Comparison between wire-mesh sensors and conductive needle-probes for measurements of two-phase flow parameters

The vertical co-current downward air-water two-phase flow was studied under adiabatic condition in round tube test sections of 25.4-mm and 50.8-mm ID. In flow regime identification, a new approach was employed to minimize the subjective judgment. It was found that the flow regimes in the co-current downward flow strongly depend on the channel size. In addition, various local two-phase flow parameters were acquired by the multi-sensor miniaturized conductivity probe in bubbly flow. Furthermore, the area-averaged data acquired by the impedance void meter were analyzed using the drift flux model. Three different distributions parameters were developed for different ranges of non-dimensional superficial velocity, defined by the ration of total superficial velocity to the drift velocity.

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Local characteristic of horizontal air–water two-phase flow by wire-mesh sensor

Transactions of the Institute of Measurement and Control ◽

10.1177/0142331216665689 ◽

2016 ◽

Vol 40 (3) ◽

pp. 746-761 ◽

Cited By ~ 5

Author(s):

Weiling Liu ◽

Chao Tan ◽

Feng Dong

Keyword(s):

Void Fraction ◽

Transient Flow ◽

Two Phase Flow ◽

Wire Mesh ◽

Local Characteristic ◽

Phase Flow ◽

Flow Conditions ◽

Two Phase ◽

Horizontal Pipe ◽

Local Flow

Two-phase flow widely exists in many industries. Understanding local characteristics of two-phase flow under different flow conditions in piping systems is important to design and optimize the industrial process for higher productivity and lower cost. Air–water two-phase flow experiments were conducted with a 16×16 conductivity wire-mesh sensor (WMS) in a horizontal pipe of a multiphase flow facility. The cross-sectional void fraction time series was analysed by the probability density function (PDF), which described the void fraction fluctuation at different flow conditions. The changes and causes of PDFs during a flow regime transition were analysed. The local structure and flow behaviour were characterized by the local flow spectrum energy analysis and the local void fraction distribution (horizontal, vertical and radial direction) analysis. Finally, three-dimensional transient flow fluctuation energy evolution and characteristic scale distribution based on wavelet analysis of air–water two-phase flow were presented, which revealed the structural features of each phase in two-phase flow.

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An Experimental Study of Two-Phase Flow in a Tight Lattice Using Wire-Mesh Sensor

10.1115/1.0000349v ◽

2021 ◽

Author(s):

Hengwei Zhang ◽

Yao Xiao ◽

Hanyang Gu

Keyword(s):

Experimental Study ◽

Two Phase Flow ◽

Wire Mesh ◽

Phase Flow ◽

Two Phase ◽

Tight Lattice

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Measuring two phase flow parameters using impedance cross-correlation flow meter

10.1063/1.3694692 ◽

2012 ◽

Cited By ~ 2

Author(s):

Y. Muhamedsalih ◽

G. Lucas

Keyword(s):

Cross Correlation ◽

Two Phase Flow ◽

Phase Flow ◽

Flow Meter ◽

Two Phase ◽

Flow Parameters

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Influence of Gas Properties on Gas-Liquid Two-Phase Flow

Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation ◽

10.1115/icone2020-16434 ◽

2020 ◽

Author(s):

Miki Saito ◽

Taizo Kanai ◽

Satoshi Nishimura ◽

Yoshihisa Nishi

Keyword(s):

Removal Efficiency ◽

Nuclear Power ◽

Two Phase Flow ◽

Wire Mesh ◽

Severe Accident ◽

Phase Flow ◽

Stagnant Water ◽

Two Phase ◽

Bubble Characteristics ◽

Gas Properties

Abstract Understanding the mechanism of fission product (FP) removal by pool scrubbing is essential for improving the prediction accuracy of FP emissions concerning severe accident (SA) in a nuclear power plant. Since FP migrates from a gas-phase to a liquid-phase via a gas-liquid interface, the FP removal efficiency by pool scrubbing is largely affected by the flow regime of gas-liquid two-phase flow. In order to gain a deeper understanding of the influence of gas properties on flow regimes, experiments were performed by injecting helium (He) and nitrogen (N2) gas mixtures of several volumetric ratios through a pool of stagnant water. The result suggests clear effects of gas compositions on gas-liquid two-phase flow, where both void and holdup fractions were found to increase with N2 fraction in the supplied gas. The results were compared with previous studies, and a detailed analysis of bubble characteristics for different compositions of gases was performed using a wire-mesh sensor (WMS). This paper also illustrates further research aspects needed to discuss the effect of its results on FP removal efficiency in a SA, and to acquire comprehensive physics behind such gas property influences on two-phase flow.

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Laboratory Measurement of Two-Phase Flow Parameters in Rock Joints Based on High Pressure Triaxial Testing

Journal of Geotechnical and Geoenvironmental Engineering ◽

10.1061/(asce)1090-0241(2001)127:6(530) ◽

2001 ◽

Vol 127 (6) ◽

pp. 530-542 ◽

Cited By ~ 16

Author(s):

B. Indraratna ◽

P. G. Ranjith

Keyword(s):

High Pressure ◽

Two Phase Flow ◽

Rock Joints ◽

Laboratory Measurement ◽

Triaxial Testing ◽

Phase Flow ◽

Two Phase ◽

Flow Parameters

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Measurement of Two-Dimensional Void Fraction Distributions of Rising Bubbles in a Simulated Sub-Channel by Wire-Mesh Sensors at Conditions of Forced Convective and Stagnant Flows

Volume 9: Student Paper Competition ◽

10.1115/icone25-67895 ◽

2017 ◽

Author(s):

Yota Suzuki ◽

Yusei Tanaka ◽

Taku Sakka ◽

Akinori Sato ◽

Kazuyuki Takase ◽

...

Keyword(s):

Flow Condition ◽

Two Phase Flow ◽

Flow Behavior ◽

Wire Mesh ◽

Phase Flow ◽

Two Dimensional ◽

Two Phase ◽

Fuel Rods ◽

Fuel Rod ◽

Stagnant Flow

Clarifying thermal-hydraulic characteristics in a nuclear reactor core is important in particular to enhance the thermo-fluid safety of nuclear reactors. Spacers installed in subchannels of fuel assemblies have the role of keeping the interval between adjacent fuel rods constantly. Similarly, in case of PWR the spacer has also the role as the turbulence promoter. When the transient event occurs, two-phase flow is generated by boiling of water due to heating of fuel rods. Therefore, it is important to confirm the two-phase flow behavior around the spacer. So, the effect of the spacer affecting the two-phase flow was investigated experimentally at forced convective flow condition. Furthermore, in order to improve the thermal safety of current light water reactors, it is necessary to clarify the two-phase flow behavior in the subchannels at the stagnant flow condition. So, the bubbly flow data around a simulated fuel rod were obtained experimentally at the stagnant flow condition. A wire-mesh sensor was used to obtain a detailed two-dimensional void fraction distribution around the simulated spacer and fuel rod. As a result of this research, the bubbly behavior around the simulated spacer and fuel rod was qualitatively revealed and also bubble dynamics in the sub-channels at the conditions of forced convective and stagnant flows were evaluated. The present experimental data are very useful for verifying the detailed three-dimensional two-phase flow analysis codes.

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