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Quantitative calculations on the reoxidation behavior of oxide reduction system for pyroprocessing

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Abstract

Reoxidation reaction of metallic uranium in the oxide reduction system for pyroprocessing of used nuclear fuels is quantitatively investigated via calculating thermodynamic equilibrium compositions. The calculations consider three operating parameters; LiCl/U ratio, Li2O concentration, and excess metallic Li. The results suggest that decreasing LiCl/U ratio and Li2O concentration reduce the extent of the reoxidation reaction. The presence of excess metallic Li suppresses the reoxidation reaction more effectively; the calculated amount of reoxidized U from pure metallic U is merely 0.6% with 9 wt% (vs. Li2O) of excess Li. Excess Li can be synthesized in situ during the oxide reduction operation.

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References

  1. Wigeland RA, Bauer TH, Fanning TH, Morris EE (2006) Separations and transmutation criteria to improve utilization of a geologic repository. Nucl Technol 154:95–106

    CAS  Google Scholar 

  2. Stevenson CE (1987) The EBR-II fuel cycle story. American Nuclear Society, USA

    Google Scholar 

  3. Lee H, Park GI, Kang KH, Hur JM, Kim JG, Ahn DH, Cho YZ, Kim EH (2011) Pyroprocessing technology development at KAERI. Nucl Eng Technol 43:317–328

    Article  CAS  Google Scholar 

  4. Herrmann SD, Li SX, Simpson MF, Phongikarroon S (2006) Electrolytic reduction of spent nuclear oxide fuel as part of an integral process to separate and recover actinides from fission products. Sep Sci Technol 41:1965–1983

    Article  CAS  Google Scholar 

  5. Herrmann SD, Li SX (2010) Separation and recovery of uranium metal from spent light water reactor fuel via electrolytic reduction and electrorefining. Nucl Technol 171:247–265

    Article  CAS  Google Scholar 

  6. Sakamura Y, Kurata M, Inoue T (2006) Electrochemical reduction of UO2 in molten CaCl2 or LiCl. J Electrochem Soc 153:D31–D39

    Article  CAS  Google Scholar 

  7. Choi EY, Lee JW, Park JJ, Hur JM, Kim JK, Jung KY, Jeong SM (2012) Electrochemical reduction behavior of a highly porous SIMFUEL particle in a LiCl molten salt. Chem Eng J 207–208:514–520

    Article  Google Scholar 

  8. Jeon MK, Choi EY, Kim SW, Lee SK, Kang HW, Hong SS, Lee J, Hur JM, Jeon SC, Lee JH, Cho YZ, Ahn DH (2016) Electrolytic reduction rate of porous UO2 pellets. Korean J Chem Eng 33:2235–2239

    Article  CAS  Google Scholar 

  9. Choi EY, Jeon MK, Lee J, Kim SW, Lee SK, Lee SJ, Heo DH, Kang HW, Jeon SC, Hur JM (2017) Reoxidation of uranium metal immersed in a Li2O-LiCl molten salt after electrolytic reduction of uranium oxide. J Nucl Mater 485:90–97

    Article  CAS  Google Scholar 

  10. Hur JM, Jeong SM, Lee H (2010) Underpotential deposition of Li in a molten LiCl-Li2O electrolyte for the electrochemical reduction of U from uranium oxides. Electrochem Commun 12:706–709

    Article  CAS  Google Scholar 

  11. Liu J, Poignet JC (1990) Measurement of the activity of lithium in dilute solutions in molten lithium chloride between 650 and 800  C. J Appl Electrochem 20:864–867

    Article  CAS  Google Scholar 

  12. Roine A (2002) Outokumpu HSC chemistry for windows. Outokumpu Research Oy, Finland

    Google Scholar 

Download references

Acknowledgements

This research was sponsored by the Nuclear R&D program of the Korean Ministry of Science, ICT & Future Planning (2017M2A8A5015077).

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Authors and Affiliations

  1. Nuclear Fuel Cycle Process Development Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero 989-111, Yuseong-gu, Daejeon, 305-353, Republic of Korea

    Min Ku Jeon, Eun-Young Choi & **-Mok Hur

  2. Department of Quantum Energy Chemical Engineering, University of Science and Technology, 217 Gajeong-ro, Yuseong-gu, Daejeon, 305-350, Republic of Korea

    Min Ku Jeon

  3. Pyroprocessing Division, Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID, 83415, USA

    Tae-Sic Yoo

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  1. Min Ku Jeon
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  2. Tae-Sic Yoo
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  3. Eun-Young Choi
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  4. **-Mok Hur
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Correspondence to Min Ku Jeon.

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Jeon, M.K., Yoo, TS., Choi, EY. et al. Quantitative calculations on the reoxidation behavior of oxide reduction system for pyroprocessing. J Radioanal Nucl Chem 313, 155–159 (2017). https://doi.org/10.1007/s10967-017-5264-4

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  • DOI: https://doi.org/10.1007/s10967-017-5264-4

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