2022 Annual Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[1I17-18] Nitride Fuel/HTGR Fuel

Wed. Mar 16, 2022 4:55 PM - 5:30 PM Room I

Chair: Mutsumi Hirai (TEPCO HD)

5:10 PM - 5:25 PM

[1I18] Study on SiC compact oxidation under HTGR air ingress accident

(1)SiC oxidation experiment

*Yosuke Nishimura1 (1. University of Tokyo )

Keywords:Gen-4 reactors, HTGR, SiC oxidation, Thermogravimetric, THYTAN code simulation

As the Gen-4 reactor, they have been paying great attention to High Temperature Gas-cooled Reactor. We have to improve the safety features to make HTGR in practical use. In this study, we assume the air ingress accident which is following the guillotine break of primary pipes and LOCA. To control the severe oxidation in the core, it is recommended that we should replace graphite fuel compact for SiC. We tested many SiC samples in thermogravimetric furnace, then oxidation rates and activation energy are collected in wide range of presumable temperatures and oxygen concentrations. In conclusion, we show the superiority of SiC fuel compact and suggest further improvements.