2023 Fall Meeting

Presentation information

Oral presentation

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

[1E10-14] Vitrification 2

Wed. Sep 6, 2023 3:30 PM - 4:45 PM Room E (Okuma Machine Tool Eng. Bildg. 1F Okuma Hall)

Chair:Tatsumi Arima(Kyushu Univ.)

4:15 PM - 4:30 PM

[1E13] Basic Research Programs of Vitrification Technology for Waste Volume Reduction

(119)Aapplicability evaluation of pretreated HLW to glass melter for diversity of HLW

*KUNIHIKO NAKANO1, ATSUMI MIYAJIMA1, HARUKA TADA1, TOSHIRO ONIKI1 (1. IHI)

Keywords:MOX spent fuel waste, vitrification technology

Vitrification technology for MOX spent fuel waste has been developed. Pretreatment technology for concentrating the waste has been studied for applying the glass melting furnace to treat MOX spent fuel waste. Operating conditions of the glass melting furnace may differ between the pretreated waste and the non-pretreated one. Then, melting tests using the small glass melting furnace were carried out for the pretreated waste and the non-pretreated one to understand the cold cap condition, the off-gas transfer characteristics, and YP generation. We evaluated the applicability of the pretreated waste to the glass melting furnace.

Abstract password authentication.
Password is required to view the abstract. Please enter a password to authenticate.

Password