• Transactions of the Korean Society of Mechanical Engineers B
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• v.36 no.1
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• pp.83-88
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• 2012

Real slug and bubbly flows were measured using a three-ring impedance meter that can efficiently measure the void fraction of two-phase flows in a tube. First, the fitting curves between the signal from the impedance meters and the void fraction were found. The impedance meter had different fitting curves for slug and bubbly flows that had the same void fraction. An impedance meter should choose one of the two fitting curves according to the flow pattern, and the flow patterns can be recognized using the measured void fraction. The velocities and sizes of the bubbles were calculated using the void fraction curves measured by two impedance meters.

• Journal of the Korean Society of Visualization
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• v.16 no.1
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• pp.37-41
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• 2018

The two-fluid model is widely used for practical applications involving multi-phase flows in chemical reactor, nuclear reactor, desalination systems, boilers, and internal combustion engine. There are several modeling terms in the two-fluid model, which must be determined properly. This study suggests the best models for turbulent vertical bubbly flow.

• Journal of Energy Engineering
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• v.25 no.1
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• pp.69-75
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• 2016

Bubble size is a key parameter for an accurate prediction of bubble behaviours in the multi-dimensional two-phase flow. In the current STAR CCM+ CFD code, a mechanistic bubble size model $S{\gamma}$ is available for the prediction of bubble size in the flow channel. As another model, Yun model is developed based on DEBORA that is subcooled boiling data in high pressure. In this study, numerical simulation for the gas-liquid two-phase flow was conducted to validate and confirm the performance of $S{\gamma}$ model and Yun model, using the commercial CFD code STAR CCM+ ver. 10.02. For this, local bubble models was evaluated against the air-water data from DEDALE experiments (1995) and Hibiki et al. (2001) in the vertical pipe. All numerical results of $S{\gamma}$ model predicted reasonably the two-phase flow parameters and Yun model is needed to be improved for the prediction of air-water flow under low pressure condition.

• Nuclear Engineering and Technology
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• v.27 no.6
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• pp.918-931
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• 1995

임계열속을 예측하는 기존의 여러 방법중 임계열속 발생 역학구조에 근거한 이론적 접근 방법은 여러 유동형태(Flow pattern)별로 연구되고 있으며, 대표적으로 환상유동에서의 LFD(Liquid Film Dryout) 이론, 기포류에서의 BBLD(Bubble Boundary Layer Dryout) 흑은 LNID(Local Nucleation Initiated Dryout)이론 등이 제시되고 있다. 본 논문에서는 일반적으로 원자로 조건에 서 적용될 수 있는 LFD이론과 BBLD 이론에 대하여 대표적인 모델들을 소개하고 특성을 검토하였다. 특히 BBLD 이론중에서 기포군집 (Bubble coalescence) 모델과 층류막 드라이 아웃(Sublayer dryout) 모델에 대해서는 원형관에서의 임계열속 시험자료를 사용하여 각 모델의 예측 성능 및 특성을 평가하였다. 평가 결과, 기포군집 모형인 Weisman 모델의 예측성능이 가장 우수했으며 아울러 층류막 드라이아웃 모델인 Katto 모델과 Mudawwar 모델은 구성 인자중 기포군속도와 층류막 두께와의 관계가 보다 정확히 모형화되야 할 것으로 판단된다.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.34 no.5
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• pp.471-479
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• 2010

The adiabatic two-phase flow in single rectangular microchannels was studied for different aspect ratios. The working fluids were liquid water and nitrogen gas. The hydraulic diameters of the rectangular microchannels were 490, 322, and $143\;{\mu}m$, and the widths of the microchannels were around $500\;{\mu}m$. The two-phase flow pattern was visualized using a high-speed camera and a long-distance microscope. This study was focused on bubble flow regimes. From the visualized images, the bubble velocity, bubble length, number of bubbles, and void fraction were evaluated. Further, the pressure drop in a single bubble was evaluated by using a unit cell model. The bubble velocity is proportional to the superficial velocity. Further, the relationship between the void fraction and the volumetric quality is linear. The pressure drop in a single elongated bubble is strongly related to the aspect ratio. Finally, the new correlation about the pressure drop of a single elongated bubble in the rectangular microchannel was proposed.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.24 no.6
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• pp.886-893
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• 2000

