2023 Annual Meeting

Presentation information

Oral presentation

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

[1I12-16] Vitrification 4

Mon. Mar 13, 2023 3:50 PM - 5:10 PM Room I (13 Bildg.1F 1313)

Chair:Ryo Hamada(RWMC)

4:05 PM - 4:20 PM

[1I13] Basic Research Programs of Vitrification Technology for Waste Volume Reduction

(112)Evaluation of Transportability and Chemical Reactivity of Briquettes for New Feeding Process of Vitrification of High-Level Radioactive Waste Derived from Reprocessing of High-Burnup and MOX Spent Fuels

*Tetsuji Yano1, Mizuto Saito1, Hiroyuki Kadono1, Tetsuo Kishi1, Ryou Souma2, Kohei Oowaku2, Takeshi Tsukada1, Norio Kanehira2 (1. Tokyo Tech, 2. JNFL)

Keywords:Vitrification of nuclear wastes, briquettes, high-burnup spent fuels, MOX spent fuels

In order to realize homogeneous vitrification of HLW from high-burnup and/or MOX spent fuels, it is important to develop new feeding form of glass materials with stable transportability in melting operation and attain high reactivity with HLW. In this study, the properties required for suitable glass-powder briquettes were evaluated: transportability, which means high enough yield stress to maintain its shape until feeding, and appropriately high chemical reactivity, which allows the collapse by mixing with HLW to form homogeneous slurry.