[2D03-05] Next-Gen. Materials (SiC)

[2D05] Severe accident analysis for core fuel with SiC cladding

(3)Study of cooling effect of circulation steam flow in RPV by nuclear thermal hydraulics analysis code TRACT^TM

*Kenya Takiwaki¹, Yutaka Takeuchi¹, Hideki Horie¹, Kazuo Kakiuchi¹, Hisaki Sato¹ (1. TOSHIBA ENERGY SYSTEMS & SOLUTIONS CORPORATION)

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

A water-SiC oxidation reaction model was incorporated to TRACT and applied to claddings. As a result,it was found that severe core damage could possibly be avoided. In addition, cooling effect of circulation steam flow in RPV was evaluated.