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http://dx.doi.org/10.1016/j.net.2019.05.023

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

Kim, Sung-Wook (Korea Atomic Energy Research Institute)
Heo, Dong Hyeon (Korea Atomic Energy Research Institute)
Kang, Hyun Woo (Korea Atomic Energy Research Institute)
Hong, Sun-Seok (Korea Atomic Energy Research Institute)
Lee, Sang-Kwon (Korea Atomic Energy Research Institute)
Jeon, Min Ku (Korea Atomic Energy Research Institute)
Hur, Jin-Mok (Korea Atomic Energy Research Institute)
Choi, Eun-Young (Korea Atomic Energy Research Institute)
Publication Information
Nuclear Engineering and Technology / v.51, no.7, 2019 , pp. 1866-1870 More about this Journal
Abstract
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.
Keywords
Pyroprocessing; Molten salt; Residual salt separation; Liquid-solid separation; Heating gun;
Citations & Related Records
Times Cited By KSCI : 3  (Citation Analysis)
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1 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.   DOI
2 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.
3 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.   DOI
4 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.   DOI
5 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.   DOI
6 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.   DOI
7 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.   DOI
8 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.
9 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.   DOI
10 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.   DOI
11 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.   DOI
12 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.   DOI
13 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.   DOI
14 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.
15 T. Inoue, L. Koch, Development of pyroprocessing and its future direction, Nucl. Eng. Technol. 40 (2008) 183-190.   DOI
16 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.   DOI