In this work, we investigated the
dissolution behavior of U3O8 and UO3 in the LiCl–KCl molten
salt using 2.9 or 9.5 wt % AlCl3 as a chlorination agent
under an argon atmosphere at 450 °C. Ultraviolet–visible/Ultraviolet–visible–near
infrared absorption spectroscopy (UV–vis/UV–vis–NIR),
fluorescence emission spectroscopy (FL), X-ray absorption fine structure
(XAFS), and electrochemical techniques were used to systematically
study the chemical species and the transformation of the dissolved
products of U3O8 and UO3. It was
found that with the aid of AlCl3, the initial products
of U3O8 and UO3 dissolution were
different. The initial products of U3O8 were
UO2Cl4
2– and UCl6
2–, while the initial product of UO3 dissolution was UO2Cl4
2–. Interestingly, regardless of U3O8 or UO3, with the increase of AlCl3 content, the UO2Cl4
2– in their dissolved products
showed a tendency to transform into UCl6
2–. In addition, UCl4 was produced by mixing 0.05 g of U3O8/UO3 powders with 10 times the amount
of AlCl3 and heating them at 300 °C for 2 h. This
work focuses on the pyrochemical reprocessing of spent oxide fuels,
deepening the understanding of the dissolution of uranium oxides in
higher oxidation states, and enriching the knowledge of uranium in
the transformation of chemical species in molten salts.