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

Abstract

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.

Keywords

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