2020 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 304-1 Thermal Hydraulics, Energy Conversion, Energy Transfer, Energy Storage

[3G01-06] Critical Heat Flux

Wed. Mar 18, 2020 10:15 AM - 11:55 AM Room G (Lecture Bildg. M 2F M-21)

Chair:Koji Nishida(INSS)

11:00 AM - 11:15 AM

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

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

Keywords: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.