2019 Annual Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 505-1  Radioactive Waste Management

[3B05-08] Vitrification3

Fri. Mar 22, 2019 10:55 AM - 12:00 PM Room B (Common Education Bildg. 2 1F No.10)

Chair:Jun Onoe(Nagoya Univ.)

11:10 AM - 11:25 AM

[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.