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http://dx.doi.org/10.1016/j.net.2022.01.009

Reprocessing of spent nuclear fuel in carbonate media: Problems, achievements, and prospects  

Stepanov, Sergei I. (Mendeleev University of Chemical Technology)
Boyarintsev, Alexander V. (Mendeleev University of Chemical Technology)
Publication Information
Nuclear Engineering and Technology / v.54, no.7, 2022 , pp. 2339-2358 More about this Journal
Abstract
The review discusses various alternative approaches for spent nuclear fuel (SNF) reprocessing in aqueous carbonate media. The main stages, schemes, and methods of the most well-known and well-described processes for reprocessing SNF and some high-level radioactive waste using carbonate systems developed by research groups in Japan, the United States of America, the Republic of Korea, and the Russian Federation described and compared. The main advantages of such methods are outlined compared to the SNF reprocessing in nitric acid media. The levels of development and proximity of the designed processes to the industrial implementation are shown. The main principle achievements, prospects, and routes for the refinement of such methods for the technology of SNF reprocessing and handling of high-level radioactive waste formulated.
Keywords
Spent nuclear fuel; Radioactive waste; Hydrochemical reprocessing; Carbonate media; Uranium; Plutonium; Minor actinides; Fission products; Alkali metals carbonates; Ammonium carbonates; Hydrogen peroxide;
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