• Title/Summary/Keyword: Saturated Boiling

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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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Critical Heat Flux of an Impinging Water Jet on a Heated Surface with Boiling (비등을 수반하는 발열면에 충돌하는 수분류의 임계열유속에 관한 연구)

  • Lee, Jong-Su;Kim, Heuy-Dong;Choi, Kuk-Kwang
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.24 no.4
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    • pp.485-494
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    • 2000
  • The purpose of this paper is to investigate a critical heat flux(CHF) during forced convective subcooled and saturated boiling in free water jet system impinged on a rectangular heated surface. The surface is supplied with subcooled or saturated water through a rectangular jet. Experimental parameters studied are a width of heated surface, a height of supplementary water and a degree of subcooling. Incipient boiling point is observed in the temperature of 6${\~}8^{\circ}C$ of superheat of test specimen. CHF depends on jet velocity for various boiling-involved coolant system. CHF also is proportional to the nozzle exit velocity to the power of n, where n is 0.55 and 0.8 for subcooled and saturated boiling, respectively. CHF is enhanced with a higher jet velocity, higher degree of subcooling and smaller width of a heated surface.

A Study on Saturated Boiling Heat Transfer in Upward Rectangular Impinging Water Jet System (연직상향(鉛直上向) 사각충돌수분류(四角衝突水噴流)의 포화비등 열전달에 관한 연구)

  • Lee, J.S.;Ohm, K.C.;Seo, J.Y.
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.3 no.5
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    • pp.395-403
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    • 1991
  • The purpose of this investigation was to characterize nucleate boiling and burn-out heat flux for rectangular free jet with saturated water impinging perpendicularly and upward against a flat uniform heat flux surface. Heat flux measured for Reynolds number based on rectangular nozzle width and for aspect ratio. The result of nucleate boiling heat transfer was presented nondimensional experimental equation including Nusselt, Boiling, Subcooling, Reynolds and Weber number. The effect of aspect ratio of heated surface in the burn-out heat flux had not appeared distinctly. But for the same aspect ratio, burn-out heat flux increased linearly with increment of nozzle exit velocity.

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Mechanisms of Convective and Boiling Heat Transfer Enhancement via Ultrasonic Vibration (초음파 진동에 의한 대류 및 비등 열전달 촉진 원리에 관한 연구)

  • Kim, Yi-Gu;Kim, Ho-Young;Kang, Seoung-Min;Kang, Byung-ha;Lee, Jin-Ho
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.27 no.5
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    • pp.612-619
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    • 2003
  • This work experimentally studies the fundamental mechanisms by which the ultrasonic vibration enhances convection and pool boiling heat transfer. A thin platinum wire is used as both a heat source and a temperature sensor. A high speed video imaging system is employed to observe the behavior of cavitation and thermal bubbles. It is found that when the liquid temperature is below its boiling point, cavitation takes place due to ultrasonic vibration while cavitation disappears when the liquid reaches the boiling point. Moreover, when the gas dissolved in liquid is removed by pre-degassing, the cavitation arises only locally. Depending on the liquid temperature, heat transfer rates in convection, subcooled boiling and saturated boiling regimes are examined. In convection heat transfer regime, fully agitated cavitation is the most efficient heat transfer enhancement mechanism. Subcooled boiling is most enhanced when tile local cavitation is induced after degassing. In saturated boiling regime, acoustic pressure is shown to be a dominant heat transfer enhancement mechanism.

An Experimental Study on Heat Transfer Coefficients just before Critical Heat Flux Conditions in Uniformly Heated Vertical Annulus (균일 가열 수직 환상관에서 임계열유속조건 직전의 열전달계수에 관한 실험적 연구)

  • Chun, Se-Young;Lim, Chang-Ha;Moon, Sang-Ki;Chung, Moon-Ki;Choi, Young-Don
    • Proceedings of the KSME Conference
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    • 2001.11b
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    • pp.330-336
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    • 2001
  • Water heat transfer experiments were carried out in a uniformly heated annulus with a wide range of pressure conditions. The local heat transfer coefficients for saturated water flow boiling have been measured just before the occurrence of the critical heat flux (CHF) along the length of the heated section. The trends of the measured heat transfer coefficients were quite different from the conventional understanding for the heat transfer of saturated flow boiling. This discrepancy was explained from the nucleate boiling in the liquid film of annular flow under high heat flux conditions.

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An Experimental Study on Heat Transfer Characteristics Just Before Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures

  • Chun, Se-Young;Moon, Sang-Ki;Chung, Heung-June;Chung, Moon-Ki
    • Nuclear Engineering and Technology
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    • v.34 no.4
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    • pp.269-285
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    • 2002
  • Water heat transfer experiments were carried out in a uniformly heated annulus with a wide range of pressure conditions. The local heat transfer coefficients for saturated water (low boiling have been measured just before the occurrence of the critical heat flux (CHF) along the length of the heated section. The trends of the measured heat transfer coefficients were quite different from the conventional understanding for the heat transfer of saturated flow boiling. This discrepancy was explained from the nucleate boiling in the liquid film of annular flow under high heat flux conditions. The well-known correlations were compared with the measured heat transfer coefficients. The Shah and Kandlikar correlations gave better prediction than the Chen correlation. However, the modified Chen correlation proposed in the present work showed the best agreement with the present data among correlations examined .

