• Title/Summary/Keyword: Boiling Bubble

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Experimental Study on Geometry of a Microlayer During Single-Bubble Nucleate Boiling (단일기포 핵비등 시 미세액막층 구조에 대한 실험적 연구)

  • Jeong, Seunghyuck;Jung, Satbyoul;Kim, Hyungdae
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.39 no.6
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    • pp.519-526
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    • 2015
  • To measure the physical parameters of the simple microlayer model for the prediction of the heat flux and heat transfer rate due to the evaporation of the microlayer during nucleate boiling, the microlayer geometry was experimentally examined. The parameters, including initial thickness, moving velocity and microlayer radius, were measured by total reflection and interferometry techniques using a laser. Single-bubble nucleate boiling experiments were conducted using saturated water on a horizontal surface under atmospheric pressure. The geometric characteristics of the microlayer underneath the bubbles periodically nucleating at a nucleation site at an average heat flux of $200kW/m^2$ were analyzed. The experimental results in the present study show that the maximum initial thickness of the microlayer and the horizontal moving velocity are $5.4{\mu}m$ and 0.12 m/s, respectively.

Two-dimensional Numerical Simulation of the Contact Angle and the Bubble Necking Using the Two Phase Lattice Boltzmann Method (2상 격자 볼츠만 방법을 이용한 접촉각과 Bubble Necking 2차원 수치 모사)

  • Ryu, Seung-Yeob;Kim, Jae-Yong;Ko, Sung-Ho
    • The KSFM Journal of Fluid Machinery
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    • v.14 no.3
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    • pp.10-17
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    • 2011
  • Free energy based lattice Boltzmann method (LBM) has been used to simulate the contact angle and the bubble necking with large density ratio. LBM with the proper contact angle model is able to reduce the spurious currents and eliminate the singularity in the contact lines. The numerical results of the contact angles are satisfied with the Youngs law. For bubble necking flows, simulations are executed for various viscosities and contact angles. The phenomena of the bubble necking are simulated successfully and the subsequent results are presented. The present method is also applicable to the nucleate boiling flows.

An Experimental Study on Direct Cooling Performance using Pool Boiling from Micro-Porous Coated Surface (마이크로다공성 코팅된 발열체에서의 풀비등 직접냉각 성능에 관한 실험적 연구)

  • Kim, Tae-Gyun;Lee, Kyu-Jung;Kim, Yong-Chan;Park, Chan-Sung
    • Proceedings of the KSME Conference
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    • 2004.11a
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    • pp.1353-1358
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    • 2004
  • An experimental study of pool boiling behavior on micro-porous enhanced square heater surfaces immersed in PF5060 is performed. The effects of heater orientation, Subcooling and substrate distance on the pool boiling heat transfer performance for the double heaters were investigated under increasing heat-flux conditions. The boiling performance of micro-porous coated surface was better than that of plain surface. The double heaters with upper substrate of 0.2cm substrate interval have lower boiling performances compared with the results for the double heaters with that of 0.5cm and 1.0cm substrate interval and without the substrate. In comparison to upper heater and below heater with orientation, the upper heater has lower superheat temperature than the below heater due to the bubble sweeping.

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BRIEF REVIEW OF LATEST DIRECT NUMERICAL SIMULATION ON POOL AND FILM BOILING

  • Kunugi, Tomoaki
    • Nuclear Engineering and Technology
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    • v.44 no.8
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    • pp.847-854
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    • 2012
  • Despite extensive research efforts, the mechanism of the nucleate boiling phenomena is still not clear. A direct numerical simulation of the boiling phenomena is one of the promising approaches in order to clarify its heat transfer characteristics and discuss their mechanism. Therefore, many DNS procedures have been developed based on recent highly advancing computer technologies. This brief review focuses on the state of the art in direct numerical simulation of the pool boiling phenomena over the past two decades. In this review, the fundamentals of the boiling phenomena and the bubble departure and micro-layer models are briefly introduced, and then the numerical procedures for tracking or capturing interface/surface shape such as the front tracking method, level set method, volume of fluid treatments, and other methods (Lattice Boltzmann method, phase-field method and so on) are briefly reviewed.

A Visual Study on Nucleate Boiling Phenomena in a Closed Two-Phase Thermosyphon (밀폐형 2상 열사이폰내의 비등현상에 관한 가시화 연구)

  • 강환국;오광헌;김철주;박이동;황영규
    • Proceedings of the Korea Society for Energy Engineering kosee Conference
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    • 1995.05a
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    • pp.185-198
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    • 1995
  • This is an experimental study conducted to visualize the nucleate boiling phenomena and flow regimes occurring inside the liquid pool in a closed two-phase thermosyphon. To meet this purpose, an annular-type thermosyphon was designed and manufactured using a glass tube and a stainless steel tube, being assembled axisymmetrically. The heat to be supplied to the working fluid is generated within a very thin layer of stainless steel tube wall by applying a high frequency electromagnetic field through the induction coil, axisymmetrically set around the evaporator zone. Some important results were as follows ; 1) Considering the structural complexity of the tested thermosyphon, it showed good performance for the range of heat flux 2< q" <25kW/$m^2$ and saturation vapor pressure, 0.1<Pv<1.1bar 2) different type of nucleating boiling regimes were observed as described below, -Pulse boiling regime : Flow pattern changed cyclically with time during 1 cycle of pulse boiling process. The onset of Nucleation was followed by expulsive growing of vapor bubble, resulting in the so called blow-up phenomenon, massive expulsion of large amount of liquid around the bubble. -Transient : Some spherical vapor bobbles were observed growing out from 2~3 nucleating sites, that was dispersed at the lower part of the heated tube wall in the liquid pool. But the rest upper region above the nucleating sites were filled with churns or bubbles of vapor. -Continuous nucleate boiling regime : The whole zone of evaporator was filled with lots of spherical vapor bubbles, and the bubbles showed tendency to decrease in diameter as the heat flux increased.ased.

