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)

4:20 PM - 4:35 PM

[1I14] Basic Research Programs of Vitrification Technology for Waste Volume Reduction

(113)廃液多様化に対応したガラス溶融炉の運転性への影響検討

*Kunihiko Nakano1, Atsumi Miyajima1, Haruka Tada1, Toshiro Oniki1 (1. IHI)

Keywords:high-burnup spent fuel waste, MOX spent fuel waste, Vitrification technology

Vitrification technologies for high-burnup spent fuel waste and MOX one have been developed. The melting tests using the tubular furnace were carried out for the purpose of basic investigation on the operability of the melting furnace and high-burnup fuel waste was found to produce vitrified waste at the same rate for standard spent fuel waste. In addition, regarding the pretreatment technology of the waste, which is being studied as the method of concentrating MOX spent fuel waste, the melting tests using the tubular furnace ware carried out for the investigation of the influence of the waste supply form on the operability of the melting furnace. The difference on the operability of the melting furnace was evaluated.