JOURNAL BROWSE
Search
Advanced SearchSearch Tips
Prediction of Critical Heat Flux for Saturated Flow Boiling Water in Vertical Narrow Rectangular Channels
facebook(new window)  Pirnt(new window) E-mail(new window) Excel Download
 Title & Authors
Prediction of Critical Heat Flux for Saturated Flow Boiling Water in Vertical Narrow Rectangular Channels
Choi, Gil Sik; Chang, Soon Heung; Jeong, Yong Hun;
  PDF(new window)
 Abstract
There is an increasing need to understand the thermal-hydraulic phenomena, including the critical heat flux (CHF), in narrow rectangular channels and consider these in system design. The CHF mechanism under a saturated flow boiling condition involves the depletion of the liquid film of an annular flow. To predict this type of CHF, the previous representative liquid film dryout models (LFD models) were studied, and their shortcomings were reviewed, including the assumption that void fraction or quality is constant at the boundary condition for the onset of annular flow (OAF). A new LFD model was proposed based on the recent constitutive correlations for the droplet deposition rate and entrainment rate. In addition, this LFD model was applied to predict the CHF in vertical narrow rectangular channels that were uniformly heated. The predicted CHF showed good agreement with 284 pieces of experimental data, with a mean absolute error of 18. 1 % and root mean square error of 22.9 %.
 Keywords
Annular Flow;Critical Heat Flux;Droyout;Liquid Film Dryout Model;Narrow Rectangular Channel;Saturated Boiling;
 Language
Korean
 Cited by
 References
1.
Choi, G.S. and Chang, S.H., 2014, "Review of Critical Heat Flux Correlations for Upward Flow in a Vertical Thin Rectangular Channel," Trans. Korean Nuclear Soc. Spring Meeting.

2.
Chang, S.H., Baek, W.P., 1997, Critical Heat Flux(Korean), Chung Moon Gak, pp. 117-118.

3.
Whalley, P.B., 1987, Boiling, Condensation, and Gas- Liquid Flow, Clarendon Press., Oxford, pp. 181-183.

4.
Levy, S., Healzer, J.M. and Abdollahian, D., 1981, "Prediction of Critical Heat Flux in Vertical Pipe Flow," Nuclear Engineering and Design, Vol. 65, pp. 131-140. crossref(new window)

5.
Wurtz, J., 1978, "An Experimental and Theoretical Investigation of Annular Steam-Water Flow in Tubes and Annuli at 30-90 bar," Riso Report No. 372, Riso National Lab.

6.
Saito, T., Hughes, E.D. and Carbon, M.W., 1978, "Multi-fluid Modeling of Annular Two-phase Flow," Nuclear Engineering and Design, Vol. 50, pp. 225-271. crossref(new window)

7.
Sugawara, S. and Miyamoto, Y., 1990, "FIDAS: Detailed Subchannel Analysis Code based on the Three-fluid and Three-field Model," Nuclear Engineering and Design, Vol. 120, pp. 147-161. crossref(new window)

8.
El-Shanawany, M., El-Shirbini, A.A and Murgatroyd, W., 1978, "A Model for Predicting the Dry-out Position for Annular Flow in a Uniformly Heated Vertical Tube," International Journal of Heat and Mass Transfer, Vol. 21, pp. 529-536. crossref(new window)

9.
Mishima, K. and Nishihara, H., 1989, "Dryout Model for Critical Heat Flux at High and Intermediate Quality Region," Annu. Rep., Res. Reactor Inst. Kyoto Univ., Vol. 22, pp. 1-13.

10.
Celata, G.P., Mishima, K. and Zummo, G., 2001, "Critical Heat Flux Prediction for Saturated Flow Boiling of Water in Vertical Tubes," International Journal of Heat and Mass Transfer, Vol. 44, pp. 4323-4331. crossref(new window)

11.
Chandraker, D.K., Vijayan, P.K., Sinha, R.K. and Aritomi, M., 2011, "Phenomenological Prediction of CHF under Boiling Water Reactor (BWR) Conditions," Progress in Nuclear Energy, Vol. 53, pp. 874-880. crossref(new window)

12.
Okawa, T., Kotani, A., Kataoka, I and Naito, M., 2003, "Prediction of Critical Heat Flux in Annular Flow using a Film Flow Model," Journal of Nuclear Science and Technology, Vol. 40, No. 6, pp. 388-396. crossref(new window)

13.
Hewitt, G.F. and Roberts, D.N., 1969, "Studies of Two-phase Flow Patterns by Simultaneous X-ray and Flash Photography," AERE-M-2159, UK AEA.

