Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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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)
  • Received : 2020.10.18
  • Accepted : 2022.01.04
  • Published : 2022.07.25
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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

Acknowledgement

The Mendeleev University of Chemical Technology financially supported the reported study.

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