[1I01-07] 熱流動数値解析

[1I05] Preliminary CFD simulation of critical heat flux for subcooled water flow boiling in vertical heated tubes

*KAI WANG¹, Nejdet Erkan¹, Koji Okamoto² (1. Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-8654, Japan, 2. Nuclear Professional School, School of Engineering, The University of Tokyo, 2-22 Shirakata, Tokai-mura, Ibaraki, 319-1188, Japan)

キーワード：Subcooled boiling, critical heat flux, Critical heat flux model

Eulerian two-fluid model coupled with an extended RPI wall boiling model was applied to simulate the departure
from nucleate boiling (DNB) under ultra-high critical Heat Flux (CHF) in vertical heated tubes by using CFD.