Skip to main content
SpringerLink
Log in

Uranium recovery via melt separation of rare earth elements and chemical oxidation

  • Published:
Journal of Radioanalytical and Nuclear Chemistry Aims and scope Submit manuscript

Abstract

Pyroprocessing of spent fuels, especially the recovery of U, improves the overall efficiency of nuclear recycling. The recovery of U/Transuranic elements (TRU) during the removal of rare earth elements (REEs) via melting was evaluated. Uranium was used as a surrogate material instead of TRU, and the distributions of U, Nd, and Ce were evaluated after melting. Uranium and REEs were clearly separated after melting and the U component contained < 2 wt% of REEs as impurities. Melting recovery of U was applicable after the electrorefining process to obtain a high enough concentration of REEs above their solubility in U. The REE component contained ~3 wt% U, and U was also recovered through the chemical oxidation of REEs with UCl3. The U remaining in the product following chemical oxidation exceeded 87%. Based on these results, a new method of recovering U/Pu from U/Pu/REE-alloys following the electrorefining process is proposed. This approach can be used to improve the recycling of spent nuclear fuels, thereby enhancing the efficiency and sustainability of nuclear systems.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Log in via an institution

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Fig. 1
Fig. 2
Fig. 3
Fig. 4
Fig. 5
Fig. 6
Fig. 7
Fig. 8
Fig. 9
Fig. 10
Fig. 11

Similar content being viewed by others

References

  1. Yoo JH, Lee B-J, Lee HS, Kim EH (2007) Investigation of pyroprocessing concept and its applicability as an alternative technology for conventional fuel cycle. J Nucl Fuel Cycle Waste Technol 5(4):283–295

    Google Scholar 

  2. Yoo JH, Hong KP, Lee HS (2008) A conceptual design study for a spent fuel pyroprocessing facility of a demonstration scale. J Nucl Fuel Cycle Waste Technol 6(3):233–244

    Google Scholar 

  3. 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(3):247–265. https://doi.org/10.13182/NT171-247

    Article  CAS  Google Scholar 

  4. Lee JH, Kang YH, Hwang SC, Shim JB, Ahn BG, Kim EH, Park SW (2006) Electrodeposition characteristics of uranium in molten LiCl–KCl eutectic and its salt distillation behavior. J Nucl Sci Technol 43(3):263–269. https://doi.org/10.1080/18811248.2006.9711088

    Article  CAS  Google Scholar 

  5. Lee JH, Kang YH, Hwang SC, Kim EH, Yoo JH, Park HS (2007) Separation characteristics of a spent fuel surrogate in the molten salt electrorefining process. J Mater Process Technol 189(1–3):268–272. https://doi.org/10.1016/j.jmatprotec.2007.01.034

    Article  CAS  Google Scholar 

  6. Simpson F (2012) Developments of spent nuclear fuel pyroprocessing technology at Idaho national laboratory, INL/EXT-12-25124. US. Department of Energy Idaho National Laboratory, Idaho Falls

  7. Vaden D, Li SX, Westphal BR, Davies KB, Johnson TA, Pace DM (2008) Engineering-scale liquid cadmium cathode experiments. Nucl Technol 162(2):124–128. https://doi.org/10.13182/NT08-A3938

    Article  CAS  Google Scholar 

  8. Li SX, Herrmann SD, Goff KM, Simpson MF, Benedict RW (2009) Actinide recovery experiments with bench-scale liquid cadmium cathode in real fission product-laden molten salt. Nucl Technol 165(2):190–199. https://doi.org/10.13182/NT09-A4085

    Article  CAS  Google Scholar 

  9. Li SX, Herrmann SD, Simpson MF (2009) Experimental investigations into U/TRU recovery using a liquid cadmium cathode and salt containing high rare Earth concentrations In: Proceedings of global 2009, vol 9058. Paris, France, Sep. 6–11. pp 1174–1183

  10. Stevenson CE (1987) The EBR-II fuel cycle story. American Nuclear Society, La Grange Park, pp 85–120

    Google Scholar 

  11. Jang J, Kim T, Kim G-Y, Yoon D, Lee S (2019) Uranium recovery via electrochemical deposition with a liquid zinc cathode followed by electrochemical oxidation of rare earth metals. J Nucl Mat 520:245–251. https://doi.org/10.1016/j.jnucmat.2019.04.024

