Pre-treatment for the separation of actinide and noble metals from high-level radioactive waste to improve the vitrification process and performance

The porous compound generated from the reaction of 4-[tris(4-carboxyphenyl)methyl]benzoic acid (H4MTB) with actinide Th in simulated high-level radioactive waste can adsorb Ru, which can separate Th and Ru by more than 68.1 and 37.3%, respectively, in simulated high-level radioactive waste. The waste liquid before and after separation was vitrified with borosilicate glass and iron phosphate glass. The composition and morphology of the glasses were characterized by XRD, SEM and ICP‒OES, and the product consistency test was used to measure the chemical durability of the glasses. The chemical stability and waste loading of the glasses after the separation of actinide and noble metal elements was significantly improved. This work is of great significance for the recovery and utilization of actinide and noble metal elements in high-level radioactive waste and the optimization of the vitrification process of radioactive waste.