• 대한기계학회논문집B
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• 제34권11호
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• pp.983-990
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• 2010

본 연구에서는 냉각면의 표면온도가 비교적 낮은 강제대류 및 핵비등영역에서 다양한 종류의 마이크로 휜이 가공된 냉각면의 분무냉각 열전달에 대해 실험적으로 연구하였다. 실험결과로부터 냉각면 표면에 가공된 마이크로 휜은 분무냉각 열전달을 촉진시키며, 냉각휜의 크기와 종류에 상관없이 분무유량이 증가할수록 분무냉각 열전달도 큰 폭으로 증가하고 있음을 알 수 있었다. 또한 희박한 분무영역에서는 냉각면에 가공된 휜의 크기와 형상이 분무냉각 열전달에 큰 영향을 미치고 있으나, 분무유량이 증가할수록 이러한 경향은 점차 약해져 본 실험에서 가장 높은 분무유량조건에서는 편평한 냉각면을 제외한 모든 냉각면의 열유속이 거의 동일하게 나타나고 있음을 알 수 있었다.

• 대한기계학회논문집B
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• 제26권11호
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• pp.1513-1520
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• 2002

Effect of Convex Surface Curvature on the Onset of Nucleate Boiling of Subcooled Fluid Flow in Vertical Concentric Annuli An experimental study has been carried out to investigate the effect of the transverse convex surface curvature of core tubes on heat transfer in concentric annular tubes. Water is used as the working fluid. Three annuli having a different radius of the inner cores, Ri=3.18mm, 6.35mm, and 12.70mm with a fixed ratio of Ri/Ro=0.5 are used over a range of the Reynolds number between about 40,000 and 80,000. The inner cores are made of smooth stainless steel tubes and heated electrically to provide constant heat fluxes throughout the whole length of each test section. Experimental result shows that heat flux values on the onset of nucleate boiling of the smaller inner diameter model is much higher than that of the larger size test model.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 추계학술대회논문집B
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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.

• 대한기계학회논문집B
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• 제26권1호
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• pp.116-124
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• 2002

An experimental parametric study of a tubular heat exchanger has been carried out far the saturated water at atmospheric pressure to determine effects of tube inclination on pool boiling heat transfer. For the analysis, seven inclination angles(0°, 15°, 30°, 45°, 60°, 75°, and 90°) and two tube diameters(12.7 and 19.1 mm) were tested. According to the results, inclination angles result in very much change on pool boiling heat transfer. As the inclination angle is around horizontal or vertical, maximum or minimum heat transfer is expected, respectively. For the same wall superheat(about 5.5K) the ratio between two heat fluxes fur $\theta$ =15° and 75° has the value of more than five when the tube diameter is 12.7 mm and heat flux is increasing.

• Design & Manufacturing
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• 제13권1호
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• pp.42-47
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• 2019

Nucleate boiling heat transfer is one of the most important phenomenon in the various industries. Especially, critical heat flux (CHF) refers to the upper limit of the pool boiling heat transfer region. Therefore, many researchers have found that CHF can be significantly increased by adding very small amounts of nanoparticles. In this study, the CHF and heat transfer coefficient were tested under the pool boiling state using copper and multi wall carbon nanotube nanoparticles. The results showed that two different types of nanoparticles deposited on the surface of two specimens made of the same material increased the heat flux in the nanoparticles with high conductivity, and there was no difference in the critical heat flux when the same material nanoparticles were deposited on the two different specimen surfaces.

• 대한기계학회논문집B
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• 제29권5호
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• pp.643-652
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• 2005

Saturated nucleate pool boiling experiments for binary mixtures, which are consisted of refrigerant R11 and R113, were performed with constant wall temperature condition. Results for binary mixtures were also compared with pure fluids. A microscale heater array and Wheatstone bridge circuits were used to maintain the constant temperature of the heating surface and to obtain heat flow rate measurements with high temporal and spatial resolutions. Bubble growth images were captured using a high speed CCD camera synchronized with the heat flow rate measurements. The departure time for binary mixtures was longer than that for pure fluids, and binary mixtures had a higher onset of nucleate boiling (ONB) temperature than pure fluids. In the asymptotic growth region, the bubble growth rate was proportional to a value between $t^{\frac{1}{6}}$ and $t^{\frac{1}{4}}$. The bubble growth behavior was analyzed to permit comparisons with binary mixtures and pure fluids at the same scale using dimensionless parameters. There was no discernable difference in the bubble growth behavior between binary mixtures and pure fluids for a given ONB temperature. And the departure radius and time were well predicted within a ${\pm}30{\%}$ error. The minimum heat transfer coefficient of binary mixtures occurred near the maximum ${\mid}y-x{\mid}$ value, and the average required heat flux during bubble growth did not depend on the mass fraction of R11 as more volatile component in binary mixtures. Finally, the results showed that for binary mixtures, a higher ONB temperature had the greatest effect on reducing the heat transfer coefficient.

