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

Nuclear Engineering and Design

Volumn 199, Issue 1, 2000, Pages 49-73

  Kim, Hong Chae ^a   Baek, Won Pil ^a   Chang, Soon Heung ^a  

^a Korea Advanced Institute of Science and Technology (KAIST)   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

CORRELATION METHODS; FLOW OF WATER; HEAT TRANSFER COEFFICIENTS; PRESSURE; THERMODYNAMICS; TUBES (COMPONENTS);

CRITICAL HEAT FLUX; LIQUID FILM DRYOUT MODEL; MASS FLUX; WATER FLOW;

HEAT FLUX;

EID: 0033690146     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(99)00074-6     Document Type: Article

References (32)

1. Baek, W.P., Moon, S.K., Chang, S.H., 1995. A modified CHF correlation for low flow of water at low pressures. In: Proceedings of the First International Symposium on Two-Phase Flow Modeling and Experimentation, Rome, Italy, 9-11 October, pp. 853-858.
2. Baek, W.P., Kim, H.G., Chang, S.H., 1997. KAIST critical heat flux correlation for water flow in vertical round tubes, NUTHOS-5, Paper No. AA5.
3. Bennett A.W., Hewitt G.F., Kearsey H.A., Keeys R.K.F., Pulling D.J. Studies of burnout in boiling heat transfer. Trans. Inst. Chem. Eng. 45:1967;T319-T339.
4. Bergles A.E. Burnout in boiling heat transfer, Part II: subcooled and low quality forced convection systems. Nucl. Safety. 18:1977;154-167.
5. -2, AEEW-R-789.
6. Chang S.H., Baek W.P., Bae T.M. A study of critical heat flux for low flow of water in vertical round tubes under low pressure. Nucl. Eng. Des. 132:1991;225-237.
7. Collier J.G., Thome J.R. Convective Boiling and Condensation. 3:1994;329-367 Oxford University Press, Oxford.
8. Govan, A.H., Hewitt, G.F., Owen, D.G., Bott, T.R., 1988. An improved CHF modeling code. In: 2nd UK National Conference on Heat Transfer, London, UK, vol. 1, pp. 33-48.
9. Groeneveld D.C., Leung L.K.H., Kirillov P.L., Bobkov V.P., Smogalev I.P., Vinogradov V.N., Huang X.C., Royer E. The 1995 look-up table for critical heat flux in tubes. Nucl. Eng. Des. 163:1996;1-23.
10. Haramura Y., Katto Y. A new hydrodynamic model of critical heat flux, applicable widely to both pool and forced convection boiling on submerged bodies in saturated liquids. Int. J. Heat Mass Transfer. 26:1983;389-399.
11. Hewitt G.F. Burnout. Hetsroni G. Handbook of Miltiphase Systems. 1:1982;Hemisphere Publishing Corporation, USA.
12. Inasaka F., Nariai H. Evaluation of subcooled critical heat flux correlations for tubes with and without internal twisted tapes. Nucl. Eng. Des. 163:1996;225-239.
13. Kataoka, I., Ishii, M., 1982. Mechanism and correlation of droplet entrainment and deposition in annular two-phase flow, NUREG/CR-2885, ANL-82-44.
14. Katto Y. A study on limiting exit quality of CHF of forced convection boiling in uniformly heated vertical channels. Trans. ASME. 104(2):1982;40-47.
15. Katto Y., Ohno H. An improved version of the generalized correlation of critical heat flux for the forced convective boiling in uniformly heated vertical tubes. Int. J. Heat Mass Transfer. 27(9):1984;1641-1648.
16. Katto Y. Prediction of critical heat flux for annular flow in tubes taking into account the critical liquid film thickness concept. Int. J. Heat Mass Transfer. 27(6):1984;883-891.
17. Kim, Y.I., Baek, W.P., Chang, S.H., 1998. Critical heat flux for oscillatory water flow in vertical round tubes. In: Proceedings of the Eleventh International Heat Transfer Conference, Kyongju, South Korea, vol. 6, pp. 9-14.
18. Kirillov, P.L., 1994. Some aspects of heat transfer during nuclear reactor accidents. In: Proceedings of the Tenth International Heat Transfer Conference, pp. 387-417.
19. Lee, Y.H., Chun, T.H., Baek, W.P., Chang, S.H., 1998. Development of the heated length to diameter correction factor on critical heat flux using the artificial neural networks. In: Proceedings of the Korean Nuclear Society Spring Meeting, Seoul, South Korea, vol. 1, May, pp. 443-448.
20. Levitan L.L., Lantsman F.P. Investigating burnout with flow of a steam-water mixture in a round tube. Therm. Eng. (USSR). 22(1):1975;102-105. (English Transl.).
21. Levy S., Healzer I.M., Abdollahian D. Prediction of critical heat flux in vertical pipe flow. Nucl. Eng. Des. 24:1981;131-140.
22. Lowdermilk, W.H., Lanzo, C.D., Siegel, B.L., 1958. Investigation of boiling burnout and flow stability for water flowing in tubes, NACA-TN-4382.
23. Mishima K., Ishii M. Flow regime transition criteria for upward two-phase flow in vertical tubes. Int. J. Heat Mass Transfer. 27(5):1984;723-737.
24. Mishima K., Nishihara H., Michiyoshi I. Boiling burnout and flow instabilities for water flowing in a round tube under atmospheric pressure. Int. J. Heat Mass Transfer. 28:1985;1115-1129.
25. Mishima K., Nishihara H. Effect of channel geometry on critical heat flux for low pressure water. Int. J. Heat Mass Transfer. 30(6):1987;1169-1182.
26. Mishima, K., Nishihara, H., Kureta, M., Tasaka, K., 1993. Critical heat flux for low pressure water in small diameter tubes. In: Proc. Sixth Int. Top. Meet. Nucl. Reactor T/H, Grenoble, France, pp. 435-443.
27. Moon S.K., Baek W.P., Chang S.H. Parametric trend analysis of the critical heat flux based on artificial neural networks. Nucl. Eng. Des. 163:1996;29-49.
28. Park C., Baek W.P., Chang S.H. Countercurrent flooding limited critical heat flux in vertical channels at zero inlet flow. Int. Comm. Heat Mass Transfer. 24(4):1997;453-464.
29. Shah M.M. Improved general correlation for critical heat flux during upflow in uniformly heated vertical tubes. Heat Fluid Flow. 8(4):1987;326-335.
30. Wallis G.B. One Dimensional Two-phase Flow. 1969;McGraw-Hill, New York.
31. Whalley, P.B., Hutchinson, P., James, P.W., 1978. The calculation of critical heat flux in complex situations using an annular flow model. In: Proceedings of the Sixth International Heat Transfer Conference, Toronto, Canada, vol. 5, pp. 65-70.
32. Weber, P., Johannsen, K., 1990. Study of critical heat flux condition at convective boiling of water: temperature and power controlled experiments. In: Proceedings of the Ninth International Heat Transfer Conference, 1-BO-11, Jerusalem, Israel, vol. 2, pp. 63-68.