Introduction of MKZP (Min Ku Zirconium Process) as an alternative to pyroprocessing for used nuclear fuel management

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• 作者：Min Ku Jeon ; Jin Mok Hur ; Do-Hee Ahn
• 关键词：Pyroprocessing ; Oxide reduction ; Cladding hull chlorination ; Used nuclear fuel ; Electro ; refining
• 刊名：Journal of Radioanalytical and Nuclear Chemistry
• 出版年：2016
• 出版时间：May 2016
• 年：2016
• 卷：308
• 期：2
• 页码：747-752
• 全文大小：404 KB
• 参考文献：1.Lee H, Park GI, Kang KH, Hur JM, Kim JG, Ahn DH, Cho YZ, Kim EH (2011) Pyroprocessing technology development at KAERI. Nucl Eng Technol 43:317–328CrossRef
  2.Song KC, Lee H, Hur JM, Kim JG, Ahn DH, Cho YZ (2010) Status of pyroprocessing technology development in Korea. Nucl Eng Technol 42:131–144CrossRef
  3.Simpson MF (2012) Development of spent nuclear fuel pyroprocessing technology at Idaho National Laboratory. INL/EXT-12-25124, Idaho National Laboratory
  4.Hur JM, Hong SS, Lee H (2010) Reduction of U3O8 to U by a metallic reductant, Li. J Radioanal Nucl Chem 284:7–11CrossRef
  5.Choi EY, Kim JK, Im HS, Choi IK, Na SH, Lee JW, Jeong SM, Hur JM (2013) Effect of the UO2 form on the electrochemical reduction rate in a LiCl–Li2O molten salt. J Nucl Mater 437:178–187CrossRef
  6.Jeong SM, Shin HS, Hong SS, Hur JM, Do JB, Lee HS (2010) Electrochemical reduction behavior of U3O8 powder in a LiCl molten salt. Electrochim Acta 55:1749–1755CrossRef
  7.Park W, Hur JM, Hong SS, Choi EY, Im HS, Oh SC, Lee JW (2013) An experimental study for Li recycling in an electrolytic reduction process for UO2 with a Li2O–LiCl molten salt. J Nucl Mater 441:232–239CrossRef
  8.Roine A (2002) Outokumpu HSC chemistry for windows. Pori, Finland
  9.Sakamura Y, Inoue T, Iwai T, Moriyama H (2005) Chlorination of UO2, PuO2 and rare earth oxides using ZrCl4 in LiCl–KCl eutectic melt. J Nucl Mater 340:39–51CrossRef
  10.Americium(III) chloride, wikipedia. https://​en.​wikipedia.​org/​wiki/​Americium(III)_​chloride
  11.Collins ED, Del Cul GD, Spencer BB, Brunson RR, Johnson JA, Terekhov DS, Emmanuel NV (2012) Process development studies for zirconium recovery/recycle from used nuclear fuel cladding. Procedia Chem 7:72–76CrossRef
  12.Bresee JC, Griffith AR, Collins ED, Jubin RT, DelCul GD (2012) Chemical pre-treatment of used fuel for long-term storage. Procedia Chem 7:66–71CrossRef
  13.Jeon MK, Kang KH, Heo CM, Yang JH, Lee CH, Park GI (2012) Effect of oxidation conditions on chlorination reaction of Zircaloy-4 hulls. J Nucl Mater 424:153–157CrossRef
  14.Jeon MK, Kang KH, Park GI, Lee YS (2012) Chlorination reaction behavior of Zircaloy-4 hulls: experimental and theoretical approaches. J Radioanal Nucl Chem 292:513–517CrossRef
  15.Yasuike Y, Iwasa S, Suzuki K, Kobayashi H, Amano O, Sato N (2003) Recycle of Zr metal from hull wastes by treatment of chlorination and metalization. In: Proceedings of ICEM’03: the 9th international conference on radioactive waste management and environmental remediation, Oxford, England
  16.Ewing RC (1999) Nuclear waste forms for actinides. Proc Natl Acad Sci USA 96:3432–3439CrossRef
  
• 作者单位：Min Ku Jeon (1) (2)
  Jin Mok Hur (1)
  Do-Hee Ahn (1) (2)
  
  1. Nuclear Fuel Cycle Process Development Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of Korea
  2. Department of Quantum Energy Chemical Engineering, University of Science and Technology, 217 Gajeong-ro, Yuseong-gu, Daejeon, 305-350, Republic of Korea
  
• 刊物类别：Chemistry and Materials Science
• 刊物主题：Chemistry
  Nuclear Chemistry
  Physical Chemistry
  Nuclear Physics, Heavy Ions and Hadrons
  Diagnostic Radiology
  Inorganic Chemistry
  
• 出版者：Akad茅miai Kiad贸, co-published with Springer Science+Business Media B.V., Formerly Kluwer Academic
• ISSN：1588-2780

文摘

A new process to co-recover uranium and transuranic nuclides from used nuclear fuels was introduced, which was named ‘MKZP’ (Min Ku Zirconium Process), as an alternative of widely known pyroprocessing. Instead of an electrochemical reduction of the pyroprocessing, the MKZP employs Zr and ZrCl₄ as reactants to chemically convert U₃O₈ into UCl₃, which leads to a significant advantage in total number of processes. An addition of fresh zirconium can be minimized by employing cladding hull waste as a source of zirconium tetrachloride through a chlorination process.