Void distribution and bubble motion in bubbly flows in a 4 x 4 rod bundle. Part I: Experiments

被引:42
作者
Hosokawa, Shigeo [1 ]
Hayashi, Kosuke [1 ]
Tomiyama, Akio [1 ]
机构
[1] Kobe Univ, Dept Mech Engn, Grad Sch Engn, Nada Ku, Kobe, Hyogo 6578501, Japan
基金
日本学术振兴会;
关键词
rod bundle; two-phase flow; bubbly flow; void fraction; bubble motion; conductivity probe; SINGLE BUBBLES; FRACTION MEASUREMENTS; PIPE FLOWS; SUBCHANNEL; VELOCITIES; LIQUID;
D O I
10.1080/00223131.2013.862189
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Lack of local void fraction data in a rod bundle makes it difficult to validate a numerical method for predicting gas-liquid two-phase flow in the bundle. Distributions of local void fraction and bubble velocity in each subchannel in a 4x4 rod bundle were, therefore, measured using a double-sensor conductivity probe. Liquid velocity in the subchannel was also measured using laser Doppler velocimetry (LDV) to obtain relative velocity between bubbles and the liquid phase. The size and pitch of rods were 10 and 12.5mm, respectively. Air and water at atmospheric pressure and room temperature were used for the gas and liquid phases, respectively. The volume fluxes of gas and liquid phases ranged from 0.06 to 0.15m/s and from 0.9 to 1.5m/s, respectively. Experimental results showed that the distributions of void fraction in inner and side subchannels depend not only on lift force acting on bubbles but also on geometrical constraints on bubble dynamics, i.e. the effects of rod walls on bubble shape and rise velocity. The relative velocity between bubbles and the liquid phase in the subchannel forms a non-uniform distribution over the cross-section, and the relative velocity becomes smaller as bubbles approach the wall due to the wall effects.
引用
收藏
页码:220 / 230
页数:11
相关论文
共 25 条
[1]  
Anklam TM, 1985, NUCL ENG DES, V75, P99
[2]   Turbulence modification in gas-liquid and solid-liquid dispersed two-phase pipe flows [J].
Hosokawa, S ;
Tomiyama, A .
INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW, 2004, 25 (03) :489-498
[3]   Development of a submersible small fiber LDV probe and its application to flows in a 4 x 4 rod bundle [J].
Hosokawa, Shigeo ;
Mikihara, Ikumi ;
Tomiyama, Akio .
NUCLEAR ENGINEERING AND DESIGN, 2013, 263 :342-349
[4]   Measurements of turbulent flows in a 2 x 2 rod bundle [J].
Hosokawa, Shigeo ;
Yamamoto, Taishi ;
Okajima, Jun ;
Tomiyama, Akio .
NUCLEAR ENGINEERING AND DESIGN, 2012, 249 :2-13
[5]   Multi-fluid simulation of turbulent bubbly pipe flows [J].
Hosokawa, Shigeo ;
Tomiyama, Akio .
CHEMICAL ENGINEERING SCIENCE, 2009, 64 (24) :5308-5318
[6]   SIMULTANEOUS MEASUREMENT OF LIQUID AND BUBBLE VELOCITIES IN A CYLINDRICAL BATH SUBJECT TO CENTRIC BOTTOM GAS INJECTION [J].
IGUCHI, M ;
KONDOH, T ;
UEMURA, T .
INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 1994, 20 (04) :753-762
[7]   Numerical simulation of secondary flow in bubbly turbulent flow in sub-channel [J].
Ikeno, Tsutomu ;
Kataoka, Isao .
NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (11) :4568-4574
[8]  
Kamei Akihiro, 2010, Journal of Power and Energy Systems, V4, P315, DOI 10.1299/jpes.4.315
[9]   Subchannel void-fraction measurements in a 6 x 6 rod bundle using a simple gamma-transmission method [J].
Kok, HV ;
van der Hagen, THJJ ;
Mudde, RF .
INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 2001, 27 (01) :147-170
[10]   CFD modelling of subcooled boiling - Concept, validation and application to fuel assembly design [J].
Krepper, Eckhard ;
Koncar, Bostjan ;
Egorov, Yury .
NUCLEAR ENGINEERING AND DESIGN, 2007, 237 (07) :716-731