scholarly journals CRITICAL HEAT FLUX ENHANCEMENT IN FLOW BOILING OF Al2O3AND SiC NANOFLUIDS UNDER LOW PRESSURE AND LOW FLOW CONDITIONS

2012 ◽  
Vol 44 (4) ◽  
pp. 429-436 ◽  
Author(s):  
Seung-Won Lee ◽  
Seong-Dae Park ◽  
Sa-Rah Kang ◽  
Seong-Man Kim ◽  
Han Seo ◽  
...  
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Flow Boiling ◽  
Low Pressure ◽  
Low Flow ◽  
Flow Conditions ◽  
Flux Enhancement

scholarly journals EXPERIMENTAL INVESTIGATION OF CRITICAL HEAT FLUX IN ANNULUS AT LOW PRESSURE AND LOW FLOW PARAMETERS

2020 ◽  
Vol 28 ◽  
pp. 50-58
Author(s):  
Daniel Vlček ◽  
Ladislav Suk ◽  
Kamil Števanka ◽  
Taron Petrosyan
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Flow Boiling ◽  
Low Pressure ◽  
Low Flow ◽  
Inconel 625 ◽  
Outer Diameter ◽  
Flow Parameters ◽  
Low Mass ◽  
Vertically Aligned

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.

A New Mechanistic Critical Heat Flux Model at Low-Pressure and Low-Flow Conditions

1998 ◽  
Vol 124 (3) ◽  
pp. 243-254 ◽  
Author(s):  
Kuan-Chywan Tu ◽  
Chien-Hsiung Lee ◽  
Shih-Jen Wang ◽  
Bau-Shei Pei
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Low Pressure ◽  
Low Flow ◽  
Flow Conditions ◽  
Flux Model ◽  
Heat Flux Model

Critical heat flux of water in vertical round tubes at low pressure and low flow conditions

2000 ◽  
Vol 199 (1-2) ◽  
pp. 49-73 ◽  
Author(s):  
Hong Chae Kim ◽  
Won-Pil Baek ◽  
Soon Heung Chang
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Low Pressure ◽  
Low Flow ◽  
Flow Conditions

A study of critical heat flux for low flow of water in vertical round tubes under low pressure

1991 ◽  
Vol 132 (2) ◽  
pp. 225-237 ◽  
Author(s):  
Soon Heung Chang ◽  
Won-Pil Baek ◽  
Tae Min Bae
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Low Pressure ◽  
Low Flow

Critical heat flux enhancement on a downward face using porous honeycomb plate in saturated flow boiling

2017 ◽  
Vol 109 ◽  
pp. 454-461 ◽  
Author(s):  
Laishun Wang ◽  
Abdul R. Khan ◽  
Nejdet Erkan ◽  
Haiguang Gong ◽  
Koji Okamoto
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Flow Boiling ◽  
Saturated Flow ◽  
Flux Enhancement

Effect of Flow Orientation on Critical Heat Flux in Subcooled Flow Boiling

Volume 3 ◽  
2004 ◽  
Author(s):  
Jason S. Bower ◽  
James F. Klausner
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Heat Exchangers ◽  
Flow Boiling ◽  
Bulk Flow ◽  
Flow Conditions ◽  
Convective Velocity ◽  
Subcooled Flow Boiling ◽  
Subcooled Flow ◽  
Significant Interest

Recent work has demonstrated that as the bulk convective velocity in subcooled nucleate flow boiling increases, the heat transfer tends to become independent of flow orientation with respect to gravity. There is significant interest in developing heat exchangers for next generation spacecraft that operate in the gravity-independent flow boiling regime. In order to develop such heat exchangers it is important to understand the effect of gravity on the critical heat flux and to determine whether a gravity on the critical heat flux and to determine whether a gravity-independent flow boiling critical heat flux regime exists. This work describes subcooled flow boiling experiments where the critical heat flux is measured over a range of flow orientations with respect to gravity: 0°, 45°, 90°, 135°, 180°, 225°, 270°, and 315°. It has been found that at low bulk flow velocities there is a large variation of critical heat flux with different flow orientations. At large convective velocities, the variation of critical heat flux with different flow orientations is significantly diminished. It appears that with further increases in bulk flow velocity, a gravity-independent critical heat flux regime exists, although the current experimental facility was not capable of operating at those flow conditions.

An Experimental Study on the Critical Heat Flux for Low Flow of Water in Bilaterally Heated Vertical Annuli Under Low Pressure Conditions

2014 ◽  
Author(s):  
Lei Zhou ◽  
Guangxu Liu ◽  
Yuanfeng Zan ◽  
Xiao Yan
Keyword(s):  
Experimental Study ◽  
Heat Flux ◽  
Critical Heat Flux ◽  
Nuclear Power ◽  
Low Pressure ◽  
Operating Conditions ◽  
Low Flow ◽  
Plant Design ◽  
Water Reactors ◽  
Vertical Annuli

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.

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