2020 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 504-3 Fuel Reprocessing

[1F07-10] Boiling and Drying Accident of HLLW, and Pyroprocessing

Wed. Sep 16, 2020 2:45 PM - 4:00 PM Room F (Zoom room 6)

Chair:Kayo Sawada(Nagoya Univ.)

3:30 PM - 3:45 PM

[1F10] Evaluation of salt waste form reduction by modification of pyroprocessing

*Koichi Uozumi1, Kensuke Kinoshita1, Masatoshi Iizuka1 (1. CRIEPI)

Keywords:Pyroprocessing, Spent salt treatment, Zeolite column, Equilibrium absorption amount, Salt waste form

Effect of modification of pyroprocessing for treating 40t-HM of spent metallic fuel annually was evaluated quantitatively as the number of generated salt waste forms. It was estimated that advance recovery of 90% of rare-earth fission products onto silicone electrode prior to the zeolite column treatment followed by making use of the rare-earth silicon alloy as the glass content of salt waste form, i.e., glass-bonded sodalite, would reduce the amount of salt waste forms by 22%.