Experimental study on bubble dynamics and wall heat transfer arising from a single nucleation site at subcooled flow boiling conditions - Part 2: Data analysis on sliding bubble characteristics and associated wall heat transfer

被引:39
作者
Yoo, Junsoo [1 ]
Estrada-Perez, Carlos E. [2 ]
Hassan, Yassin A. [2 ,3 ]
机构
[1] Idaho Natl Lab, 2525 North Fremont Ave,POB 3860, Idaho Falls, ID 83415 USA
[2] Texas A&M Univ, Dept Mech Engn, 100 MEOB, College Stn, TX 77843 USA
[3] Texas A&M Univ, Dept Nucl Engn, 253 Bizzell West, College Stn, TX 77843 USA
关键词
Subcooled flow boiling; Single nucleation site; Bubble sliding; Bubble coalescence; Sliding bubble velocity; Bubble size distribution; Boiling heat transfer; DEPARTURE FREQUENCY; VERTICAL UPFLOW; NARROW CHANNEL; LOW-PRESSURES; SYSTEM; FLUX; VISUALIZATION; DIAMETER; VELOCITY; BEHAVIOR;
D O I
10.1016/j.ijmultiphaseflow.2016.04.019
中图分类号
O3 [力学];
学科分类号
08 ; 0801 ;
摘要
This second of two companion papers presents an analysis of sliding bubble and wall heat transfer parameters measured during subcooled boiling in a square, vertical, upward flow channel. Bubbles were generated only from a single nucleation site for better observation of both the sliding bubble characteristics and their impact on wall heat transfer through optical measurement techniques. Specific interests include: (i) bubbles departure and subsequent growth while sliding, (ii) bubbles release frequency, (iii) coalescence of sliding bubbles, (iv) sliding bubbles velocity, (v) bubbles size distribution and (vi) wall heat transfer influenced by sliding bubbles. The results showed that sliding bubbles involve two distinct growth behaviors: (i) at low mass fluxes, sliding bubbles grew fast near the nucleation site, subsequently shrank, and then grew again, (ii) as mass flux increased, however, sliding bubbles grew more steadily. The bubbles originating from the single nucleation site coalesced frequently while sliding, which showed close relation with bubbles release frequency. The sliding bubble velocity near the nucleation site consistently decreased by increasing mass flux, while the observation often became reversed as the bubbles slid downstream due to the effect of interfacial drag. The sliding bubbles moved faster than the local liquid (i.e., u(r) < 0) at low mass flux conditions, but it became reversed as the mass flux increased. The size distribution of sliding bubbles followed Gaussian distribution well both near and far from the nucleation site. The standard deviation of bubble size varied insignificantly through sliding compared to the changes in mean bubble size. Lastly, the sliding bubbles enhanced the wall heat transfer and the effect became more noticeable as inlet subcooling/mass flux decreased or wall heat flux increased. In particular, the sliding bubble characteristics such as bubble growth behavior observed near the nucleation site played a dominant role in determining the ultimate level of wall heat transfer enhancement within the test channel. (C) 2016 Elsevier Ltd. All rights reserved.
引用
收藏
页码:292 / 314
页数:23
相关论文
共 43 条
[1]   Analysis of subcooled boiling flow with one-group interfacial area transport equation and bubble lift-off model [J].
Bae, Byoung-Uhn ;
Yun, Byong-Jo ;
Yoon, Han-Young ;
Song, Chul-Hwa ;
Park, Goon-Cherl .
NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (09) :2281-2294
[2]   Wall heat flux partitioning during subcooled flow boiling: Part 1 - Model development [J].
Basu, N ;
Warrier, GR ;
Dhir, VK .
JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME, 2005, 127 (02) :131-140
[3]  
Bowring R.W., 1962, OECD Halden Reactor Project Report HPR-10
[4]   Modeling subcooled flow boiling in vertical channels at low pressures - Part 1: Assessment of empirical correlations [J].
Cheung, S. C. P. ;
Vahaji, S. ;
Yeoh, G. H. ;
Tu, J. Y. .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2014, 75 :736-753
[5]   Bubble Lift-off Diameter and Nucleation Frequency in Vertical Subcooled Boiling Flow [J].
Chu, In-Cheol ;
No, Hee Cheon ;
Song, Chul-Hwa .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2011, 48 (06) :936-949
[6]   A PHOTOGRAPHIC STUDY OF POOL BOILING IN THE REGION OF THE CRITICAL HEAT FLUX [J].
COLE, R .
AICHE JOURNAL, 1960, 6 (04) :533-538
[7]   THE INFLUENCE OF BUBBLY FLOW ON BOILING FROM A TUBE IN A BUNDLE [J].
CORNWELL, K .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1990, 33 (12) :2579-2584
[8]   SUBCOOLED FLOW BOILING AT HIGH HEAT-FLUX [J].
DELVALLE, VH ;
KENNING, DBR .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1985, 28 (10) :1907-1920
[9]   Characteristics of Bubble Departure Frequency in a Low-Pressure Subcooled Boiling Flow [J].
Euh, Dongjin ;
Ozar, Basar ;
Hibiki, Takashi ;
Ishii, Mamoru ;
Song, Chul-Hwa .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2010, 47 (07) :608-617
[10]  
FORSTER HK, 1959, J HEAT TRANSFER, V81, P43