logo

An investigation of flow characteristics and critical heat flux in vertical upward round tube

MISCELLANEOUS

An investigation of flow characteristics and critical heat flux in vertical upward round tube

FAN Pu
QIU Sui-Zheng
JIA Dou-Nan
Nuclear Science and TechniquesVol.17, No.3pp.170-176Published in print 20 Jun 2006
45100

Prediction of critical heat flux (CHF) in annular flow is important for the safety of once-through steam generator and the reactor core under accident conditions. The dryout in annular flow occurs at the point where the film is depleted due to entrainment, deposition, and evaporation. The film thickness, film mass flow rate along axial distribution, and CHF are calculated in vertical upward round tube on the basis of a separated flow model of annular flow. The theoretical CHF values are higher than those derived from experimental data, with error being within 30%.

Annular flowCritical heat fluxDryoutEntrainmentDeposition
References
[1] Butterwort D, Hewitt G F. Two-phase flow and heat transfer, Oxford University Press, 1977
[2] Isbin H S, Vanerwater R, Fauske H K, et al. J Heat Transfer, 1961, 83(5):149-157
[3] Hewitt G F, Hall-Taylor N S. Annular two-phase flow, Pergamon Press, New York, 1970
[4] Ishii M, Mishima K. Int J Heat Mass Transfer, 1989, 32(10):1835-1846
[5] Tomio Okawa, Tsutoshi Kitahara, Kenji Yoshida, et al. International Heat and Mass Transfer, 2002, 45:87-98
[6] Kataoka I, Ishii M, Nakayama A. Int J Heat Mass Transfer, 2000, 43:1573-1589
[7] Paleev I I, Filippovich B S. Int J Heat Mass Transfer, 1966, 9: 1089-1093
[8] Henstock W H, Hanratty T J. AICHE, 1976, 22: 990-1000
[9] Ren Ling.

Experimental research of dryout in vertical upward round tube, Master Thesis

, China Institute of Atomic Energy, July 2003
Baidu ScholarGoogle Scholar