2018 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 405-1 Radioactive Waste Management

[2O10-13] Vitrification 4

Tue. Mar 27, 2018 2:45 PM - 3:45 PM Room O (M3-212 -M3 Building)

Chair: Takeshi Tsukada (CRIEPI)

3:30 PM - 3:45 PM

[2O13] Effects of average bonding number and non-bridging oxygen content on the MoO3 solubility and chemical durability of borosilicate glasses

*Ryo Souma1, Katsushige Komatsu1, Shigeru Yamamoto1, Akihiro Yamada1, Jun Matsuoka1, Kouhei Oowaku2, Norio Kanehira2 (1. The University of Shiga Prefecture, 2. Japan Nuclear Fuel Limited)

Keywords:Borosilicate glass, MoO3 solubility, Chemical durability, Average bonding number, Non-bridging oxygen

In order to develop high-level radioactive waste glass with high-loading capacity, effects of average bonding number of glass network and non-bridging oxygen content on the MoO3 solubility and on the chemical durability were investigated for simplified compositions of high-level radioactive waste glass. Average bonding number is found to be the dominant factor.