Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Separation and purification of elements from alkaline and carbonate nuclear waste solutions

  • Alexander V. Boyarintsev (Mendeleev University of Chemical Technology) ;
  • Sergei I. Stepanov (Mendeleev University of Chemical Technology) ;
  • Galina V. Kostikova (A.N. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences) ;
  • Valeriy I. Zhilov (A.N. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences) ;
  • Alfiya M. Safiulina (JSC Academician A.A. Bochvar High-Tech Research Institute of Inorganic Materials) ;
  • Aslan Yu Tsivadze (A.N. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences)
  • Received : 2021.08.30
  • Accepted : 2022.09.26
  • Published : 2023.02.25
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Abstract

This article provides a survey of wet (aqueous) methods for recovery, separation, and purification of uranium from fission products in carbonate solutions during the reprocessing of spent nuclear fuel and methods for removal of radionuclides from alkaline radioactive waste. The main methods such as selective direct precipitation, ion exchange, and solvent extraction are considered. These methods were compared and evaluated for reprocessing of spent nuclear fuel in carbonate media according to novel alternative non-acidic methods and for treatment processes of alkaline radioactive waste.

Keywords

Acknowledgement

The work was carried out with the financial support of the Ministry of Education and Science of the Russian Federation, project number 075-15-2020-782.

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