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J. Korean Ceram. Soc. > Volume 39(2); 2002 > Article
Journal of the Korean Ceramic Society 2002;39(2): 204.
doi: https://doi.org/10.4191/kcers.2002.39.2.204
핵연료분말 제조공정에서 발생된 여액으로부터 우라늄 회수 및 회수된 우라늄 화합물의 열분해 특성
정경채, 정지영, 김병호, 김태준, 최종현
한국원자력연구소 칼리머기술개발팀
Uranium Recovery from Nuclear Fuel Powder Conversion Plant Filtrate and its Thermal Decomposition Characteristics
Kyung-Chai Jeong, Ji-Young Jeong, Byung-Ho Kim, Tae-Joon Kim, Jong-Hyeun Choi
KALIMER Technology Development Team, Korea Atomic Energy Research Institute
In this study, $UO_4{cdot}2NH_4F$, the precipitates which has low solubility, was obtained by chemical precipitation method to recover and reuse the trace uranium from the liquid waste producing in AUC process and for this compound it was characterized by means of chemical analysis, TG-DTA, XRD and FT-IR analyses. This compound was analyzed as $UO_4{cdot}2NH_4F$ and shape of this precipitate was hexagonal type, having the size of 2∼3 ${mu}m$. Also, the intermediates were obtained as $UO_4F,;UO_4,;UO_3,;and;U_3O_8$ by the thermal decomposition over the temperature of 220, 310, 515 and 640$^{circ}C$, respectively. It is concluded that under the condition of a constant heating rate of 5$^{circ}C$/min in air atmosphere range of between room temperature and 800$^{circ}C$, thermal decomposition reaction mechanism of $UO_4{cdot}2NH_4F$ is as follow; $UO_4{cdot}2NH_4F{rightarrow}UO_4F{rightarrow}UO_4{rightarrow}UO_3{rightarrow}U_3O_8$.
Key words: Nuclear fuel, AUC, $UO_4$, Thermal decomposition, Conversion
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