Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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SEPARATION OF STRONTIUM AND CESIUM FROM TERNARY AND QUATERNARY LITHIUM CHLORIDE-POTASSIUM CHLORIDE SALTS VIA MELT CRYSTALLIZATION

  • WILLIAMS, AMMON N. (Department of Mechanical and Nuclear Engineering, Virginia Commonwealth University) ;
  • PACK, MICHAEL (Department of Chemical and Materials Engineering and Nuclear Engineering Program, University of Idaho) ;
  • PHONGIKAROON, SUPATHORN (Department of Mechanical and Nuclear Engineering, Virginia Commonwealth University)
  • Received : 2015.03.23
  • Accepted : 2015.08.09
  • Published : 2015.12.25
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Abstract

Separation of cesium chloride (CsCl) and strontium chloride ($SrCl_2$) from the lithium chloride-potassium chloride (LiCl-KCl) salt was studied using a melt crystallization process similar to the reverse vertical Bridgeman growth technique. A ternary $SrCl_2-LiCl-KCl$ salt was explored at similar growth rates (1.8-5 mm/h) and compared with CsCl ternary results to identify similarities. Quaternary experiments were also conducted and compared with the ternary cases to identify trends and possible limitations to the separations process. In the ternary case, as much as 68% of the total salt could be recycled per batch process. In the quaternary experiments, separation of Cs and Sr was nearly identical at the slower rates; however, as the growth rate increased, $SrCl_2$ separated more easily than CsCl. The quaternary results show less separation and rate dependence than in both ternary cases. As an estimated result, only 51% of the total salt could be recycled per batch. Furthermore, two models have been explored to further understand the growth process and separation. A comparison of the experimental and modeling results reveals that the nonmixed model fits reasonably well with the ternary and quaternary data sets. A dimensional analysis was performed and a correlation was identified to semipredict the segregation coefficient.

Keywords

References

  1. J. Laidler, J. Battles, W. Miller, J. Ackerman, E. Carls, Development of pyroprocessing technologies, Prog. Nucl. Energy 31 (1997) 131-140. https://doi.org/10.1016/0149-1970(96)00007-8
  2. J. Ackerman, T. Johnson, S. Chow, E. Carls, W. Hannum, J. Laidler, Treatment of wastes in the IFR fuel cycle, Prog. Nucl. Energy 31 (1997) 141-154. https://doi.org/10.1016/0149-1970(96)00008-X
  3. J. Willit, W. Miller, J. Battles, Electrorefining of uranium and plutonium-a literature review, J. Nucl. Mater. 195 (1992) 229-249. https://doi.org/10.1016/0022-3115(92)90515-M
  4. S. Phongikaroon, M. Simpson, Equilibrium model for ion exchange between monovalent cations and zeolite-A in a molten salt, in: AIChE Annual Conference Proc., Cincinnati, OH, USA, 2005.
  5. Y. Cho, T. Lee, J. Choi, H. Eun, H. Park, G. Park, Eutectic (LiCl-KCl) waste salt treatment by sequential separation process, Nucl. Eng. Tech. 45 (2013) 675-682. https://doi.org/10.5516/NET.06.2013.022
  6. T. Yoo, D. Labrier, M. Lineberry, M. Shaltry, S. Phongikaroon, Selective reduction of active metal chlorides from molten LiCl-KCl using lithium drawdown, Nucl. Eng. Technol. 44 (2012) 767-772. https://doi.org/10.5516/NET.06.2011.010
  7. M. Shaltry, S. Phongikaroon, M. Simpson, Ion exchange kinetics of fission products between molten salt and zeolite-A, Microporous Mesoporous Mater. 152 (2012) 185-189. https://doi.org/10.1016/j.micromeso.2011.11.035
  8. M. Simpson, M. Gougar, Two-site equilibrium model for ion exchange between monovalent cations and zeolite-A in a molten salt, Ind. Eng. Chem. Res. 42 (2003) 4208-4212. https://doi.org/10.1021/ie020896b
  9. Y. Cho, H. Yang, G. Park, H. Lee, I. Kim, Treatment of LiCl-KCl waste delivered from pyroprocessing of spent nuclear fuel, in: Proceedings of the 2nd International Pyroprocessing Research Conference, Jeju, Korea, 2008, pp. 74-75.
  10. Y. Cho, G. Park, H. Lee, I. Kim, Concentration of cesium and strontium elements involved in a LiCl waste salt by a melt crystallization process, Nucl. Technol. 171 (2010) 325. https://doi.org/10.13182/NT09-7
  11. J. Choi, Y. Cho, T. Lee, H. Eun, J. Kim, I. Kim, G. Park, J. Kang, Inclusion behavior of Cs, Sr, and Ba impurities in LiCl crystal formed by layer-melt crystallization: combined firstprinciples calculation and experimental study, J. Cryst. Growth 371 (2013) 84-89. https://doi.org/10.1016/j.jcrysgro.2013.02.013
  12. A.N. Williams, S. Phongikaroon, M. Simpson, Separation of CsCl from a ternary CsCl-LiCl-KCl salt via a melt crystallization technique for pyroprocessing waste minimization, Chem. Eng. Sci. 89 (2013) 258-263. https://doi.org/10.1016/j.ces.2012.12.012
  13. J.R. Versey, S. Phongikaroon, M.F. Simpson, Separation of CsCl from LiCl-CsCl molten salt by cold finger melt crystallization, Nucl. Eng. Tech. 46 (2014) 395-406. https://doi.org/10.5516/NET.06.2013.082
  14. A.N. Wiliams, Zone Freezing Study for Pyrochemical Process Waste Minimization, MS Thesis, University of Idaho, Idaho Falls, ID, 2012.
  15. E. Scheil, Bemerkungen zur schichtkristall bildung, Z. Metallkd. 23 (1931) 237.
  16. W.A. Tiller, K.A. Jackson, J.W. Rutter, B. Chalmers, The redistribution of solute atoms during the solidification of melt, Acta Metallurgica 31 (1953) 15-39.

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