Published August 2018 | Version v1
Journal article

One-dimensional interfacial area transport for bubbly two-phase flow in vertical 5 × 5 rod bundle

  • 1. Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Chongqing University, Ministry of Education, Chongqing 400044 (China)
  • 2. School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette 47907-2017 (United States)

Description

Highlights: • Axial development of two-phase parameters in rod bundle are measured. • Spacer grids affects two-phase flow parameters. • "Swirling effect" and "bubble breaker effect" of space grid have been identified. • A drift-flux correlation for adiabatic rod bundle has been developed. • Hibiki-Ishii correlation agrees with the current interfacial area concentration well. - Abstract: For the modeling of the interfacial structure characteristics, an experiment of vertical adiabatic air-water flow has been conducted under an atmosphere pressure condition. The experimental facility is composed of 5 × 5 rods arranged on a square pitch in a square casing with 9.5 mm outside rod diameter and 12.6 mm pitch, simulating a prototypic rod bundle in nuclear reactors. The miniaturized four-sensor conductivity probe has been developed to allow for the experimental measurement in the small flow channel. Extensive data are acquired for one-dimensional flow parameters including axial development of void fraction, interfacial area concentration and gas velocity. The effect of a prototypic spacer grids with mixing vanes on the flow structure has been discussed at various flow conditions based on the experimental data. Two competing effects, "swirling effect" and "bubble breaker effect", are identified. The effect vanishes out within a short distance from the space grid. A drift-flux correlation is developed for predicting void fraction of adiabatic bubbly two-phase flow in a vertical rod bundle. Existing interfacial area correlations are tested and Hibiki-Ishii correlation (2002b) is recommended as most accurate correlation to predict the interfacial area concentration. It is expected that the newly obtained data in the 5 × 5 rod bundle is useful for developing the interfacial area transport equation and benchmarking a computational code.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.ijheatfluidflow.2018.06.006

Additional details

Identifiers

DOI
10.1016/j.ijheatfluidflow.2018.06.006;
PII
S0142727X17312225;

Publishing Information

Journal Title
International Journal of Heat and Fluid Flow
Journal Volume
72
Journal Page Range
p. 257-273
ISSN
0142-727X
CODEN
IJHFD2

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50051941
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
BUBBLES; CORRELATIONS; FUEL ELEMENT CLUSTERS; ONE-DIMENSIONAL CALCULATIONS; TRANSPORT THEORY; TWO-PHASE FLOW; VOID FRACTION
Descriptors DEC
FLUID FLOW; FUEL ASSEMBLIES

Optional Information

Copyright
Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.