[2I08-17] SiC

[2I11] Severe accident analysis for core fuel with SiC cladding

(2)Evaluation by nuclear thermal hydraulics analysis code TRACT^TM

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

Keywords:SiC cladding, SiC-water oxidation reaction, Fuel cladding temperature

1F-3 accident simulation by plant transient analysis code TRACT with SiC oxidation reaction model was performed. As a result, it was found that severe core damage could possibly be avoided when SiC cladding was applied. In addition, analysis results and models of TRACT were compared with severe accident analysis code MAAP.