Electrochemical recovery of uranium from solid wastes contaminated with uranium using deep eutectic as electrolyte

Ohashi, Yusuke ; Ikeda, Yasuhisa*; Harada, Masayuki*; Asanuma, Noriko*

Approximately 60% of uranium in spent filter aids is found to be dissolved selectively in CCU at 100C. An uncoupled reduction and some oxidation peaks were observed around -0.7 V and 0.4, 0.8 V, respectively. Potential controlled electrolysis of CCU dissolving the spent filter aids was carried out under the constant potential (-1.5 V). As a result, the black deposit were produced. The XPS analyses suggest that the deposits are the uranium compounds mainly containing O and F. We confirmed that CCU is effective media for recovering uranium selectively from spent filter aids by the electrolytic method.