Characteristics of cerium doped aluminosilicate glass as simulated radioactive waste forms: Effect on structures and properties

Various cerium doped aluminosilicate glass was prepared by a high-temperature melting method using natural granite material as the only origin of the glass substrate . TG-DSC was used to understand the changes of this aluminosilicate material in the melting process. The structure of the glass was systematically studied by X-ray diffraction, scanning electron microscopy, infrared spectroscopy, X-ray photoelectron spectra. This type of aluminosilicate material begins to vitrify at about 1000 °C, and its maximum vitrification degree was obtained at 1500 °C. The structure of the glassy waste forms prepared at this temperature is mainly composed of Q 3 and Q 4 structural units. With the addition of cerium ions, the proportion can even reach 82%. Such good glass integrity makes this type of aluminosilicate glass density and hardness up to 2.89 g cm −3 and 7.80 GPa, respectively. However, the addition of excessive cerium ions destroys the integrity of the network, resulting in that the glass can only carry 17  wt % cerium ions at most. At this point, 55.93% of Ce 4+ ions are reduced to Ce 3+ . In the meantime, cerium ions are evenly distributed in the glass network. This study provides a strategy for the treatment of radioactive waste with similar properties with cerium ions.