Drift-flux model for upward dispersed two-phase flows in a vertical rod bundle

被引:13
作者
Hibiki, Takashi [1 ]
Tsukamoto, Naofumi [2 ]
机构
[1] City Univ Hong Kong, Dept Mech Engn, 83 Tat Chee Ave, Hong Kong, Peoples R China
[2] Nucl Regulat Author, Regulatory Stand & Res Dept, Roppongi First Bldg,1-9-9 Roppongi, Minato, Tokyo 1068450, Japan
关键词
Drift -flux model; Drift velocity; Void fraction; Rod bundle; Interfacial transfer; VOID-FRACTION; HIGH-PRESSURE;
D O I
10.1016/j.applthermaleng.2023.120323
中图分类号
O414.1 [热力学];
学科分类号
摘要
The present study investigates the drift-flux model for upward dispersed two-phase flows in a vertical rod bundle. The drift-flux model is critical to formulating the interfacial drag force in one-dimensional simulation codes. A rod bundle includes three length scales: a large outer casing width, a medium hydraulic equivalent diameter of a subchannel, and a small gap between rods. Existing research does not provide comprehensive information on an appropriate geometrical length scale for a rod bundle. The present study calculates the evolution process of the drift velocity using the two-bubble-group approach. The two-bubble-group-based formulation is simplified to calculate the drift velocity behavior at the transition between bubbly and beyond-bubbly flows. A scheme is proposed to explicitly calculate the distribution parameter and drift velocity with operating parameters. The new drift-flux correlation is validated by 317 data collected for the pressure from 0.1 to 12 MPa. The extensive evaluation identifies that an appropriate length scale characterizing a two-phase flow in a rod bundle is an outer casing width of a rod bundle. The prediction bias of the new drift-flux correlation was negligibly small, and the random error was 0.0571 in an absolute value measure and 16.1 % in a relative value measure.
引用
收藏
页数:15
相关论文
共 26 条
[1]   VOID FRACTION UNDER HIGH-PRESSURE, LOW FLOW CONDITIONS IN ROD BUNDLE GEOMETRY [J].
ANKLAM, TM ;
MILLER, RF .
NUCLEAR ENGINEERING AND DESIGN, 1983, 75 (01) :99-108
[2]  
[Anonymous], 2008, TRACE V50 THEORY MAN
[3]   THE PHYSICAL CLOSURE LAWS IN THE CATHARE CODE [J].
BESTION, D .
NUCLEAR ENGINEERING AND DESIGN, 1990, 124 (03) :229-245
[4]  
Borkowski J.A., 1992, TRAC BF1MOD1 MODELS
[5]   Modeling of bubble-layer thickness for formulation of one-dimensional interfacial area transport equation in subcooled boiling two-phase flow [J].
Hibiki, T ;
Situ, R ;
Mi, Y ;
Ishii, M .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2003, 46 (08) :1409-1423
[6]   One-dimensional drift-flux model for two-phase flow in a large diameter pipe [J].
Hibiki, T ;
Ishii, M .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2003, 46 (10) :1773-1790
[7]   Drift-flux model for upward dispersed two-phase flows in vertical medium-to-large round tubes [J].
Hibiki, Takashi ;
Tsukamoto, Naofumi .
PROGRESS IN NUCLEAR ENERGY, 2023, 158
[8]   Channel size effect on drift-flux parameters for adiabatic and boiling two-phase flows [J].
Hibiki, Takashi ;
Ju, Peng ;
Rassame, Somboon ;
Miwa, Shuichiro ;
Shen, Xiuzhong ;
Ozaki, Tetsuhiro .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2022, 185
[9]   One-dimensional drift-flux correlations for two-phase flow in medium-size channels [J].
Hibiki, Takashi .
EXPERIMENTAL AND COMPUTATIONAL MULTIPHASE FLOW, 2019, 1 (02) :85-100
[10]  
Information System Laboratories, 2001, NUREGCR 5535REV1 INF, VIV