• Title/Summary/Keyword: Two-phase Nozzle

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Mass Transfer Characteristics of Vertical Two-Phase Flows with Orifice Nozzle (오리피스 노즐 수직 2 상 유동의 물질전달 특성)

  • Kim, Dong Jun;Yang, Hei Cheon
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.39 no.10
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    • pp.817-824
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    • 2015
  • Experiments were carried out to investigate the flow and mass transfer characteristics of an orifice nozzle. Measurements of primary and suction flow rates, dissolved oxygen concentration, and electric power were obtained. Vertically injected mixed-jet images were captured by a direct visualization technique with a high speed camera unit. The mass ratio, volumetric mass transfer coefficient, and mass transfer performance were calculated using the measured data. As the primary flow pressure increases, the mass ratio decreases slightly, while the volumetric mass transfer coefficient and electric power increase. As the primary flow pressure increases and the mass ratio decreases, the mass transfer rate increases because of the fine bubbles and wider distribution of the bubbles.

CFD simulation of a prefilming air blast fuel nozzle (Prefilming air blast 연료 노즐의 다상유동 및 반응 유동장 수치해석)

  • Jung, Seungchai;Kim, Shaun;Park, Heeho;Ryu, Shiyang
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2017.05a
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    • pp.251-253
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    • 2017
  • Numerical study of air-blast type injector for low emission aircraft engines was conducted. Volume-of-fluids approach was used to track interface of fuel and air. Primary atomization of fuel stream was visualized, and thickness and mean velocity at the injector exit was calculated. Liquid fuel injected from fuel slots joined together as a thin film on preflimer surface, and interacted with swirling air. As instability on the fuel surface increased, separation of fuel as ligaments and droplets occured. The film thickness and velocity were used to as fuel injection boundary condition for reactive flow simulation. Primary reaction zone was formed in vicinity of the fuel nozzle, creating a stable flame inside the combustor.

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Experimental study on two-phase flow behavior inside a vertical tube evaporator under flashing phenomenon (후래시 현상을 수반하는 수직증발관내에서의 2상유동에 관한 실험적 연구)

  • 이상용;송시홍;이상호
    • Transactions of the Korean Society of Mechanical Engineers
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    • v.12 no.4
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    • pp.833-846
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    • 1988
  • Two-phase flow heat transfer phenomena with flash evaporation inside a vertical tube were studied experimentally. Void fractions were measured using electrical probes, and the flow patterns were identified from the output voltage signal itself. The flow pattern as well as the beat transfer rates were changing along the axial distance from the tube inlet with the system pressure. As the pressure inside the tube decreases with fixed inlet temperature, the overall heat transfer coefficient through the tube wall and the boiling heat transfer coefficient inside the tube increase whereas the condensation heat transfer coefficient outside the tube decreases. The boiling heat transfer coefficient inside the tube measured by the experiments appeared to be somewhat larger than the value obtained from the Chen's correlation. Also, the flow patterns identified from present experiments are at the larger quality region of the low pattern map based on the transition criteria of Mishima and Ishii. This may be due to the non-equilibrium flashing phenomenon occurred at the nozzle exit and the tube inlet ; this also implies that the flow pattern of the two-phase flow depends strongly on the inlet conditions.

Measurement of Bubble Diameter and Rising Velocity in a Cylindrical Tank using an Optical Fiber Probe and a High Speed Visualization Technique (광섬유 탐침과 고속가시화 기법을 이용한 원형탱크 내부의 기포직경 및 상승속도 측정)

  • Kim, Gyurak;Choi, Seong Whan;Kim, Yoon Kee;Kim, Kyung Chun
    • Journal of the Korean Society of Visualization
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    • v.10 no.2
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    • pp.14-19
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    • 2012
  • An optical fiber probe system for measuring the local void fraction in the air-water two-phase flow was developed with a 1550 nm light source. Air was injected through a nozzle placed in the center of the bottom wall of a water-filled cylindrical tank. The optical fiber probe having a diameter of $125{\mu}m$ was sufficiently thin to resolve the air-water interface of the bubbly flows. To verify the performance of the optical fiber probe, the synchronized high speed visualization study using a high speed camera was carried out. Comparison between the optical signals and the instantaneous bubble diffraction images confirms that the optical fiber probe is very accurate to measure the void fraction in two-phase flows. The estimated bubble diameter and the rising velocity by the optical fiber probe have 1% and 5% of accuracy, respectively.

A PROPOSED CORRELATION FOR CRITICAL FLOW RATE OF WATER FLOW

  • KIM, YEON-SIK
    • Nuclear Engineering and Technology
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    • v.47 no.1
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    • pp.135-138
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    • 2015
  • A new correlation predicting the idealized critical mass-flow rates of water for subcooled and saturated liquid water including two-phase water flow was developed for a wide range of upstream stagnation pressures (e.g., 0.5-20.0 MPa). A choking correction factor dependent on the upstream stagnation pressure and subcooled temperature was introduced into a new correlation, and its values were suggested to satisfy the idealized nozzle data within 10% error ranges. The suggested correlation will be instructive and helpful for related studies and/or engineering works.

