Experimental Study of Subcooled Flow Boiling Critical Heat Flux of Water Under Steady-State and Flow-Transient Conditions at Lower Pressure  

作　　者：CHEN Yu-zhou, YANG Chun-sheng, MAO Yu-long 

出　　处：《Annual Report of China Institute of Atomic Energy》2005年第1期154-154,共1页中国原子能科学研究院年报（英文版）

摘　　要：A subcooled boiling CHF experiment was carried out in tube of Di = 15.9 mm under steady-state and flow reduction transient conditions, covering the ranges of pressure of p 0.2-1.7 MPa, velocity of v = 2.1-13.5 m/s, exit subcooling of △Ts =0-110 K and critical heat flux of qCHF =（3.2-13.5）×10^6W/m^2.

关 键 词：反应堆 临界热流密度实验 低压欠热沸腾水 稳态流动 瞬态流动 

分 类 号：TL334[核科学技术—核技术及应用]