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.)

3:15 PM - 3:30 PM

[2I10] Severe accident analysis for core fuel with SiC cladding

(1)Evaluation by severe accident analysis code MAAP

*Hideki Horie1, Yutaka Takeuchi1, Fumie Sebe1, Kenya Takiwaki1, Kazuo Kakiuchi1, Hisaki Sato1 (1. Toshiba Corporation)

Keywords:SiC cladding, SiC channel box, SiC-water oxidation reaction, Amount of hydrogen generation

A new water-SiC oxidation reaction model was incorporated to MAAP, and applied to Zry claddings, Zry channel boxes, and SUS structures in core. As a result, in the case of applying to the new model to the above three parts, an less amount of hydrogen was generated than the traditional model.