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Experimental Research of Characteristic of Pool Boiling Heat Transfer of Saturated Liquid Nitrogen with Helical Coil Type Heat Exchanger (나선형 튜브 열교환 방식의 포화 상태 액체질소의 비등열전달 특성에 대한 실험적 연구)

  • Seo, Mansu;Lee, Jisung;Kim, Junghan;Kang, Sunil
    • Journal of the Korean Society of Propulsion Engineers
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    • v.24 no.3
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    • pp.59-70
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    • 2020
  • Obtaining external forced convection heat transfer from bubble boiling and validating it with experimental results using cryogenic liquids are suggested to derive total heat transfer coefficient with pool boiling condition in the case of coil type heat exchanger with a bundle of tubes and to overcome the limitation of using the empirical correlation. Experiment is conducted with pool boiling heat transfer of saturate liquid nitrogen with helical coil type heat exchanger using liquid oxygen as hot stream fluid. Experimentally measured heat transfer coefficient is well-agreed with the estimated curve considering nucleate boiling and forced convection induced by bubble rise.

MECHANISM OF NUCLEATE BOILING HEAT TRANSFER FROM WIRES IMMERSED IN SATURATED FC-72 AND WATER (전열면적 및 유체의 종류가 핵비등 열전달에 미치는 영향과 그 원인)

  • Kim, J.H.;You, S.M.;Park, J.Y.
    • Proceedings of the KSME Conference
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    • 2001.06d
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    • pp.232-239
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    • 2001
  • The present study is an experimental investigation of nucleate boiling heat transfer mechanism in pool boiling from wire heaters immersed in saturated FC-72 coolant and water. The vapor volume flow rate departing from a wire during nucleate boiling was determined by measuring the volume of bubbles, varying $25{\mu}m,\;75{\mu}m,\;and\;390{\mu}m$, from a wire utilizing the consecutive-photo method. The effects of the wire size on heat transfer mechanism during a nucleate boiling were investigated by measuring vapor volume flow rate and the frequency of bubbles departing from a wire immersed in saturated FC-72. One wire diameter of $390{\mu}m$ was selected and tested in saturated water to investigate the fluid effect on the nucleate boiling heat transfer mechanism. Results of the study showed that an increase in nucleate boiling heat transfer coefficients with reductions in wire diameter was related to the decreased latent heat contribution. The latent heat contribution of boiling heat transfer for the water test was found to be higher than that of FC-72. The frequency of departing bubbles was correlated as a function of bubble diameters.

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Numerical Study of Bubble Growth in a Microchannel (미세관에서의 기포성장에 관한 수치적 연구)

  • Seo, Ki-Chel;Son, Gi-Hun
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.28 no.8 s.227
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    • pp.996-1003
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    • 2004
  • The bubble motion during nucleate boiling in a microchannel is investigated by numerically solving the equations governing conservation of mass, momentum and energy in the liquid and vapor phases. The liquid-vapor interface is tracked by a level set method which is modified to include the effects of phase change at the interface and contact angle at the wall. Also, the evaporative heat flux from the thin liquid film that forms underneath a growing bubble attached to the wall is incorporated in the analysis. Based on the numerical results, the effects of channel size, contact angle, wall superheat and waiting period on the bubble growth and heat transfer in a microchannel are quantified.

An Experimental visualization of the Pool Boiling Heat Transfer on the Inclined square surface (경사진 가열면에서의 수조비등에 대한 가시화 연구)

  • Kim, J.K.;Song, J.H.;Kim, S.B.;Kim, H.D.
    • Proceedings of the KSME Conference
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    • 2001.06e
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    • pp.63-68
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    • 2001
  • An experimental study was carried out to identify the various regimes of natural convective boiling and to determine the Critical Heat Flux(CHF) on a 70mm square surface which is inclined at $180^{\circ}$(upward), $90^{\circ}, \;45^{\circ}$. The heater block made of copper with cartridge heaters is submerged in a water tank with windows for visualization. As the heat flux increases from $100kW/m^2$ to $1.1MW/m^2$, the heat transfer regime migrates from the nucleate boiling to film boiling and results in a rapid heat up of the heater block. An explosive vapor generation on the heated surface, whose size and frequency are characterized by the heat flux, is visualized by using a digital camcorder with $512{\times}512$ pixel size at 30fps.

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Transition mechanism during the critical heat flux condition in flow and pool boiling (유동 및 풀비등에 있어서 한계열플럭스 상태하의 천이기구)

  • 김경근;김명환;권형정;김종헌;최순호
    • Journal of Advanced Marine Engineering and Technology
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    • v.13 no.4
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    • pp.40-53
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    • 1989
  • Boiling heat transfer phenomena is widely applied to BWR and electrical heating system because of its high heat transfer coefficient. In these systems, steady state heat transfer is dependent on nucleate boiling. When the heat generating rate is sharply increased or the cooling capacity of coolant is sharply decreased, sharp wall temperature rise is occurred under the critical heat flux(CHF) condition. This paper presents the simple wall temperature fluctuation model of transition mechanism in the repeating process of overheating and quenching, when coalescent bubble passes relatively slowly on the wall and simultaneously the transition from nucleate boiling to film boiling is carried at especially onset of the CHF state. The values calculated by the present model are resulted comparatively good with the measured.

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