Immobilize Simulated Am-Np-RE-Pu Product Waste from Trialkyl Phosphine Oxide process in Natural Granite-Based Aluminum Silicate Glass or Glass-Ceramic

Abstract

The immobilization of nuclear waste can effectively reduce the possible harm of radioactive waste to human survival. In this study, preferred natural granite was used to prepare aluminosilicate glass or glass-ceramic for immobilizing simulated Am-Np-RE-Pu product waste from trialkyl phosphine oxide (TRPO) process. The phase evolution, microstructure, physical and chemical stability of the waste forms were researched. The results indicated that the waste cations mainly incorporated by the glass network or stable oxyapatite crystals. The lattice binding force and the interface effect inhibited the waste cations from escaping out of the glassy bulk. After 42d leaching, the normalized leaching rates of Ce, Nd, and La in glass-ceramic reached ~10-7 g m-2 d-1, ~10-8 g m-2 d-1, ~10-7 g m-2 d-1, respectively. This study demonstrated that the preferred natural granite showed considerable potential in effectively immobilize high-level radioactive waste rich in rare earth elements.