Recovery of uranium from (U,Gd)O2 nuclear fuel scrap using dissolution and precipitation in carbonate media

This work studied a process to recover uranium from contaminated (U,Gd)O2 scraps generated from nuclear fuel fabrication processes by using the dissolution of (U,Gd)O2 scraps in a carbonate with H2O2 and the precipitation of the dissolved uranium as UO4. The dissolution characteristics of uranium, Gd, and impurity metal oxides were tested, and the behaviors of UO4 precipitation and Gd solubility were evaluated with changes of the pH of the solution. A little Gd was entrained in the UO4 precipitate to contaminate the uranium precipitate. Below a pH of 3, the uranium dissolved in the form of uranyl peroxo-carbonato complex ions in the carbonate solution was precipitated as UO4 with a high precipitation yield, and the Gd had a very high solubility. Using these characteristics, the Gd-contaminated UO4 could be purified using dissolution in a 1-M HNO3 solution with heating and re-precipitation upon addition of H2O2 to the solution. Finally, an environmentally friendly and economical process to recover pure uranium from contaminated (U,Gd)O2 scraps was suggested.