2023 Annual Meeting

Presentation information

Oral presentation

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

[1I04-07] Vitrification 2

Mon. Mar 13, 2023 10:50 AM - 11:55 AM Room I (13 Bildg.1F 1313)

Chair:Tetsuji Yano(Tokyo Tech)

10:50 AM - 11:05 AM

[1I04] MoO3 solubility and durability of simulated radioactive waste glass containing V2O5

*Minako Nagata1, Toshiaki Ohira1, Toru Sugawara1 (1. Akita University, Graduate School of Engineering Science)

Keywords:High-level radioactive waste, Vitrified waste, MoO3 solubility

The molybdenum phase is a problem in the high-level radioactive waste because it decreases chemical durability of the glass. In addition, waste glass dissolves when exposed to water, and the glass durability is different depending on its composition. Both high MoO3 solubility and durability are required for vitrified waste. In this study, we investigate the effect of V2O5 addition on MoO3 solubility and durability of glass. Phase equilibrium experiments were performed at 1200℃ for a glass of the current composition and a glass of the composition with added V2O5, and it was found that the addition of V2O5 increased MoO3 solubility. The glass with increased MoO3 solubility will be tested for durability.