CRITICAL HEAT FLUX AND PRESSURE DROP UNDER FORCED CONVECTION BOILING OF SUBCOOLED WATER: EXPERIMENTAL DATA

1994 ◽  
Author(s):  
Yuri Albertovich Zeigarnik
Keyword(s):  
Experimental Data ◽  
Heat Flux ◽  
Pressure Drop ◽  
Forced Convection ◽  
Critical Heat Flux ◽  
Subcooled Water

Critical Heat Flux of Steady Boiling for Subcooled Water Jet Impingement on the Flat Stagnation Zone

2004 ◽  
Vol 126 (2) ◽  
pp. 179-183 ◽  
Author(s):  
Zhen-Hua Liu ◽  
Tie-Feng Tong ◽  
Yu-Hao Qiu
Keyword(s):  
Experimental Data ◽  
Heat Flux ◽  
Critical Heat Flux ◽  
Jet Impingement ◽  
Nucleate Boiling ◽  
Water Jet ◽  
Stagnation Zone ◽  
Subcooled Water ◽  
Nozzle Size ◽  
Jet Nozzle

An experimental investigation was carried out for predicting the critical heat flux (CHF) of steady boiling for a round subcooled water jet impingement on the flat stagnation zone. The experimental data were measured in a steady nucleate boiling state. Three main influencing parameters, i.e., subcooling, impact velocity and jet nozzle size were widely changed and their effects on the critical heat flux were systemically studied. An empirical correlation was obtained using the experimental data over a wide experimental range for predicting the critical heat flux of steady boiling for a round subcooled water jet impingement on the flat stagnation zone.

Critical Heat Flux Modeling in Forced Convection Boiling During Power Transients

1990 ◽  
Vol 112 (4) ◽  
pp. 1058-1062 ◽  
Author(s):  
K. O. Pasamehmetoglu ◽  
R. A. Nelson ◽  
F. S. Gunnerson
Keyword(s):  
Experimental Data ◽  
Heat Flux ◽  
Theoretical Prediction ◽  
Forced Convection ◽  
Critical Heat Flux ◽  
Nucleate Boiling ◽  
Convective Boiling ◽  
New Model ◽  
Semi Empirical

In this paper, a theoretical prediction of critical heat flux (CHF) during power transients in forced convective boiling is presented. The analysis is restricted to departure from nucleate boiling (DNB) type of CHF at low qualities. The developed theory is compared with the experimental data available in the literature. The agreement is exceptionally good. The new model also is compared with the semi-empirical transient CHF model in the literature.

THE CALCULATION OF CRITICAL HEAT FLUX IN FORCED CONVECTION BOILING

1974 ◽  
Author(s):  
P. B. Whalley ◽  
P. Hutchinson ◽  
Geoffrey F. Hewitt
Keyword(s):  
Heat Flux ◽  
Forced Convection ◽  
Critical Heat Flux

Experimental Study of Heat Transfer to Supercritical Pressure Water Flowing in a 2×2 Rod Bundle

2014 ◽  
Author(s):  
Han Wang ◽  
Qincheng Bi ◽  
Linchuan Wang ◽  
Haicai Lv ◽  
Laurence K. H. Leung
Keyword(s):  
Heat Transfer ◽  
Experimental Data ◽  
Heat Flux ◽  
Pressure Drop ◽  
Wall Temperature ◽  
Mass Flux ◽  
Heat Fluxes ◽  
Outer Diameter ◽  
Square Channel ◽  
Rod Bundle

An experiment has recently been performed at Xi’an Jiaotong University to study the wall temperature and pressure drop at supercritical pressures with upward flow of water inside a 2×2 rod bundle. A fuel-assembly simulator with four heated rods was installed inside a square channel with rounded corner. The outer diameter of each heated rod is 8 mm with an effective heated length of 600 mm. Experimental parameters covered the pressure of 23–28 MPa, mass flux of 350–1000 kg/m2s and heat flux on the rod surface of 200–1000 kW/m2. According to the experimental data, it was found that the circumferential wall temperature distribution of a heated rod is not uniform. The temperature difference between the maximum and the minimum varies with heat flux and/or mass flux. Heat transfer characteristics of supercritical water in bundle were discussed with respect to various heat fluxes. The effect of heat flux on heat transfer in rod bundles is similar with that in tubes or annuli. In addition, flow resistance reflected in the form of pressure loss has also been studied. Experimental results showed that the total pressure drop increases with bulk enthalpy and mass flux. Four heat transfer correlations developed for supercritical pressures water were compared with the present test data. Predictions of Jackson correlation agrees closely with the experimental data.

Critical Heat Flux in Subcooled Water Flow of One-Side-Heated Screw Tubes

1999 ◽  
Vol 35 (3) ◽  
pp. 289-296 ◽  
Author(s):  
Jean Boscary ◽  
Masanori Araki ◽  
Satoshi Suzuki ◽  
Koichiro Ezato ◽  
Masato Akiba
Keyword(s):  
Heat Flux ◽  
Critical Heat Flux ◽  
Water Flow ◽  
Subcooled Water

Flow boiling in microgravity: Part 2 – Critical heat flux interfacial behavior, experimental data, and model

2015 ◽  
Vol 81 ◽  
pp. 721-736 ◽  
Author(s):  
Christopher Konishi ◽  
Hyoungsoon Lee ◽  
Issam Mudawar ◽  
Mohammad M. Hasan ◽  
Henry K. Nahra ◽  
...  
Keyword(s):  
Experimental Data ◽  
Heat Flux ◽  
Critical Heat Flux ◽  
Flow Boiling ◽  
Interfacial Behavior

An Investigation of Flow, Heat Transfer Characteristic of Annular Flow and Critical Heat Flux in Vertical Upward Round Tube

2006 ◽  
Author(s):  
Fan Pu ◽  
Suizheng Qiu ◽  
Guanghui Su ◽  
Dounan Jia
Keyword(s):  
Heat Transfer ◽  
Experimental Data ◽  
Heat Flux ◽  
Heat Transfer Coefficient ◽  
Liquid Film ◽  
Critical Heat Flux ◽  
Heat Transfer Characteristic ◽  
Annular Flow ◽  
Transfer Characteristic ◽  
Round Tube

The term annular flow is used to describe the configuration of vapor-liquid flow in which part of the liquid travels as a film on the wall and the rest is entrained as drops by the vapor core in the center of the channel. The objective of this paper is to develop a hydrodynamic model for vertical upward annular flow. A separated flow model is developed and the conservations of Mass, Momentum, Energy, entrainment rate correlation in wide range of conditions and interfacial frictional correlation are used to research the flow and heat transfer characteristic of annular flow. The liquid film thickness, liquid film mass flow rate, two-phase heat transfer coefficient pressure along axial position, local velocity profiles along radial position are predicted theoretically. The influence of the mass flux, heat flux on liquid film thickness, heat transfer coefficient etc. are investigated in detail. The critical heat flux are also predicted in vertical upward round tube according to the theory that the dryout in vertical annular flow emerges at the point where the film is depleted due to the integrating result of entrainment, deposition and evaporation. The influence of mass flux, inlet mass quality and tube diameter on critical heat flux is also predicted in this paper. Finally the predicted result of critical heat flux is compared with experimental data, and the theoretical CHF values are higher than that of experimental data, with error within 30%.

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