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 degrees C, and its maximum vitrification degree was obtained at 1500 degrees 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 Ce4+ ions are reduced to Ce3+. 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.

Automated summary

Various cerium doped aluminosilicate glasses were prepared by high-temperature melting method, and their structure and properties were studied. It was found that the addition of cerium ions can improve the integrity and hardness of the glass, but excessive cerium ions can destroy the integrity of the network.