[3B05-08] Vitrification3

[3B06] Evaluation of vitirification and dissolution of simulated high-level radioactive wastes in borosilicate glasses with high-loading capacity

*Tetsuji Yano¹, Takuhiro Miyawaki¹, Shintaro Matsumoto¹, Nobuhiro Matsushita¹, Tetsuo Kishi¹, Yoshiyuki Miura², Norio Kanehira² (1. Tokyo Institute of Technology, 2. Japan Nuclear Fuel Limited)

Keywords:nuclear waste glass, borosilicate glasses, vitirification, waste loading, combinatorial approach

This article presents the evaluation of vitirification behavior of simulated high-level radioactive wastes from the reprocessing of spent nuclear fuels with borosilicate glassesdeveloped for the high-loading of wastes, and dissolution conditions of wastes in the glass. In-situ on-heating process and rate-cooled vitirifcied glasses were examined, and summarized with the results of the combinatorial approach to find glass matrixes with high-loading capacity.