14.
Wallis, G.B., 1969, One-dimensional Two-phase Flow, McGraw-Hill, USA.

15.
Collier, J.G and Thome J.R., 1996, Convective Boiling and Condensation, 3rd edition, Clarendon Press, Oxford.

16.
Taitel, Y., Bornea, D. and Dukler, A.E., 1980, "Modelling Flow Pattern Transitions for Steady Upward Gas-Liquid Flow in Vertical Tubes," AlChE Journal, Vol. 26, No. 3, pp. 345-354. crossref(new window)

17.
Mishima, K. and Ishii, M., 1984, "Flow Regime Transition Criteria for Upward Two-phase Flow in Vertical Tubes," International Journal of Heat and Mass Transfer, Vol. 27, No. 5, pp. 723-737. crossref(new window)

18.
Saha, P. and Zuber, N., 1974, "Point of Net Vapor Generation and Vapor Void Fraction in Subcooled Boiling," Proceedings of 5th International Heat Transfer Conference, Tokyo.

19.
Katto, Y., 1984, "Prediction of Critical Heat Flux for Annular Flow in Tubes taking into account the Critical Liquid Film Thickness Concept," International Journal of Heat and Mass Transfer, Vol. 27, No. 6, pp. 883-891. crossref(new window)

20.
Okawa, T., Kitahara, T., Yoshida, K., Matsumoto, T. and Kataoka, I., 2002, "New Entrainment Rate Correlation in Annular Two-phase Flow Applicable to Wide Range of Flow Condition," International Journal of Heat and Mass Transfer, Vol. 45, pp. 87-98. crossref(new window)

21.
Ishii, M. and Grolmes, M.A., 1975, "Inception Criteria for Droplet Entrainment in Two-phase Concurrent Film Flow," AlChE Journal, Vol. 21, No. 2, pp. 308-318. crossref(new window)

22.
Okawa, T., Kotani, A., Kataoka, I. and Naitoh, M., 2004, "Prediction of the Critical Heat Flux in Annular Regime in Various Vertical Channels," Nuclear Engineering and Design, Vol. 229, pp. 223-236. crossref(new window)

23.
Ueda, T., Inoue, M. and Nagatome, S., 1981, "Critical Heat Flux and Droplet Entrainment Rate in Boiling of Falling Liquid Films," International Journal of Heat and Mass Transfer, Vol. 24., No. 7, pp. 1257-1266. crossref(new window)

24.
Ueda, T. and Isayama, Y., 1981, "Critical Heat Flux and Exit Film Flow Rate in a Flow Boiling System," International Journal of Heat and Mass Transfer, Vol. 24, No. 7, pp. 1267-1276. crossref(new window)

25.
Fore, L.B., Beus, S.G. and Bauer, R.C., 2000, "Interfacial Friction in Gas-Liquid Annular Flow: Analogies to Full and Transition Roughness," International Journal of Multiphase Flow, Vol. 26, pp. 1755-1769. crossref(new window)

26.
Hibiki, T. and Mishima, K., 2001, "Flow Regime Transition Criteria for Upward Two-phase flow in Vertical Narrow Rectangular Channels," Nuclear Engineering and Design, Vol. 203, pp. 117-131. crossref(new window)

27.
DeBortoli, R.A., Green, S.J., LeTournea, B.W., Troy, M. and Weiss, A., 1958, Forced-Convection Heat Transfer Burnout Studies for Water in Rectangular Channels and Round Tubes at Pressures Above 500 psia, WAPD-188, Westinghouse Electric Corporation.

28.
Troy, M., 1958, Upflow Burnout Data for Water at 2000, 1200, 800 and 600 psia in Vertical 0.070in.x2.25in.x72in. Long Stainless Steel Rectangular Channels, WAPD-TH-408, Westinghouse Electric Corporation.

29.
Jacket, H.S., Roatry, J.D. and Zerbe, J.E., 1958, "Investigation of Burnout Heat Flux in Rectangular Channels at 2000 psia," Trans. of the ASME, Journal of Heat Transfer, Vol. 80, No. 2, pp. 391-401.

30.
Tippets, F.E., 1962, "Critical Heat Flux and Flow Pattern Characteristics of High Pressure Boiling Water in Forced Convection," GEAP-3766, General Electric Company.