DOI QR코드

DOI QR Code

EUTECTIC(LiCl-KCl) WASTE SALT TREATMENT BY SEQUENCIAL SEPARATION PROCESS

  • Cho, Yung-Zun (Nuclear Fuel Cycle Waste Treatment Research Division, Korea Atomic Energy Research Institute) ;
  • Lee, Tae-Kyo (Nuclear Fuel Cycle Waste Treatment Research Division, Korea Atomic Energy Research Institute) ;
  • Choi, Jung-Hun (Nuclear Fuel Cycle Waste Treatment Research Division, Korea Atomic Energy Research Institute) ;
  • Eun, Hee-Chul (Nuclear Fuel Cycle Waste Treatment Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Hwan-Seo (Nuclear Fuel Cycle Waste Treatment Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Geun-Il (Nuclear Fuel Cycle Waste Treatment Research Division, Korea Atomic Energy Research Institute)
  • 투고 : 2013.03.06
  • 심사 : 2013.04.29
  • 발행 : 2013.10.25

초록

The sequential separation process, composed of an oxygen sparging process for separating lanthanides and a zone freezing process for separating Group I and II fission products, was evaluated and tested with a surrogate eutectic waste salt generated from pyroprocessing of used metal nuclear fuel. During the oxygen sparging process, the used lanthanide chlorides (Y, Ce, Pr and Nd) were converted into their sat-insoluble precipitates, over 99.5% at $800^{\circ}C$; however, Group I (Cs) and II (Sr) chlorides were not converted but remained within the eutectic salt bed. In the next process, zone freezing, both precipitation of lanthanide precipitates and concentration of Group I/II elements were preformed. The separation efficiency of Cs and Sr increased with a decrease in the crucible moving speed, and there was little effect of crucible moving speed on the separation efficiency of Cs and Sr in the range of a 3.7 - 4.8 mm/hr. When assuming a 60% eutectic salt reuse rate, over 90% separation efficiency of Cs and Sr is possible, but when increasing the eutectic salt reuse rate to 80%, a separation efficiency of about 82 - 86 % for Cs and Sr was estimated.

키워드

참고문헌

  1. M.F. Simpson and P. Sachdev, "Development of electrorefiner waste salt disposal process for the EBR-II spent fuel treatment project", Nuclear Engineering and Technology, 40, 175-182 (2008). https://doi.org/10.5516/NET.2008.40.3.175
  2. D. Hudry, I. Bardez, A. Rakhmatullin, C. Bessada, F. Bart, S. Jobic and P. Deniard, "Synthesis of rare earth phosphate in molten LiCl-KCl eutectic: Application to preliminary treatment of chlorinated waste streams containing fission products", Journal of Nuclear Materials, 381, 284-289 (2008). https://doi.org/10.1016/j.jnucmat.2008.09.005
  3. Y. Katayama, R. Hagiwara and Y. Ito, "Precipitation of rare earth compounds in LiCl-KCl eutectic", Journal of Electrochemical Society, 142, 2174-2178 (1995). https://doi.org/10.1149/1.2044271
  4. Y.Z. Cho, G.H. Park, H.C. Yang, D.S. Han, H.S. Lee and I.T. Kim, "Minimization of eutectic salt waste from pyroprocessing by oxidative precipitation of lanthanides", Journal of Nuclear Science and Technology, 46, 1004-1011 (2009). https://doi.org/10.1080/18811248.2009.9711610
  5. I. Amamoto, H. Kofuji, M. Myochin , Y. Takasaki and T. Terai, "Phosphates behaviors in conversion of FP chlorides", Journal of Nuclear Materials, 389, 142-148 (2009). https://doi.org/10.1016/j.jnucmat.2009.01.019
  6. Y.Z. Cho, T.K. Lee, H.C. Eun, J.H. Choi, I.T. Kim and G.I. Park, "Purification of used eutectic (LiCl-KCl) salt electrolyte from pyroprocessing", Journal of Nuclear Materials, 437, 47-54 (2013). https://doi.org/10.1016/j.jnucmat.2013.01.344
  7. M.F. Simpson, T.S. Yoo, R.W. Benedict, S. Phongikaroon, S. Frank, P. Sachdev and K. Hartman, "Strategic minimization of high level waste from pyroprocessing of spent nuclear fuel", Proc. Global 2007, Boise, USA (2007).
  8. M.T. Harrison, H.E. Simms, A. Jackson and R.G. Lewin, "Salt waste treatment from a LiCl-KCl based pyrochemical spent fuel treatment process", Radiochim. Acta, 96, 295-301 (2008).
  9. Y.Z. Cho, H.C. Yang, H.C. Eun, E.H. Kim and I.T. Kim, "Carbonate reaction of alkaline-earth element by carbonate agent injection method", Journal of Nuclear Science and Technology, 45, 459-463 (2008). https://doi.org/10.1080/18811248.2008.9711455
  10. P. Yang, J. Liao, B. Shen, P. Shao, H. Ni and Z. Yin, "Growth of large-size crystal of PbWO4 by vertical Bridgman method with multi-crucibles", Journal of Crystal Growth, 236, 589-595 (2002). https://doi.org/10.1016/S0022-0248(01)02385-5
  11. G. Li, W. Jie, G. Yang and T. Wang, "Behavior of impurities in Cd0.85Zn0.15Te crystals grown by vertical Bridgman method", Materials Science and Engineering B, 113, 7-12 (2004). https://doi.org/10.1016/j.mseb.2004.05.006
  12. B.R. Pamplin, Crystal growth, Pergamon press, New York, 1975.
  13. Web site: http://www.factsage.com
  14. S.C. Chapra and R.P. Canale, Numerical methods for engineers, McGraw-Hill, New York, 1988.

피인용 문헌

  1. Development, characterization and dissolution behavior of calcium-aluminoborate glass wasteforms to immobilize rare-earth oxides vol.8, pp.1, 2018, https://doi.org/10.1038/s41598-018-23665-z