Stoichiometric relation for extraction of uranium from UO2 powder using TBP complex with HNO3 and H2O in supercritical CO2

被引:22
|
作者
Sawada, K [1 ]
Uruga, K
Koyama, T
Shimada, T
Mori, Y
Enokida, Y
Yamamoto, I
机构
[1] Nagoya Univ, Chikusa Ku, Nagoya, Aichi 4648603, Japan
[2] Japan Nucl Cycle Dev Inst, Ibaraki 3191194, Japan
[3] Mitsubishi Heavy Inds Ltd, Nucl Energy Syst Engn Ctr, Nishi Ku, Yokohama, Kanagawa 2208401, Japan
关键词
supercritical carbon dioxide; uranium dioxide; TBP complex with HNO3 and H2O; stoichiometry; dissolution;
D O I
10.3327/jnst.42.301
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The stoichiometry of UO2 dissolution with a tri-n-butylphosphate (TBP) complex with HNO3 and H2O was experimentally determined in supercritical carbon dioxide (SF-CO2) at 25 MPa, 323 K to estimate the required amount of the complex for a process design calculation. The molecular ratio of TBP:HNO3:H2O was determined as 1.0:1.8:0.6 when prepared as an organic phase after vigorous mixing of concentrated HNO3 and TBP. The HNO3 consumption was approximately 4 times the amount of extracted uranium. In designing a supercritical fluid extraction process, the following equation can be used to describe the overall dissolution of UO2 using the TBP complex with HNO3 and H2O in SF-CO2: UO2 + 4HNO(3) + 2TBP → UO2(NO3)(2) (.) 2TBP + 2NO(2) + 2H(2)O.
引用
收藏
页码:301 / 304
页数:4
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