2017 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 401-2 Nuclear Fuel and the Irradiation Behavior

[1I13-17] characteristics of fuel cladding

Mon. Mar 27, 2017 4:25 PM - 5:50 PM Room I (16-304 Building No.16)

Chair: Ken Kurosaki (Osaka Univ.)

4:40 PM - 4:55 PM

[1I14] The evaluation on the applicability of SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(2)Evaluations of severe accident tolerance for SiC

*Yoshinori Yamakoshi1, Manabu Miyata1, Kazuki Kirimura1, Masatsugu Mizokami1, Shinya Kosaka1, Shinichiro Yamashita2, Fumihisa Nagase2 (1. Mitsubishi Heavy Industries, ltd., 2. Japan Atomic Energy Agency)

Keywords:accident tolerant fuel, SiC composite, fuel cladding, PWR, severe accident

Evaluations were performed for severe accident tolerance when SiC composite fuel is applied as an accident tolerant fuel using severe accident analysis code. Intended accident sequences are large pipe break LOCA and SBO both of which lead to core melt. In both accident sequences, the timing of core melt and relocation of molten core is delayed in comparison with conventional fuel, which showed a possibility of core injection recovery. It was also confirmed that the amount of hydrogen generated is significantly reduced in comparison with conventional fuel.