Presentation Information
[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.