A Study on the Relief of Shell Wall Thinning of High pressure Feedwater Heater (고압형 급수가열기 동체 감육 완화에 관한 연구)

  • Kim, Hyung-Joon;Park, Sang-Hoon;Seo, Hyuk-Ki;Kim, Kyung-Hoon;Hwang, Kyung-Mo
    • Proceedings of the KSME Conference
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    • 2008.11b
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    • pp.2664-2669
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    • 2008
  • Feedwater heaters of many nuclear power plants have recently experienced severe wall thinning damange, which will increase as operating time progresses. Several nuclear power plants in Korea have experienced wall thinning damage in the area around the impingement baffle-installed downstream of the high pressure turbine extraction stream line- inside number 5A and 5B feedwater heaters. At that point, the extracted steam from the high pressure turbine is two phase fluid at high temperature, high pressure, and high speed. Since it flows in reverse direction after impinging the impingement baffle, the shell wall of the number 5 high pressure feedwater heater may be affected by flow-accelerated corrosion. This paper describes operation of experience and numerical analysis composed similar condition with real high pressure feedwater heater. This study applied squared, curved and new type impingement baffle plates to feedwater heater same as previous study. In addition, it shows difference of pressure distribution and value between single phase and two phase based on experience and numerical analysis.

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Design Modification and Correlation Verification between Reattachment Flow of Dispersed Jet and Local Thinning of Feedwater Heater (충돌로 인해 분산된 2상 제트스팀의 재부착 현상과 국부 감육 상관관계 규명 및 설계개선에 관한 연구)

  • Kim, Hyung-Joon;Kim, Kyung-Hoon;Hwang, Kyeong-Mo
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.21 no.9
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    • pp.483-495
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    • 2009
  • Feedwater heaters of many nuclear power plants have recently experienced severe wall thinning damange, which will increase as operating time progresses. Several nuclear power plants in Korea have experienced wall thinning damage in the area around the impingement baffle-installed downstream of the high pressure turbine extraction stream line-inside number 5A and 5B feedwater heaters. At that point, the extracted steam from the high pressure turbine is two phase fluid at high temperature, high pressure, and high speed. Since it flows in reverse direction after impinging the impingement baffle, the shell wall of the number 5 high pressure feedwater heater may be affected by flow-accelerated corrosion. This paper describes operation of experience and numerical analysis composed similar condition with real high pressure feedwater heater. This study applied squared, curved and new type impingement baffle plates to feedwater heater same as previous study. In addition, it shows difference of pressure distribution and value between single phase and two phase based on experience and numerical analysis.

Numerical Prediction of Chamber Performance for OWC Wave Energy Converter (OWC 파력발전장치의 공기실 성능예측에 대한 수치적인 연구)

  • Jin, Ji-Yuan;Hyun, Beom-Soo;Liu, Zhen;Hong, Key-Yong
    • Journal of the Korean Society for Marine Environment & Energy
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    • v.13 no.2
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    • pp.91-98
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    • 2010
  • The water elevation inside the air chamber and bi-directional air flow in the duct of Oscillating Water Column wave energy converter is one of the most important factors to evaluate the operating performance. The numerical wave tank based on the commercial software Fluent 6.2 in the present paper is employed to generate the incident waves. The numerical wave tank consists of the continuity equations, the Reynolds-averaged Navier-Stokes equations and the two-phase VOF function. The oscillating amplitude of water column in the chamber and bi-directional air flow in the duct installed on the top of the chamber are calculated, and compared with experimental data to verify the validation of the present NWT. The nozzle effects of the chamber-duct system on the relative amplitudes of the inner free water surface and air flow rate in the duct are investigated.

Analytical Methods of Leakage Rate Estimation from a Containment tinder a LOCA (냉각수상실 사고시 격납용기로부터 누출되는 유체유량 추산을 위한 해석적 방법)

  • Moon-Hyun Chun
    • Nuclear Engineering and Technology
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    • v.13 no.3
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    • pp.121-129
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    • 1981
  • Three most outstanding maximum flow rate formulas are identified from many existing models. Outlines of the three limiting mass flow rate models are given along with computational procedures to estimate approximate amount of fission products released from a containment to environment for a given characteristic hole size for containment-isolation failure and containment pressure and temperature under a loss of coolant accident. Sample calculations are performed using the critical ideal gas flow rate model and the Moody's graphs for the maximum two-phase flow rates, and the results are compared with the values obtained from the mass leakage rate formula of CONTEMPT-LT code for converging nozzle and sonic flow. It is shown that the critical ideal gas flow rate formula gives almost comparable results as one can obtain from the Moody's model. It is also found that a more conservative approach to estimate leakage rate from a containment under a LOCA is to use the maximum ideal gas flow rate equation rather than tile mass leakage rate formula of CONTEMPT-LT.

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ANALYSIS ON STEAM CONDENSING FLOW USING NON-EQUILIBRIUM WET-STEAM MODEL (비평형 습증기 모델을 적용한 증기 응축 유동 해석)

  • Kim, C.H.;Park, J.H.;Ko, D.G.;Kim, D.I.;Kim, Y.S.;Baek, J.H.
    • Journal of computational fluids engineering
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    • v.20 no.3
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    • pp.1-7
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    • 2015
  • When the steam is used as working fluid in fluid machinery, different from other gases as air, phase transition (steam condensation) can occur and it affects not only the flow fields, but also machine performance & efficiency. Therefore, considering phase transition phenomena in CFD calculation is required to achieve accurate prediction of steam flow and non-equilibrium wet-steam model is needed to simulate realistic steam condensing flow. In this research, non-equilibrium wet-steam model is implemented on in-house code(T-Flow), the flow fields including phase transition phenomena in convergent-divergent nozzle are studied and compared to results of advance researches.