The Characteristics of dividing the dispersed bubble, plug, and slug steam-water flow in the horizontal junctions with horizontal branches have been experimentally investigated. The experimental investigation of the separation phenomena in a $45^{\circ}$ horizontal wye with equal pipe inner diameter of 25 mm is presented to provide a data base for the development and verification of the analytical models. The phase separation and pressure distribution in the three legs of each test section are obtained through the set of measurements made in the present work. And the dependence of phase separation on different parameters, such as inlet quality and mass flux, is discussed.

• Journal of the Korean Society of Visualization
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• v.15 no.3
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• pp.20-26
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• 2017

The two-fluid equations are widely used to simulate two-phase flows in a nuclear reactor. For the two-fluid momentum equation, the wall and interfacial drag terms play an important role in predicting a two-phase flow behavior. Since the bubble density is much smaller than the water density, the bubble accelerates faster than the liquid in a nozzle. As a result, the bubble phase becomes faster than the liquid phase in the nozzle. In contrast, the opposite phenomena occur in the diffuser. The purpose of our study is to experimentally show these behaviors in an area-varying channel such as nozzle and diffuser. Experiments were made of turbulent bubbly flows in an area-varying horizontal channel. The velocities of the bubble and liquid phases were measured by the PIV technique. It was shown that the two-phase velocities were no longer close to each other in the area-varying regions. The bubble was faster than the liquid in the nozzle; in contrast, the bubble was slower than the liquid in the diffuser. Code simulations were also performed using the MARS code. By replacing the original wall drag model in the MARS code with Kim (1)'s wall drag partition model, we obtained the simulation results being consistent with experimental observations.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05a
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• pp.342-349
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• 1997

국내 원자력발전소의 참조격인 영광 3ㆍ4호기의 RCP를 1/10으로 축소한 모델펌프를 설계ㆍ제작하여 상온, 대기압에서 단상류 펌프특성과 포화상태 근방에서 공동현상 시발 과냉각온도($\Delta$T$_{sub}$ ) 실험을 수행하였다. 단상류 특성은 RCP와 유사하였고, 공동현상 시발 $\Delta$T$_{sub}$ 는 0~5$^{\circ}C$였으며, 압력에 따라 민감하였다. 공동현상의 무차원 변수는 Ca=(equation omitted)로 정의된다. 단상류 펌프특성과 이상류 펌프특성간의 상관관계인 수두손실비 H$^{*}$ (equation omitted)를 기포율($\alpha$)와 유량계수(ø)의 함수로 나타낼 수 있을 것이다.

• Proceedings of the KSME Conference
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• 2004.11a
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• pp.1617-1622
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• 2004

Two-phase flow of liquid and gas through pipe lines are frequently encountered in nuclear power plant or industrial facility. Pressure waves which can be generated by a valve operation or any other cause in pipe lines propagate through the two-phase flow, often leading to severe noise and vibration problems or fatigue failure of pipe line system. It is of practical importance to predict the propagation characteristics of the pressure waves for the safety design for the pipe line. In the present study, a theoretical analysis is performed to understand the propagation characteristics of a weak shock wave in a bubbly flow. A wave equation is developed using a small perturbation method to analyze the weak shock wave through a bubbly flow with comparably low void fractions. It is known that the elasticity of pipe and void fraction significantly affect the propagation speed of shock wave, but the frequency of relaxation oscillation which is generated behind the shock wave is not strongly influenced by the elasticity of pipe. The present analytical results are in close agreement with existing experimental data.

• The Magazine of the Society of Air-Conditioning and Refrigerating Engineers of Korea
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• v.9 no.1
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• pp.13-23
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• 1980

sing the physical characteristics of nuclear radiation penerated into the cross section of the measurement of void fraction in saturated vapor & water passing through the is analyzed theoretically and the solutions are achieved by means of computer simulation. These theoretical results are also approved through the experiment with the simulators.