expected for the concentrations of long-lived oxidizing radiolysis compounds found in the solutions.

    • Author Affiliations


      M Kelm1 E Bohnert1

      1. Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung, Postfach 3640, 76021 Karlsruhe, Germany
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