DOI QR코드

DOI QR Code

Employing high-temperature gas flux in a residual salt separation technique for pyroprocessing

  • 투고 : 2019.01.22
  • 심사 : 2019.05.26
  • 발행 : 2019.10.25

초록

Residual salt separation is an essential step in pyroprocessing because its reaction products, as prepared by electrochemical unit processes, contain frozen residual electrolyte species, which are generally composed of alkali-metal chloride salts (e.g., LiCl, KCl). In this study, a simple technique that utilizes high-temperature gas flux as a driving force to melt and push out the residual salt in the reaction products was developed. This technique is simple as it only requires the use of a heating gun in combination with a gas injection system. Consequently, $LiNO_3-ZrO_2$ and $LiCl-ZrO_2$ mixtures were successfully separated by the high-temperature gas injection (separation efficiency > 93%), thereby demonstrating the viability of this simple technique for residual salt separation.

키워드

과제정보

연구 과제 주관 기관 : National Research Foundation of Korea (NRF)

참고문헌

  1. H.-S. Lee, G.-I. Park, K.-H. Kang, J.-M. Hur, J.-G. Kim, D.-H. Ahn, Y.-Z. Cho, E.-H. Kim, Pyroprocessing technology development at KAERI, Nucl. Eng. Technol. 43 (2011) 317-328. https://doi.org/10.5516/NET.2011.43.4.317
  2. T. Inoue, L. Koch, Development of pyroprocessing and its future direction, Nucl. Eng. Technol. 40 (2008) 183-190. https://doi.org/10.5516/NET.2008.40.3.183
  3. E.-Y. Choi, S.M. Jeong, Electrochemical processing of spent nuclear fuels: an overview of oxide reduction in pyroprocessing technology, Pro. Nat. Sci. Mater. 25 (2015) 572-582. https://doi.org/10.1016/j.pnsc.2015.11.001
  4. A.R. Brunsvold, P.D. Roach, B.R. Westphal, Design and development of a cathode processor for electrometallurgical treatment of spent nuclear fuel, in: Proceedings of ICONE 8: 8th International Conference on Nuclear Engineering, Baltimore, MD, USA, April 2-6, 2000.
  5. I. Kim, S.C. Oh, S.C.H.S. Im, J.-M. Hur, H.S. Lee, Distillation of LiCl from the LiCl-$Li_2O$ molten salt of the electrolytic reduction process, J. Radioanal. Nucl. Chem. 295 (2013) 1413-1417. https://doi.org/10.1007/s10967-012-1997-2
  6. J.-H. Lee, Y.-H. Kang, S.-C. Hwang, J.-B. Shim, B.-G. Ahn, E.-H. Kim, S.-W. Park, Electrodeposition characteristics of uranium in molten LiCl-KCl eutectic and its salt distillation behavior, J. Nucl. Sci. Technol. 43 (2006) 263-269. https://doi.org/10.1080/18811248.2006.9711088
  7. B.R. Westphal, K.C. Marsden, J.C. Price, D.V. Laug, On the development of a distillation process for the electrometallurgical treatment of irradiated spent nuclear fuel, Nucl. Eng. Technol. 40 (2008) 163-174. https://doi.org/10.5516/NET.2008.40.3.163
  8. E.-Y. Choi, M.K. Jeon, J.-M. Hur, Reoxidation of uranium in electrochemically reduced simulated oxide fuel during residual salt distillation, J. Radioanal. Nucl. Chem. 314 (2017) 207-213. https://doi.org/10.1007/s10967-017-5404-x
  9. C.P. Wang, Z.S. Li, W. Fang, X.J. Liu, Thermodynamic database and the phase diagrams of the (U, Th, Pu)-X binary system, J. Phase Equilibria Diffusion 30 (2009) 535-552. https://doi.org/10.1007/s11669-009-9562-6
  10. E.-Y. Choi, J. Lee, D.H. Heo, J.-M. Hur, Separation of electrolytic reduction product from stainless steel wire mesh cathode basket via salt draining and reuse of the cathode basket, Sci. Technol. Nucl. Ins. 2017 (2017) 3698053.
  11. S.-W. Kim, J.K. Lee, D. Ryu, M.K. Jeon, S.-S. Hong, D.H. Heo, E.-Y. Choi, Residual salt separation technique using centrifugal force for pyroprocessing, Nucl. Eng. Technol. 50 (2018) 1184-1189. https://doi.org/10.1016/j.net.2018.06.009
  12. E.-Y. Choi, J. Lee, S.-J. Lee, S.-W. Kim, S.-C. Jeon, S.H. Cho, S.C. Oh, M.K. Jeon, S.K. Lee, H.W. Kang, J.-M. Hur, Stability of yttria-stabilized zirconia during pyroprocessing test, J. Nucl. Mater. 475 (2016) 57-61. https://doi.org/10.1016/j.jnucmat.2016.03.030
  13. A.R. Shankar, U.K. Mudali, R. Sole, H.S. Khatak, B. Raj, Plasma-sprayed yttria-stabilized zirconia coatings on type 316L stainless steel for pyrochemical reprocessing plant, J. Nucl. Mater. 372 (2008) 226-232. https://doi.org/10.1016/j.jnucmat.2007.03.175
  14. H.-Y. Lee, K.-H. Baik, Comparison of corrosion resistance between $Al_2O_3$ and YSZ coatings against high temperature LiCl-$Li_2O$ molten salt, Met. Mater. Int. 15 (2009) 783-787. https://doi.org/10.1007/s12540-009-0783-8
  15. L. Li, L. Shi, S. Cao, Y. Zhang, Y. Wang, $LiNO_3$ molten salt assisted synthesis of spherical nano-sized YSZ powders in a reverse microemulsion system, Mater. Lett. 62 (2008) 1909-1912. https://doi.org/10.1016/j.matlet.2007.10.039
  16. E.-Y. Choi, M.K. Jeon, J. Lee, S.-W. Kim, S.K. Lee, S.-J. Lee, D.H. Heo, H.W. Kang, S.-C. Jeon, J.-M. Hur, Reoxidation of uranium metal immersed in a $Li_2O$-LiCl molten salt after electrolytic reduction of uranium oxide, J. Radioanal. Nucl. Chem. 485 (2017) 90-97.

피인용 문헌

  1. Effects of additives on the thermal stability of silver tellurite glass system vol.165, 2022, https://doi.org/10.1016/j.anucene.2021.108683