Study on the Single Bubble Growth During Nucleate Boiling at Saturated Pool (포화상태 풀비등시 단일기포의 성장에 관한 연구)

  • Kim Jeongbae;Lee Han Choon;Oh Byung Do;Kim Moo Hwan
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.29 no.2 s.233
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    • pp.169-179
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    • 2005
  • Nucleate boiling experiments on heating surface of constant wall temperature were performed using R113 for almost saturated pool boiling conditions. A microscale heater array and Wheatstone bridge circuits were used to maintain a constant wall temperature condition of heating surface and to measure the heat flow rate with high temporal and spatial resolutions. Bubble images during the bubble growth were taken as 5000 frames per second using a high-speed CCD camera synchronized with the heat flow rate measurements. The bubble growth behavior was analyzed using the new dimensionless parameters for each growth regions to permit comparisons with previous experimental results at the same scale. We found that the new dimensionless parameters can describe the whole growth region as initial and later (thermal) respectively. The comparisons showed good agreement in the initial and thermal growth regions. In the initial growth region including surface tension controlled, transition and inertia controlled regions as divided by Robinson and Judd, the bubble growth rate showed that the bubble radius was proportional to $t^{2/3}$ regardless of working fluids and heating conditions. And in the thermal growth region as also called asymptotic region, the bubble showed a growth rate that was proportional to $t^{1/5}$, also. Those growth rates were slower than the growth rates proposed in previous analytical analyses. The required heat flow rate for the volume change of the observed bubble was estimated to be larger than the heat flow rate measured at the wall. Heat, which is different from the instantaneous heat supplied through the heating wall, can be estimated as being transferred through the interface between bubble and liquid even with saturated pool condition. This phenomenon under a saturated pool condition needs to be analyzed and the data from this study can supply the good experimental data with the precise boundary condition (constant wall temperature).

Study on the single bubble growth at saturated pool boiling (포화상태 풀비등시 단일기포의 성장에 관한 연구)

  • Kim, Jeong-Bae;Lee, Han-Choon;Oh, Byung-Do;Kim, Moo-Hwan
    • Proceedings of the KSME Conference
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    • 2004.04a
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    • pp.1933-1938
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    • 2004
  • Nucleate boiling experiments with constant wall temperature of heating surface were performed using R113 for almost saturated pool boiling conditions. A microscale heater array and Wheatstone bridge circuits were used to maintain a constant wall temperature condition and to measure the heat flow rate with high temporal and spatial resolutions. Bubble images during the bubble growth were taken as 5000 frames a sec using a high-speed CCD camera synchronized with the heat flow rate measurements. The geometry of the bubble during growth time could be obtained from the captured bubble images. The bubble growth behavior was analyzed using the new dimensionless parameters for each growth regions to permit comparisons with previous results at the same scale. We found that the new dimensionless parameters can describe the whole growth region as initial and later respectively. The comparisons showed good agreement in the initial and thermal growth regions. The required heat flow rate for the volume change of the observed bubble was estimated to be larger than the instantaneous heat flow rate measured at the wall. Heat, which is different from the instantaneous heat supplied through the heating wall, can be estimated as being transferred through the interface between bubble and liquid even with saturated pool conditions. This phenomenon under a saturated pool condition needs to be analyzed and the data from this study can supply the good experimental data with the precise boundary condition (constant wall temperature).

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Enhanced Boiling Heat Transfer of Water Using Multi-Stage Electroplating Technique (전기 다단 도금법을 이용한 물의 핵비등열전달 촉진 실험)

  • Cho, Dae-Gwan;You, Seung-Mun;Lee, Joon-Sik
    • Proceedings of the KSME Conference
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    • 2003.04a
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    • pp.1590-1596
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    • 2003
  • The experiments of boiling heat transfer were performed to investigate the boiling enhancement in saturated water by using multi-stage electroplated surface. In order to optimize the boiling performance, current flux and duration in multi-stage electroplating were varied. Current flux, 2 $A/12cm^2$ and 0.33 $A/cm^2$, and duration ranging from 15 second to 50 second are considered. The results showed that multi-stage electro plated surfaces generate enhancement of boiling parameters such as boiling incipient superheat, boiling heat transfer coefficient, and critical heat flux compared to plain surface. The SEM images of the coated surfaces were captured to examine the structure of porous surface, which provides the enhancement of boiling heat transfer.

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Experimental Study on Single Bubble Growth Under Subcooled, Saturated, and Superheated Nucleate Pool Boiling

  • Kim Jeong-Bae;Lee Jang-Ho;Kim Moo-Hwan
    • Journal of Mechanical Science and Technology
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    • v.20 no.5
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    • pp.692-709
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    • 2006
  • Nucleate pool boiling experiments with constant wall temperature were performed using pure R1l3 for subcooled, saturated, and superheated pool conditions. A microscale heater array and Wheatstone bridge circuits were used to maintain the constant wall temperature and to measure the instantaneous heat flow rate accurately with high temporal and spatial resolutions. Images of bubble growth were taken at 5,000 frames per second using a high-speed CCD camera synchronized with the heat flow rate measurements. The bubble geometry was obtained from the captured bubble images. The effect of the pool conditions on the bubble growth behavior was analyzed using dimensionless parameters for the initial and thermal growth regions. The effect of the pool conditions on the heat flow rate behavior was also examined. This study will provide good experimental data with precise constant wall temperature boundary condition for such works.