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.)

3:00 PM - 3:15 PM

[2I09] R&D for introducing silicon carbide materials to safety improvement of BWRs core

(2)Plant transient analysis with SiC clad fuel

*Yutaka Takeuchi1, Kazuo Kakiuchi1, Sato Hisaki1, Noriko Shirasu2, Hiroaki Saito2, Shinichiro Yamashita2 (1. Toshiba Corporation, 2. JAEA)

Keywords:Accident Tolerant Fuel , SiC, DBA, TRAC, FEMAXI

We have been developed a thermal-hydraulic and mechanical coupling evaluation method for BWR plant transient and safety analysis using SiC clad fuel which is a candidate for ATF. In typical DBA conditions, we assumed that there is not so much difference in the mechanical behavior between SiC clad fuel and Zry clad fuel.