Uranyl Peroxide Compound Preparation from the Filtrate for Nuclear Fuel Powder Production Process

핵연료분말 제조공정 여액으로부터 Uranyl-peroxide 화합물의 제조

  • Jeong, Kyung-Chai (Advanced Research Groop, Korea Atomic Energy Research Institute) ;
  • Kim, Tae-Joon (Advanced Research Groop, Korea Atomic Energy Research Institute) ;
  • Choi, Jong-Hyun (Advanced Research Groop, Korea Atomic Energy Research Institute) ;
  • Park, Jin-Ho (Advanced Research Groop, Korea Atomic Energy Research Institute) ;
  • Hwang, Seong-Tae (Advanced Research Groop, Korea Atomic Energy Research Institute)
  • Received : 1997.01.17
  • Accepted : 1997.05.26
  • Published : 1997.06.10


Uranyl-peroxide compound was prepared by the reaction of excess hydrogen peroxide solution and trace uranium in filtrate from nuclear fuel conversion plant. The $CO_3{^{2-}}$ in filtrate was removed first by heating more than $98^{\circ}C$, because uranyl-peroxide compound could not be precipitated by $CO_3{^{2-}}$ remaining in filtrate. The optimum condition for uranyl-peroxide compound was ageing for 1 hr after controling the pH with $NH_3$ gas and adding the excess $H_2O_2$ of 10ml/lit.-filtrate. Uranium concentration in the filtrate was appeared to 3 ppm after the precipitation of uranyl-peroxide compound, and the chemical composition of this compound was analyzed to $UO_4{\cdot}2NH_4F$ with FT-IR, X-ray diffractometry, TG and chemical analysis. Also, this fine particle, about $1{\sim}2{\mu}m$, could be grown up to $4{\mu}m$ at pH 9.5 and $60^{\circ}C$. The separation efficiency of precipitate from mother liquor was increased with increase of pH and reaction temperature. Otherwise, the crystal form of this particle showed octahedral by SEM and XRD, and $U_3O_8$ powder was obtained by thermal decomposition at $650^{\circ}C$ in air atmosphere.



  1. Trans. Am. Nucl. Soc. v.31 Technology of UO₂Fabriction by the AUC Process H. Assmann;M. Becker
  2. Trans. Am. Nucl. Soc. v.31 Characteristics of UO₂Powder and Pellets of LWR Fuel E. Brandau;W. Dorr
  3. Industrial Crystallization S. J. Jancic;P. A. M. Grootscholton
  4. Industrial Crystallization from Solution J. Nyvlt
  5. Crystallization(3rd ed.) J. W. Mullin
  6. 공업화학 v.8 우라늄 정광의 용해/정제 및 핵연료 분말 가공공정에서 발생된 폐액의 처리에 관한 연구 정경채(외)
  7. 한국에너지연구소, KAERI/RR-240/88 AUC 제조 및 그의 액체 페기물 처리에 관한 연구, $UF_6$의 재전환 단위 공정의 화학특성 연구 장인순(외)
  8. 재변환공정 부산물인 $NH_4F$의 재사용 가능성에 관한 연구 박진호(외)
  9. Israel Program for Scientific Translations Complex Compounds of Uranium I. I. Chernayaev
  10. Enviornmental Sci. & Tech v.8 Treatment of Aqueous Effluent from$UF_6$$(NH_4)_4[UO_2(CO_3)_3]$ → UO₂Conversion H. Dokuzoguz;H. M. Muller
  11. Basic Techniques and Experiments in Infrared and FT-IR Spectroscopy L. Chia;S. Ricketts
  12. Infrared and Raman Spectra of Inorganic and Coodination Compounds(3rd ed.) K. Nakamoto
  13. J. Inorg. Nucl. Chem. v.36 Preparation, Characterization and X-ray Powder Diffraction Data of the Compound UO₄· 2NH₃· 2HF H. G. Bachmann(et al)
  14. International Series of Monographs on Analytical Chemistry v.18 Kinetics of Precipitation A. E. Nielsen
  15. ICTA 80 Birkhaeuser Thermal Analysis L. Haelldahl;O. T. Soerensen
  16. International Centre for Diffraction Data JCPDS Powder Diffraction File, Inorganic Phases R. Jenkins;W. F. McClune(et al.)
  17. J. Nucl. Mater. v.138 Thermal Analysis Studies of the Reactions Occurring during the Decomposition of Ammonium Uranyl Carbonate in Different Atomspheres L. Halldahal;M. Nygren