Characteristics of the critical heat flux for downward flow in a vertical tube at low-flow rate and low-pressure conditions

1993 ◽  
Vol 7 (2) ◽  
pp. 159 ◽  
Author(s):  
S.W. Ruan ◽  
G. Bartsch ◽  
S.M. Yang
1991 ◽  
Vol 132 (2) ◽  
pp. 225-237 ◽  
Author(s):  
Soon Heung Chang ◽  
Won-Pil Baek ◽  
Tae Min Bae

2020 ◽  
Vol 28 ◽  
pp. 50-58
Author(s):  
Daniel Vlček ◽  
Ladislav Suk ◽  
Kamil Števanka ◽  
Taron Petrosyan

Steady state flow boiling experiments were conducted on a technically smooth Inconel 625 tube with outer diameter 9.1 mm at inlet pressures 131, 220 and 323 kPa, inlet temperatures 62, 78 and 94 °C and approximately 400, 600 and 1000 kg/(m2.s) mass flow. Water of these parameters was entering into the vertically aligned annulus, where the uniformly heated tube was placed until the critical heat flux (CHF) appeared. The experimental data were compared to estimations of CHF by local PGT tube correlation and Groeneveld’s look-up tables for tubes. The results imply that in the region of low pressure and low mass flux, the differences between calculations and experiments are substantial (more than 50 % of CHF). The calculations further imply that look-up tables and tube correlations should be corrected to the annulus geometry. Here, the Doerffer’s approach was chosen and led to a substantial enhancement of CHF estimation. Yet, a new correlation for the region of low pressure and flow is needed.


Author(s):  
Lei Zhou ◽  
Guangxu Liu ◽  
Yuanfeng Zan ◽  
Xiao Yan

Critical heat flux (CHF) has been widely studied in the past decades because of its importance for nuclear power plant design. But most of the studies are based on flow under normal operating conditions for light water reactors. CHF under low flow and low pressure is of significance when considering operating transients and accidents. In this study, experimental study has been carried out on CHF for low flow rate and low pressure water flow in vertical bilaterally heated annuli. Parameter trends on CHF is discussed and a new predictive correlation was fitted based on the CHF data points. This study is meaningful for concerned nuclear engineering and similar experiment design.


2014 ◽  
Vol 2014.19 (0) ◽  
pp. 167-170
Author(s):  
Takayuki HARADA ◽  
Syota FUJIYOSHI ◽  
Takeyuki AMI ◽  
Hisashi UMEKAWA ◽  
Mamoru OZAWA ◽  
...  

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