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Prediction of Critical Heat Flux for Saturated Flow Boiling Water in Vertical Narrow Rectangular Channels

얇은 수직 사각유로에서의 포화비등조건 임계열유속 예측

  • 최길식 (한국과학기술원 원자력 및 양자공학과) ;
  • 장순흥 (한동대학교) ;
  • 정용훈 (한국과학기술원 원자력 및 양자공학과)
  • Received : 2015.09.08
  • Accepted : 2015.10.05
  • Published : 2015.12.01

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 %.

산업적으로 얇은 사각유로에서의 임계열유속을 포함한 열수력 현상을 이해하고 이를 시스템 설계에 반영해야 될 필요성이 증대되고 있다. 포화비등조건에서 임계열유속이 발생하는 주요기구는 일반적으로 환상유동 영역에서 액막이 건조되는 것이다. 이러한 임계열유속을 예측하기 위하여 원형관에 대한 대표적인 액막건조모델을 고찰하고 환상유동 시작 경계조건을 상수로 가정하는 기존 모델의 한계를 살펴보았다. 균일한 열유속으로 가열되는 얇은 수직사각유로 상향유동에서의 임계열유속을 예측하기 위하여 환상유동을 단순 모델링하고, 새로운 액막건조모델을 적용하였다. 284 개 실험데이타에 대한 예측성능을 확인한 결과 MAE 18.1%, RMSE 22.9% 예측오차로 실험데이타를 잘 예측할 수 있음을 확인하였다.

Keywords

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. https://doi.org/10.1016/0029-5493(81)90126-6
  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. https://doi.org/10.1016/0029-5493(78)90041-9
  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. https://doi.org/10.1016/0029-5493(90)90369-9
  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. https://doi.org/10.1016/0017-9310(78)90048-0
  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. https://doi.org/10.1016/S0017-9310(01)00072-2
  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. https://doi.org/10.1016/j.pnucene.2011.02.013
  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. https://doi.org/10.1080/18811248.2003.9715370
  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. https://doi.org/10.1002/aic.690260304
  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. https://doi.org/10.1016/0017-9310(84)90142-X
  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. https://doi.org/10.1016/0017-9310(84)90009-7
  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. https://doi.org/10.1016/S0017-9310(01)00111-9
  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. https://doi.org/10.1002/aic.690210212
  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. https://doi.org/10.1016/j.nucengdes.2004.01.005
  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. https://doi.org/10.1016/0017-9310(81)90175-7
  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. https://doi.org/10.1016/0017-9310(81)90176-9
  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. https://doi.org/10.1016/S0301-9322(99)00114-7
  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. https://doi.org/10.1016/S0029-5493(00)00306-X
  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.