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Radiolytic Corrosion of 238Pu-doped UO2 Pellets in 5 M NaCl Solution

Published online by Cambridge University Press:  17 March 2011

M. Kelm
Affiliation:
Institut für Nukleare Entsorgung, Forschungszentrum Karlsruhe Hermann-von-Helmholtz-Platz 1 76344 Eggenstein-Leopoldshafen, Germany e-mail:, [email protected]
E. Bohnert
Affiliation:
Institut für Nukleare Entsorgung, Forschungszentrum Karlsruhe Hermann-von-Helmholtz-Platz 1 76344 Eggenstein-Leopoldshafen, Germany
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Abstract

Deaerated 5 M NaCl solution is alpha-irradiated up to 700 days in the presence of UO2 pellets. Experiments are conducted with 238Pu-doped pellets in pure brine and with undoped UO2 pellets in a 238Pu containing brine. The long-lived radiolysis products H2, O2 and ClO3- are formed in all cases proportional to the dose applied on the solution and with yields corresponding to 200, 80 and 7 nMol/(L*Gy).

The U concentrations increase with time but do not exceed about 10−4 Mol/L thus indicating Uranium to be solubility limited. Moreover, the rinse solutions of the vessels at the end of the experiments contain up to one order of magnitude more U than found in the solutions. The total amounts of mobilized U deviate by less than a factor 10 from each other regardless of the large ratio of surface dose rates (ratio up to 2300) or mean dose rates (ratio up to 100), applied while the reference experiment (UO2 pellet in pure brine) yields only some 10−7 Mol/L U which is over 3 orders of magnitude lower than observed in experiments with radiation present.

The simulation of the radiation chemical processes using a kinetic reaction model can reasonably reproduce the findings of the experiments with respect to the formation of H2 and O2 and give the order of magnitude for the concentrations of chlorine species and of oxidized UO2.

Type
Research Article
Copyright
Copyright © Materials Research Society 2004

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