    Article  CAS  Google Scholar 

  12. Paek S, Yoon D, Jang J, Kim G-Y, Lee S-J (2019) Removal of rare earth elements from a U/RE ingot via a reaction with UCl3. J Radioanal Nucl Chem 322:495–502. https://doi.org/10.1007/s10967-019-06716-1

    Article  CAS  Google Scholar 

  13. Merck PTE (2019) Merch KGaA, Darmstadt, Germany

  14. Kurata M (2012) Phase diagrams of actinide alloys. In: Konings RJM, Allen TR, Stoller RE, Yamanaka S (eds) Comprehensive nuclear materials. Elsevier, Oxford, pp 139–195

    Chapter  Google Scholar 

  15. Nuclear Energy Agency (2012) Spent nuclear fuel reprocessing flowsheet, NEA/NSC/WPFC/DOC(2012)15. Organisation for Economic Co-operation and Development

  16. Willamson MA, Willit JL (2011) Pyroprocessing flowsheets for recycling used nuclear fuel. Nucl Eng Technol 43(4):329–334. https://doi.org/10.5516/NET.2011.43.4.329

    Article  CAS  Google Scholar 

  17. Lee HS, Park GI, Kang KH, Hur JM, Kim JG, Ahn D-H, Cho YZ, Kim EH (2011) Pyroprocessing technology development at KAERI. Nucl Eng Technol 43(4):317–328. https://doi.org/10.5516/NET.2011.43.4.317

    Article  CAS  Google Scholar 

  18. Song KC, Lee H-S, Hur JM, Kim J-G, Ahn DH, Cho YZ (2010) Status of pyroprocessing technology development in KOREA. Nucl Eng Technol 42(2):131–144. https://doi.org/10.5516/NET.2010.42.2.131

    Article  CAS  Google Scholar 

  19. Outotec (2018) HSC Chemistry, ver. 9.0. Outotec research information center, Finland

  20. Jang J, Kim T, Park S, Kim G-Y, Kim S, Lee S (2017) Evaporation behavior of lithium, potassium, uranium and rare earth chlorides in pyroprocessing. J Nucl Mater 497:30–36. https://doi.org/10.1016/j.jnucmat.2017.10.047

    Article  CAS  Google Scholar 

  21. Kim GY, Kim TJ, Ahn DH, Paek S (2013) Formation of Nd–Cd Intermetallic Compounds in LiCl–KCl. Asian J Chem 25(13):7527–7530

    Article  Google Scholar 

  22. Kim GY, Yoon D, Paek S, Kim SH, Kim TJ, Ahn DH (2012) A study on the electrochemical deposition behavior of uranium ion in a LiCl–KCl molten salt on solid and liquid electrode. J Electroanal Chem 682:128–135. https://doi.org/10.1016/j.jelechem.2012.07.025

    Article  CAS  Google Scholar 

Download references

Acknowledgements

This work was supported by the National Research Foundation of Korea [Grant Number 2017M2A8A5015079].

Author information

Authors and Affiliations

  1. Pyroprocess Technology Division, Korea Atomic Energy Research Institute, Daedeok-daero 989-111, Yuseong-gu, Daejeon, 34057, Republic of Korea

    Junhyuk Jang, Tackjin Kim, Gha-Young Kim, Seungwoo Paek & Sungjai Lee

Authors
  1. Junhyuk Jang
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Tackjin Kim
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Gha-Young Kim
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. Seungwoo Paek
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. Sungjai Lee
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to Junhyuk Jang.

Additional information

Publisher's Note

Springer Nature remains neutral with regard to jurisdictional claims in published maps and institutional affiliations.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Jang, J., Kim, T., Kim, GY. et al. Uranium recovery via melt separation of rare earth elements and chemical oxidation. J Radioanal Nucl Chem 324, 869–877 (2020). https://doi.org/10.1007/s10967-020-07112-w

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10967-020-07112-w

Keywords

Search

Navigation