2020年春の年会

講演情報

一般セッション

III. 核分裂工学 » 304-1 伝熱・流動(エネルギー変換・輸送・貯蔵を含む)

[3G01-06] 限界熱流束

2020年3月18日(水) 10:15 〜 11:55 G会場 (共通講義棟 M棟2F M-21)

座長:西田 浩二(INSS)

11:00 〜 11:15

[3G04] Preliminary research on a new model to predict CHF

*Kai Wang1, Koji Okamoto1, Nejdet Erkan1 (1. Univ. of Tokyo)

キーワード:Critical heat flux, Nucleate boiling, Bubble behavior, Monte Carlo, Nucleation site density

Due to the important role critical heat flux (CHF) plays in the boiling field, it is of great significance to study CHF, especially the mechanism of CHF in the nucleate boiling. In this study, a new numerical model to predict CHF was proposed base on the Monte Carlo method. This model can take into account of the bubble generation, bubble growth, bubble sliding and bubble departure. The results showed good agreement with the experimental results. Further works are needed to apply this model to a wider range of experiments and other working conditions.