Nuclear Engineering and Technology

  • 제51권7호
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  • Pages.1799-1804
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  • 2019
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Reprocessing of simulated voloxidized uranium-oxide SNF in the CARBEX process

  • Boyarintsev, Alexander V. (Dmitry Mendeleev University of Chemical Technology of Russia) ;
  • Stepanov, Sergei I. (Dmitry Mendeleev University of Chemical Technology of Russia) ;
  • Kostikova, Galina V. (A.N. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences) ;
  • Zhilov, Valeriy I. (A.N. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences) ;
  • Chekmarev, Alexander M. (Dmitry Mendeleev University of Chemical Technology of Russia) ;
  • Tsivadze, Aslan Yu. (A.N. Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences)
  • 투고 : 2019.03.08
  • 심사 : 2019.05.22
  • 발행 : 2019.10.25
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초록

The concept of a new method, the CARBEX (CARBonate EXtraction) process, was proposed for reprocessing of spent uranium oxide fuel. The proposed process is based on use of water solutions of $Na_2CO_3$ or $(NH_4)_2CO_3$ and solvent extraction (SE) by the quaternary ammonium compounds for selective recovery and purification of U from the fission products (FPs). Applying of SE allows to reach high degree of purification of U from FPs. Carrying out the processes in poorly aggressive alkaline carbonate media leads to increasing safety of SNF's reprocessing and better selectivity of separation of lanthanides and actinides. Moreover carbonate reprocessing media allows to carry out a recycling and regeneration of reagents. We have been done laboratory scale experiments on the extraction components of simulated voloxidated spent fuel in the solutions of NaOH or $Na_2CO_3-H_2O_2$ and recovery of U from carbonate solutions by SE method using carbonate of methyltrioctylammonium in toluene. It was shown that the purification factors of U from impurities of simulated FPs reached values $10^3-10^5$. The received results support our opinion that CARBEX after the further development can become more safe, simple and profitable method of spent fuel reprocessing.

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과제정보

연구 과제 주관 기관 : Dmitry Mendeleev University of Chemical Technology of Russia

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피인용 문헌

  1. Separation of uranium(VI) and americium(III) by Extraction from Na2CO3-H2O2 solutions using methyltrioctylammonium carbonate in toluene vol.39, pp.7, 2019, https://doi.org/10.1080/07366299.2021.1876993