2017 Fall Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[2I08-17] SiC

Thu. Sep 14, 2017 2:45 PM - 5:25 PM Room I (C310 - C Block)

Chair:Hirotatsu Kishimoto (Muroran Inst. of Tech.)

4:30 PM - 4:45 PM

[2I15] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(4)Evaluations of severe accident tolerance for SiC

*Yoshinori Yamakoshi1, Kazuki Kirimura1, Shinya Kosaka1, Shinichiro Yamashita2 (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 this time, the material properties, especially melting point of the fuel cladding, are properly modeled, so that the time to core melt is expected to be delayed. 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.