Feasibility studies on electrochemical recovery of uranium from solid wastes contaminated with uranium using 1-butyl-3-methylimidazorium chloride as an electrolyte

被引:20
作者
Ohashi, Yusuke [1 ]
Harada, Masayuki [2 ]
Asanuma, Noriko [3 ]
Ikeda, Yasuhisa [2 ]
机构
[1] Japan Atom Energy Agcy, Ningyo Toge Environm Engn Ctr, Kagamino, Okayama 7080698, Japan
[2] Tokyo Inst Technol, Nucl Reactors Res Lab, Meguro Ku, Tokyo 1528550, Japan
[3] Tokai Univ, Sch Engn, Dept Nucl Engn, Hiratsuka, Kanagawa 2591292, Japan
关键词
IONIC LIQUIDS; ACTINIDE; ELECTRODEPOSITION; DECONTAMINATION; COORDINATION; SEPARATION; EXTRACTION; COMPLEXES; CHEMISTRY; BEHAVIOR;
D O I
10.1016/j.jnucmat.2015.04.024
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In order to examine feasibility of the electrochemical deposition method for recovering uranium from the solid wastes contaminated with uranium using ionic liquid as electrolyte, we have studied the electrochemical behavior of each solution prepared by soaking the spent NaF adsorbents and the steel waste contaminated with uranium in BMICI (1-butyl-3-methyl- imidazolium chloride). The uranyl(VI) species in BMICI solutions were found to be reduced to U(V) irreversibly around -0.8 to -1.3 V vs. Ag/AgCl. The resulting U(V) species is followed by disproportionation to U(VI) and U(IV). Based on the electrochemical data, we have performed potential controlled electrolysis of each solution prepared by soaking the spent NaF adsorbents and steel wastes in BMICI at -1.5 V vs. Ag/AgCl. Black deposit was obtained, and their composition analyses suggest that the deposit is the mixtures of U(IV) and U(VI) compounds containing O, F, Cl, and N elements. From the present study, it is expected that the solid wastes contaminated with uranium can be decontaminated by treating them in BMICI and the dissolved uranium species are recovered electrolytically. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码:119 / 127
页数:9
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