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Archive | 2014

Flow Characteristics and Void Fraction Prediction in Large Diameter Pipes

Xiuzhong Shen; Joshua P. Schlegel; Shao-Wen Chen; Somboon Rassame; Matthew Griffiths; Takashi Hibiki; Mamoru Ishii

Two phase flows in large diameter pipes have immense importance in a wide variety of industrial applications. As a first approximation for the prediction of a two-phase flow and as a beginning for the development of more complex models, the drift-flux model is often used to characterize and predict flows for many geometries and flow conditions. In this chapter, the flow characteristics in flows in large diameter pipes are illustrated based on the experimental data. The flow regimes and their transition criteria are discussed. The existing drift-flux models are summarized, their strengths and weaknesses are noted and the data that can be used to evaluate these models are presented. Based on the flow regime transitions in large diameter pipes, all of the available drift-flux models are evaluated systematically in both low (bubbly) and high (cap and churn-turbulent) void fraction flows. The drift-flux type correlations of Hibiki and Ishii [14] and Kataoka and Ishii [24] are found to be able to give the best predictions for the existing low and high void fraction databases respectively and are recommended for void fraction predictions in flows in large diameter pipes.


Journal of Nuclear Science and Technology | 2014

Upward air–water bubbly flow characteristics in a vertical square duct

Haomin Sun; Tomoaki Kunugi; Xiuzhong Shen; DaZhuan Wu; Hideo Nakamura

In nuclear engineering fields, gas–liquid bubbly flows exist in channels with various shape and size cross-sections. Although many experiments have been carried out especially in circular pipes, those in a noncircular duct are very limited. To contribute to the development of gas–liquid bubbly flow model for a noncircular duct, detail measurements for the air–water bubbly flow in a square duct (side length: 0.136 m) were carried out by an X-type hot-film anemometry and a multi-sensor optical probe. Local flow parameters of the void fraction, bubble diameter, bubble frequency, axial liquid velocity and turbulent kinetic energy were measured in 11 two-phase flow conditions. These flow conditions covered bubbly flow with the area-averaged void fraction ranging from 0.069 to 0.172. A pronounced corner peak of the void fraction was observed in a quarter square area of a measuring cross-section. Due to a high bubble concentration in the corner, the maximum values of both axial liquid velocity and turbulent kinetic energy intensity were located in the corner region. It was pointed out that an effect of the corner on accumulating bubble in the corner region changed the distributions of axial liquid velocity and turbulent kinetic energy intensity significantly.


Journal of Nuclear Science and Technology | 2017

Prediction of interfacial area transport in a coupled two-fluid model computation

Joshua P. Schlegel; Takashi Hibiki; Xiuzhong Shen; Santosh Appathurai; Hariprasad J. Subramani

ABSTRACT A computer code has been written to predict interfacial area transport within the framework of the two-fluid model. The suitability of various constitutive models was evaluated from a scientific and numerical standpoint, and selected models were used to close the two-fluid model. The resulting system was then used to optimize the empirical constants in the interfacial area transport equation for large diameter pipes. The optimized model was evaluated based on comparison with the data of Shen et al. and Schlegel et al. The optimization shows agreement with previous research conducted by Dave et al. and Talley et al. using TRACE-T, and reduced the RMS error in the interfacial area concentration prediction for the large diameter pipe data from 52.3% to 34.9%. The results also highlight a need for additional high-resolution data at multiple axial locations to provide a more detailed picture of the axial development of the flow. The results also indicate a need for improved modeling of the interfacial drag, especially for Taylor cap bubbles under relatively low void fraction conditions.


Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles | 2012

Gas-Liquid Bubbly Turbulent Upward Flow in Square Duct

Haomin Sun; Tomoaki Kunugi; DaZhuan Wu; Hongna Zhang; Hideo Nakamura; Xiuzhong Shen

As for the turbulent two-phase flow in the non-circular duct, the flow could show an anisotropic turbulence feature in liquid phase. In this study, the air-water bubbly turbulent upward flow experiment in the large square duct with the inside cross-section of 136mm×136mm has been conducted. Since the bubble size is very important for air-water bubbly flows, the bubble generating method was improved to get more uniform bubble size. After confirming the flow symmetry in the measuring cross-section, the distributions of local void fraction, bubble frequency and primary liquid velocity were measured by a hot-film anemometry, and the bubble behaviors were also investigated by using the high-speed video camera. The results show that the bubbles tend to accumulate to the wall region, where the liquid primary velocity shows the maximum especially at the corner.Copyright


Water Science and Technology | 2015

CFD simulation of an unbaffled stirred tank reactor driven by a magnetic rod: assessment of turbulence models.

Jiajia Li; Baoqing Deng; Bing Zhang; Xiuzhong Shen; Chang Nyung Kim

A simulation of an unbaffled stirred tank reactor driven by a magnetic stirring rod was carried out in a moving reference frame. The free surface of unbaffled stirred tank was captured by Euler-Euler model coupled with the volume of fluid (VOF) method. The re-normalization group (RNG) k-ɛ model, large eddy simulation (LES) model and detached eddy simulation (DES) model were evaluated for simulating the flow field in the stirred tank. All turbulence models can reproduce the tangential velocity in an unbaffled stirred tank with a rotational speed of 150 rpm, 250 rpm and 400 rpm, respectively. Radial velocity is underpredicted by the three models. LES model and RNG k-ɛ model predict the better tangential velocity and axial velocity, respectively. RNG k-ɛ model is recommended for the simulation of the flow in an unbaffled stirred tank with magnetic rod due to its computational effort.


14th International Conference on Nuclear Engineering | 2006

Methodology of Local Instantaneous Interfacial Velocity Measurement in Multi-Dimensional Two-Phase Flow

Xiuzhong Shen; Kaichiro Mishima; Hideo Nakamura

Since the transport of momentum, heat and mass tightly links with local interfacial characteristics it is essential to know the local interfacial parameters in various two-phase flows. The interfacial velocity plays a determinant role in determining the other interfacial parameters such as the interfacial area concentration and so on. It is accordingly one of the most important parameters in analyzing two-phase flow. However, it also is one of the most difficult parameters to measure up to now. Based on the application of the interfacial measurement theorem to several four-sensor probes, the present study established a theoretical foundation of the measurement method for the local instantaneous interfacial velocity in multidimensional two-phase flow by using three independent four-sensor probes. Since we can find three independent four-sensor probes in a multi-sensor probe, which has more than four sensors, by sharing the sensors of the first four-sensor probe with the sensors of the others, a five- or six-sensor probe including at least one set of three four-sensor combinations was recommended to measure the local instantaneous interfacial velocity, interfacial area concentration and so on in multidimensional two-phase flow. A six-sensor probe was developed and employed in the practical measurement in an air-water multi-dimensional two-phase flow in a pool. The six-sensor probe measurements were checked against the gas flow rate measurement using a rotameter and a manometer. The comparing results were very satisfactory.Copyright


International Journal of Heat and Mass Transfer | 2005

Two-phase phase distribution in a vertical large diameter pipe

Xiuzhong Shen; Kaichiro Mishima; Hideo Nakamura


International Journal of Multiphase Flow | 2005

Methodological improvement of an intrusive four-sensor probe for the multi-dimensional two-phase flow measurement

Xiuzhong Shen; Yasushi Saito; Kaichiro Mishima; Hideo Nakamura


Experimental Thermal and Fluid Science | 2006

A study on the characteristics of upward air–water two-phase flow in a large diameter pipe

Xiuzhong Shen; Yasushi Saito; Kaichiro Mishima; Hideo Nakamura


International Journal of Heat and Fluid Flow | 2012

Developing structure of two-phase flow in a large diameter pipe at low liquid flow rate

Xiuzhong Shen; Takashi Hibiki; Hideo Nakamura

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Hideo Nakamura

Japan Atomic Energy Research Institute

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Baoqing Deng

University of Shanghai for Science and Technology

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Joshua P. Schlegel

Missouri University of Science and Technology

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