We have proposed a new reprocessing process by using ionic liquids (ILs) instead of molten salts of alkali chlorides in pyrochemical process. In the proposed process, spent nuclear fuels are dissolved in ILs by using Cl 2 as an oxidant, and UO 2 2þ and PuO 2 2þ ions in ILs are recovered as UO 2 and PuO 2 by electrochemical reduction. In order to examine applicability of ILs as media for reprocessing, we have studied electrochemical behavior of UO 2 2þ in 1-butyl-3-methylimidazolium chloride (BMICl), 1-butyl-3-methylimidazolium tetrafluoroborate (BMIBF 4 ), and 1-butyl-3-methylimidazolium nonafluorobutanesulfonate (BMINfO). Electrochemical properties of uranyl chloride dissolved into ILs were examined by cyclic voltammetry. In BMICl, an almost reversible redox couple was observed, and the formal potential and the diffusion coefficient were evaluated as À0:758 V vs. Ag/AgCl and 4:8 Â 10 À8 cm 2 Ás À1 , respectively. On the other hand, the electrochemical reactions of UO 2 2þ in BMIBF 4 and BMINfO were irreversible. In BMINfO, some reduction peaks and one sharp oxidation peak were observed in the range of À0:6$À0:2 V and around 0.85 V vs. Ag/AgCl, respectively. The reduction and oxidation peaks were assigned to multi step reduction of UO 2 2þ to U(IV) via U(V) and/or direct reduction of UO 2 2þ to U(IV), and the oxidative dissolution of the resulting U(IV) compounds, respectively. The electrochemical reduction of UO 2 2þ in BMINfO at À1:0 V vs. Ag/AgCl produced the deposits on a carbon electrode as a cathode. Analyses of the deposits with the scanning electron microscope and the energy dispersive X-ray spectrometer indicated that the deposits are compounds containing uranium, oxygen, and chlorine. As a result, it is expected that the UO 2 2þ in IL can be recovered electrolytically as uranium compounds such as UO 2 and uranium oxychlorides.