Effects of interphase momentum exchange models on simulation of subcooled flow boiling

被引:10
作者
Naghibzadeh, Seyed Mohsen [1 ]
Goharkhah, Mohammad [1 ]
Sharifpur, Mohsen [2 ,3 ]
Meyer, Josua P. [2 ]
机构
[1] Sahand Univ Technol, Fac Mech Engn, Tabriz, Iran
[2] Univ Pretoria, Dept Mech & Aeronaut Engn, ZA-0002 Pretoria, South Africa
[3] Duy Tan Univ, Inst Res & Dev, Da Nang 550000, Vietnam
关键词
Subcooled flow boiling; Eulerian two-phase method; Momentum exchange models; Simulation accuracy; NUCLEATION SITE DENSITY; CRITICAL HEAT-FLUX; CONVECTIVE FLOW; PREDICTION; BUBBLE; VALIDATION; NANOFLUIDS; FRACTION; CAVITY; WATER;
D O I
10.1016/j.icheatmasstransfer.2020.104863
中图分类号
O414.1 [热力学];
学科分类号
摘要
This research aimed to explore the accuracy of different momentum exchange models in the Eulerian multiphase method. Effects of different correlations for interaction forces on predicting of subcooled fluid flow boiling parameters in heated vertical tubes were studied numerically. Specifically, numerical simulations were carried out using several combinations of the momentum exchange coefficients separately. The results were compared with the experimental data of two benchmark test cases, and the error percentages were calculated. Results indicated that the accuracy of the two-phase simulations depended on the selection of the appropriate combination of momentum exchange models. However, it was found that modeling drag with Ishii and Universal, lift with Moraga and Saffman, wall lubrication with Antal et al. and Hosokawa, turbulent dispersion with De Bertodano, and turbulent interaction with Troshko-Hassan correlations generally led to higher accuracy. The results showed that the experimental benchmark data could be simulated numerically with the minimum relative error of 6.97%. The study also showed that wall lubrication and lift had negligible impacts on the numerical results for most working conditions.
引用
收藏
页数:18
相关论文
共 57 条
[1]  
[Anonymous], 1990, PHENOMENA MULTIPHASE
[2]  
Ansys-Fluent, 2015, MULT FLOW THEOR FLUE
[3]   ANALYSIS OF PHASE DISTRIBUTION IN FULLY-DEVELOPED LAMINAR BUBBLY 2-PHASE FLOW [J].
ANTAL, SP ;
LAHEY, RT ;
FLAHERTY, JE .
INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 1991, 17 (05) :635-652
[4]  
Bartolemei G.G., 1967, THERM ENG, V14, P123
[5]   Onset of nucleate boiling and active nucleation site density during subcooled flow boiling [J].
Basu, N ;
Warrier, GR ;
Dhir, VK .
JOURNAL OF HEAT TRANSFER-TRANSACTIONS OF THE ASME, 2002, 124 (04) :717-728
[6]   Pressure drop and void fraction during flow boiling in rectangular minichannels in weightlessness [J].
Brutin, D. ;
Ajaev, V. S. ;
Tadrist, L. .
APPLIED THERMAL ENGINEERING, 2013, 51 (1-2) :1317-1327
[7]  
Burns A.D., 2004, P 5 INT C MULT FLOW
[8]   A PHOTOGRAPHIC STUDY OF POOL BOILING IN THE REGION OF THE CRITICAL HEAT FLUX [J].
COLE, R .
AICHE JOURNAL, 1960, 6 (04) :533-538
[9]  
DEBERTODANO ML, 1994, NUCL ENG DES, V146, P43
[10]   Assessment of 12 CHF prediction methods, for an axially non-uniform heat flux distribution, with the RELAP5 computer code [J].
Ferrouk, M. ;
Aissani, S. ;
D'Auria, F. ;
DelNevo, A. ;
Salah, A. Bousbia .
NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (10) :2718-2725