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Oxidative leaching of uranium from SIMFUEL using Na2CO3–H2O2 solution

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Abstract

A feasibility and basic study to find a possibility to develop such a process for recovering U alone from spent fuel by using the methods of an oxidative leaching and a precipitation of U in high alkaline carbonate media was newly suggested with the characteristics of a highly enhanced proliferation-resistance and more environmental friendliness. This study has focused on the examination of an oxidative leaching of uranium from SIMFUEL powders contained 16 elements (U, Ce, Gd, La, Nd, Pr, Sm, Eu, Y, Mo, Pd, Ru, Zr, Ba, Sr, and Te) using a Na2CO3 solution with hydrogen peroxide. U3O8 was dissolved more rapidly than UO2 in a carbonate solution. However, in the presence of H2O2, we can find out that the leaching rates of the reduced SIMFUEL powder are faster than the oxidized SIMFUEL powder. In carbonate solutions with hydrogen peroxide, uranium oxides were dissolved in the form of uranyl peroxo-carbonato complexes. UO2(O2) x (CO3) y 2−2x−2y, where x/y has 1/2, 2/1.

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Acknowledgment

This work was supported by Nuclear Research and Development Program of the Korea Science and Engineering Foundation (KOSEF) grant funded by the Ministry of Education, Science and Technology of Korea.

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Authors and Affiliations

  1. Nuclear Fuel Cycle Development Division, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of Korea

    Dong-Yong Chung, Heui-Seung Seo, Jae-Won Lee, Han-Beom Yang, Eil-Hee Lee & Kwang-Wook Kim

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  1. Dong-Yong Chung
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  2. Heui-Seung Seo
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Correspondence to Dong-Yong Chung.

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Chung, DY., Seo, HS., Lee, JW. et al. Oxidative leaching of uranium from SIMFUEL using Na2CO3–H2O2 solution. J Radioanal Nucl Chem 284, 123–129 (2010). https://doi.org/10.1007/s10967-009-0443-6

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  • DOI: https://doi.org/10.1007/s10967-009-0443-6

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