Void fraction distribution for convective boiling flows in single and multiple heater rods assembly

被引：1

作者：

Yadav, Ashutosh ^{[1
]}

Roy, Shantanu ^{[1
]}

机构：

[1] Indian Inst Technol Delhi, Dept Chem Engn, New Delhi 110016, India

来源：

CHEMICAL ENGINEERING SCIENCE | 2022年 / 247卷

关键词：

Gamma-ray densitometry; Convective boiling flows; Subcooled boiling; Void fraction; BUBBLE; SIMULATION; SUBCHANNEL; PROFILES; DESIGN; MODELS; VOLUME; WATER;

D O I：

10.1016/j.ces.2021.117063

中图分类号：

TQ [化学工业];

学科分类号：

0817 ;

摘要：

Void fraction distribution is an essential parameter for the design and development of nuclear reactors. In this work, void fraction measurements have been performed on an experimental setup mimicking the flow behavior in a calandria of Boiling Water Reactor (BWR). Experimental measurements for void fraction distribution were performed on three heater rods configurations at fixed electrical power using noninvasive gamma-ray densitometry at varying inlet liquid flow rates and temperatures. The main focus of this contribution was to measure void fraction distribution of boiling flows in a test section having the arrangement to accommodate different heater rods configurations by keeping the mechanical aspects of the gamma-ray densitometry technique simple. Measurements were done at four axial locations. and at each axial location, void fraction measurement was performed at eight radial locations. Experimental results show that void fraction profiles are not only influenced by the configuration of heater rods but also by the operating conditions. The void fraction profiles of configuration A were flat as compared to all other heater rod configurations. The data reported here help develop CFD models and understand the dependence of void fraction distribution on heater rods configuration. (c) 2021 Elsevier Ltd. All rights reserved.

引用

页数：12

共 31 条

[1]

[Anonymous], 2012, NUCL SYSTEMS

[2] Interfacial area measurements in subcooled flow boiling [J].

Bartel, MD ;

Ishii, M ;

Masukawa, T ;

Mi, Y ;

Situ, R .

NUCLEAR ENGINEERING AND DESIGN, 2001, 210 (1-3) :135-155

[3]

Collier J.G., 1994, Convective Boiling and Condensation

[4] Accuracy of Eulerian-Eulerian, two-fluid CFD boiling models of subcooled boiling flows [J].

Colombo, M. ;

Fairweather, M. .

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 2016, 103 :28-44

[5] Feasibility investigation of experimental visualization techniques to study subcooled boiling flow [J].

Estrada-Perez, C. E. ;

Yoo, Junsoo ;

Hassan, Yassin A. .

INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 2015, 73 :17-33

[6] Measurement of subcooled flow boiling using Particle Tracking Velocimetry and infrared thermographic technique [J].

Hassan, Y. A. ;

Estrada-Perez, C. E. ;

Yoo, Jun Soo .

NUCLEAR ENGINEERING AND DESIGN, 2014, 268 :185-190

[7] Flow regime transition criteria for upward two-phase flow in vertical narrow rectangular channels [J].

Hibiki, T ;

Mishima, K .

NUCLEAR ENGINEERING AND DESIGN, 2001, 203 (2-3) :117-131

[8] Numerical study of condensing bubble in subcooled boiling flow using volume of fluid model [J].

Jeon, Seong-Su ;

Kim, Seong-Jin ;

Park, Goon-Cherl .

CHEMICAL ENGINEERING SCIENCE, 2011, 66 (23) :5899-5909

[9] Computational Modeling of Multiphase Reactors [J].

Joshi, J. B. ;

Nandakumar, K. .

ANNUAL REVIEW OF CHEMICAL AND BIOMOLECULAR ENGINEERING, VOL 6, 2015, 6 :347-378

[10] Measurements of the void-fraction distribution in a simulated fuel assembly and the role of the void-fraction on the dynamics of a natural circulation loop [J].

Kok, HV ;

vanderHagen, THJJ ;

Mudde, RF .

ANNALS OF NUCLEAR ENERGY, 1997, 24 (16) :1333-1347

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