The visual experiment of boiling crisis triggering process during subcooled flow boiling

被引:8
作者
Liu, Haidong [1 ]
Zhao, Erlei [2 ,3 ]
Chen, Deqi [2 ]
Qin, Jiang [1 ]
Yan, Peigang [1 ]
Liu, Wei [3 ]
Liu, Hanzhou [2 ]
机构
[1] Harbin Inst Technol, Sch Energy Sci & Engn, Key Lab Aerosp Thermophys, Minist Ind & Informat Technol, Harbin 150001, Peoples R China
[2] Chongqing Univ, Key Lab Low Grade Energy Utilizat Technol & Syst, Minist Educ, Chongqing 400044, Peoples R China
[3] Nucl Power Inst China, Chengdu 610041, Peoples R China
基金
中国国家自然科学基金;
关键词
Visual experiment; Subcooled flow boiling; Boiling crisis; Critical heat flux (CHF); Vapor-liquid interfacial features; CRITICAL HEAT-FLUX; CHF MECHANISM; R-134A; WALL; VISUALIZATION; ORIENTATION; CHANNEL; LENGTH;
D O I
10.1016/j.ijthermalsci.2021.107347
中图分类号
O414.1 [热力学];
学科分类号
摘要
Boiling crisis is a very interesting and complex phenomenon, which has attracted wide attention. But even so, the boiling mechanism remains unclear, and there is still further work that should be carried out. In this paper, a visual experiment is carried out to investigate the vapor-liquid interfacial features near the heating wall in subcooled flow boiling for revealing the mechanism of boiling crisis. The test section is a square channel with a cross section of 19 x 19 mm2, and the outer diameter of the heating rod is 9.5 mm. Based on high-speed photography, combined with images processing techniques, characteristics of bubble behaviors near the heating wall region during the critical heat flux (CHF) transient are detailedly analyzed under different working conditions, including the local bubble coalescence, large vapor agglomeration, local rewetting, periodic wavy vapor layer, and liquid film. In particular, through the qualitative and quantitative analysis of the vapor-liquid interfacial features close to the CHF, a different understanding of boiling crisis triggering is presented in this paper. The experimental results show that the thickness of the vapor layer has an indirect effect on the boiling crisis, and the wavelength of the vapor layer and the liquid film are the key parameters for the developing boiling crisis trigger mechanism.
引用
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页数:11
相关论文
共 38 条
[21]  
Lemmon E.W., 2018, NIST standard reference database 23 reference fluid thermodynamic and transport properties, DOI [DOI 10.18434/T4D303, 10.18434/T4D303]
[22]  
Liu W, 2002, CHEM ENG TECHNOL, V25, P447
[23]   Development and assessment of a new CHF mechanistic model for subcooled and low quality flow boiling [J].
Liu, Wei ;
Peng, Shinian ;
Jiang, Guangming ;
Liu, Yu .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2021, 165
[24]   Analytical investigation on rod bundle CHF-regime criterion based on dimensionless groups [J].
Liu, Wei ;
Peng, Shinian ;
Jiang, Guangming ;
Liu, Yu .
INTERNATIONAL JOURNAL OF THERMAL SCIENCES, 2021, 159
[25]  
Mattson R.J, 1972, PHOTOGRAPHIC STUDY S, P1
[26]  
Mattson R.J, 2006, PHOTOGRAPHIC STUDY S
[27]   DESCRIBING THE UNCERTAINTIES IN EXPERIMENTAL RESULTS [J].
MOFFAT, RJ .
EXPERIMENTAL THERMAL AND FLUID SCIENCE, 1988, 1 (01) :3-17
[28]   BOILING HEAT-TRANSFER AND CRITICAL HEAT-FLUX IN LIQUID-FILMS FALLING ON VERTICALLY-MOUNTED HEAT-SOURCES [J].
MUDAWAR, I ;
INCROPERA, TA ;
INCROPERA, FP .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1987, 30 (10) :2083-2095
[29]   An energy model for the transient flow boiling crisis under highly subcooled conditions at atmospheric pressure [J].
Nop, R. ;
Duluc, M. -C. ;
Dorville, N. ;
Kossolapov, A. ;
Chavagnat, F. ;
Bucci, M. .
INTERNATIONAL JOURNAL OF THERMAL SCIENCES, 2021, 168
[30]   Critical heat flux and flow pattern for water flow in annular geometry [J].
Park, JW ;
Baek, WP ;
Chang, SH .
NUCLEAR ENGINEERING AND DESIGN, 1997, 172 (1-2) :137-155