Title: Oxidative Dissolution of Actinide Oxides in H2O2 Containing Aqueous Solution - A Preliminary Study
Citation: JOURNAL OF NUCLEAR MATERIALS vol. 397 no. 1-3 p. 128-131
Publication Year: 2010
JRC N°: JRC57129
ISSN: 0022-3115
URI: www.elsevier.com/locate/jnucmat
DOI: 10.1016/j.jnucmat.2009.11.027
Type: Articles in periodicals and books
Abstract: Oxidative dissolution of spent nuclear fuel is an important issue in the safety assessment of a future geological repository for spent nuclear fuel. Although UO2 constitutes, in terms of mass, the majority of the spent fuel material, its main radiotoxicity is (after extended storage times) contained in actinides with half lives shorter than that of 238-uranium, such as isotopes of Np and Pu. Relatively little information is available on the dissolution behavior of Np and Pu in comparable environments. This work investigates the oxidative dissolution of NpO2 and PuO2 in non-complexing aqueous solutions containing H2O2 and compares their behavior with that of UO2. We have found that oxidative dissolution takes place for all three actinides in the presence of H2O2. Based on the obtained dissolution rates, we would not expect the dissolution of the actinides to be congruent. Instead, in a system without complexing agent, the release rates of Np and Pu are expected to be lower than the U release rate.
JRC Directorate:Nuclear Safety and Security

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