• 대한기계학회논문집B
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• 제35권7호
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• pp.665-676
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• 2011

본 연구에서는 순수 물에 탄소나노튜브를 분산시킨 나노유체를 작동유체로 하여 $60^{\circ}C$ 에서 정사각형 구리 평면 히터를 이용하여 핵 비등 열전달계수와 임계 열유속을 측정하였다. 탄소나노튜브의 체적비는 0.0001%, 0.001%, 0.01%까지 변화시켜 실험을 수행하였다. 탄소나노튜브는 고분자 물질을 사용하여 분산시키지 않고 탄소나노튜브에 직접 산화처리를 하여 분산시켰다. 실험 결과 나노유체의 열전달계수는 순수 물과 비교해 모든 체적비에서 증가하였다. 산화 처리를 한 탄소나노튜브는 비등이 일어나는 동안 열 경계층 안에서 열전도도가 큰 탄소나노튜브가 침착되지 않고 열전달 표면에 자주 접촉함으로써 열 경계층을 교란시켜 비등 열전달을 촉진시키는 것으로 사료된다. 임계 열유속은 체적비 0.001%에서 순수 물의 결과에 비해 150%까지 증가하였다. 이는 열전달 표면에서 탄소나노튜브가 매우 얇게 침착되어 생긴 나노 막으로 인해 거대한 기포막의 형성이 억제되고 핵 비등이 높은 열유속에서도 지속되어 임계 열유속이 증가하는 것으로 판단된다.

• 설비공학논문집
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• 제18권12호
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• pp.1017-1024
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• 2006

In this work, pool boiling heat transfer coefficients (HTCs) of five hydrocarbon refrigerants of propylene, propane, isobutane, butane and dimethylether (DME) were measured at the liquid temperature of $7^{\circ}C$ on a 26 fpi low fin tube, Turbo-B, and Thermoexcel-E tubes. All data were taken from 80 to $10kW/m^2$ in the decreasing order of heat flux. The data of hydrocarbon refrigerants showed a typical trend that nucleate boiling HTCs obtained on enhanced tubes also increase with the vapor pressure. Fluids with lower reduced pressure such as DME, isobutane, and butane took more advantage of the heat transfer enhancement mechanism of enhanced tubes than those enhancement ratios of $2.3\sim9.4$ among the tubes tested due to its sub-channels and re-entrant cavities.

• Nuclear Engineering and Technology
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• 제41권10호
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• pp.1285-1292
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• 2009

The effects of the narrowed upside gap on nucleate pool boiling heat transfer in a vertical annulus were investigated experimentally. For the study, a stainless steel tube with a diameter of 25.4 mm and saturated water that kept an atmospheric condition were used. The ratio between the gaps measured at the upper and the lower regions of the annulus ranged from 0.18 to 1. Two different lengths of the modified gap also were investigated. The change in heat transfer due to the modified gap became evident as the gap ratio decreased and the length of the gap increased. As the gap ratio became less than 0.51, a significant decrease in heat transfer was observed compared to the plain annulus. The longer gap size resulted in an additional decrease in heat transfer. The major cause for the tendency was attributed to the formation of lumped bubbles around the upper region of the annulus followed by the increased flow friction between the fluid and the surface around the modified gap.

• 대한기계학회논문집B
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• 제25권3호
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• pp.389-396
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• 2001

Direct numerical simulation of bubble growth and merger process on a single nucleation site during partial nucleate boiling is performed. The equations governing conservation of mass, momentum and energy are solved using a finite difference method combined with a level set method for capturing the vapor-liquid interface. The level set method is modified to include the effects of phase change at the interface and contact angle at the wall. Also, a simplified formulation for predicting the evaporative heat flux in a thin liquid micro-layer is developed and incorporated into the level set formulation. Based on the numerical results, the bubble growth and merger pattern and its effect on the heat transfer are discussed.