[3A01-04] Vitrification 5

[3A01] Electrochemical reduction of simulated vitrified waste glass in molten salt for separation and recovery of LLFPs

*Yumi Katasho¹, Kouji Yasuda^2,3, Toshiyuki Nohira¹ (1. Institute of Advanced Energy, Kyoto Univ., 2. Agency for Health, Safety and Environment, Kyoto Univ., 3. Graduate School of Energy Science, Kyoto Univ. )

Keywords:molten salt electrolysis, vitrified waste, LLFPs

Geological disposal of radioactive wastes produced by nuclear power generation has a problem for site selection in Japan. Therefore, a new disposal process has been proposed, where the LLFPs are separated and recovered from vitrified wastes and converted to stable nuclide or short-lived nuclide by transmutation. We have been studying the reduction method for SiO₂ to produce Si by molten salt electrolysis. This method can destroy the Si-O network structure of vitrified wastes and recover LLFPs. In the present study, the glass simulated for vitrified wastes was reduced in molten CaCl₂ at 1103 K. The reduced products and molten salts were analyzed to clarify the behaviors of LLFPs (Se, Zr, Cs, Pd) during the electrochemical reduction.