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Received July 2, 2003
Accepted November 8, 2003
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Prediction of Critical Heat Flux (CHF) for Vertical Round Tubes with Uniform Heat Flux in Medium Pressure Regime
Department of Chemical Engineering, Dankook University, Seoul 140-714, Korea
wjshim@dankook.ac.kr
Korean Journal of Chemical Engineering, January 2004, 21(1), 75-80(6), 10.1007/BF02705383
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Abstract
The description of critical heat flux (CHF) phenomena under medium pressure (10 bar ≤ P ≤ 70.81 bar) regime is complex due to the large specific volume of vapor and the effect of buoyancy that are inherent in the conditions. In this study, a total of 2,562 data points of CHF in uniformly heated round vertical tube for water were collected from 5 different published sources. The data consisted of the following parameter ranges: 93.7 ≤ G (mass flux) ≤ 18,580 kg/ms, 0.00114 ≤ D (diameter) ≤ 0.03747 m, 0.008 ≤ L (length) ≤ 5 m, 0.26 ≤ qc (CHF) ≤ 9.72MW/m2, and -0.21 ≤ L (exit qualities) ≤ 1.09. A comparative analysis is made on available correlations, and a new correlation is presented. The new CHF correlation is comprised of local variables, namely, “true” mass quality, mass flux, tube diameter, and two parameters as a function of pressure only. This study reveals that by incorporating “true” mass quality in a modified local condition hypothesis, the prediction of CHF under these conditions can be obtained quite accurately, overcoming the difficulties of flow instability and buoyancy effects. The new correlation predicts the CHF data are significantly better than those currently available correlations, with average error 2.5% and rms error 11.5% by the heat balance method.
References
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Thompson B, Macbeth RV, "Boiling Water Heat Transfer Bumout in Uniformly Heated Round Tubes: A Compilation of World CHF Data with Accurate Correlations," AEEW-R 356, United Kingdom Atomic Energy Authority (1964)
Becker KM, "Burnout Data for Flow of Boiling Water in Vertical Round Ducts, Annuli, and Rod Clusters," Aktiebolaget Atomenergie Report AE 177, Sweden (1965)
Biasi L, Clerici GC, Garribba S, Sara R, Energia Nucl., 14(9), 530 (1967)
Casterline JE, Matzner B, "Burnout in Vertical Long Tubes with Uniform and Cosine Heater Using Water at 1000 psia," Topical Report No. 1, TASK XVI, Columbia University (1964)
Griffel J, "Forced Convection Boiling Burnout for Water in Uniformly Heated Tubular Test Sections," NYO-187-7, Columbia University (1965)
Inasaka F, Nariai H, Nucl. Eng. Design, 163, 225 (1996)
Jafri T, Dougherty TJ, Yang B, "Correlation of Critical Heat Flux for Uniform Tubes," NURETH-7, 4, 3197 (1995)
Jafri T, "Interpretation and Analysis of the Vertical Round Tube Critical Heat Flux Data," Ph.D. Thesis, Columbia University (1993)
Katto Y, Ohno H, J. Heat Mass Transf., 27(9), 1641 (1984)
Kim HC, Baek WP, Chang SH, Nucl. Eng. Design, 199(1), 49 (2000)
Mishima K, Nishihara H, Int. J. Heat Mass Transf., 30(6), 1169 (1987)
Saha P, Zuber N, "Point of Net Vapor Generation and Vapor Void Fraction in Subcooled Boiling," Proceeding of the 5th Int. heat Transfer Conference, Tokyo, Japan, pp. 175-179 (1974)
Shah MM, Heat Fluid Flow, 8(4), 326 (1987)
Shim WJ, Joo SK, J. Ind. Eng. Chem., 8(3), 268 (2002)
Shim WJ, Korean J. Chem. Eng., 14(6), 528 (1997)
Thompson B, Macbeth RV, "Boiling Water Heat Transfer Bumout in Uniformly Heated Round Tubes: A Compilation of World CHF Data with Accurate Correlations," AEEW-R 356, United Kingdom Atomic Energy Authority (1964)
