Abstract
Advances in the CARBEX process, a new aqueous chemical method for reprocessing of spent nuclear fuel (SNF) in carbonate media, are considered. A review of carbonate methods for SNF reprocessing is given. The CARBEX process concept is presented and experimental data for every stage of the CARBEX process: high-temperature oxidation of spent fuel composition, its oxidative dissolution in carbonate aqueous solutions, extraction refining of U(VI) and Pu(VI), solid-phase re-extraction of carbonate complexes of U(VI) and Pu(VI), and obtaining of uranium and plutonium dioxide powders for fabrication of ceramic nuclear fuel, are discussed. It was shown that the CARBEX process can be more effective and safe than the well-known industrial PUREX process.
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Original Russian Text © S.I. Stepanov, A.V. Boyarintsev, M.V. Vazhenkov, B.F. Myasoedov, E.O. Nazarov, A.M. Safiulina, I.G. Tananaev, Hen Vin So, A.M. Chekmarev, A.Yu. Civadze, 2010, published in Rossiiskii Khimicheskii Zhurnal, 2010, Vol. 54, No. 3, pp. 25–34.
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Stepanov, S.I., Boyarintsev, A.V., Vazhenkov, M.V. et al. CARBEX process, a new technology of reprocessing of spent nuclear fuel. Russ J Gen Chem 81, 1949 (2011). https://doi.org/10.1134/S1070363211090404
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DOI: https://doi.org/10.1134/S1070363211090404