• Title/Summary/Keyword: Nucleate boiling heat transfer

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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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Experimental study on nucleate boiling heat transfer enhancement using an electric field (전기장을 이용한 핵비등 열전달 촉진에 관한 실험적 연구)

  • Gwon, Yeong-Cheol;Kim, Mu-Hwan;Gang, In-Sik
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.21 no.12
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    • pp.1563-1575
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    • 1997
  • To understand EHD nucleate boiling heat transfer enhancement, EHD effects on R-113 nucleate boiling heat transfer in a non-uniform electric field were investigated. The pool boiling heat transfer and the dynamic behavior of bubbles in d.c./a.c. electric fields under a saturated or subcooled boiling were studied by using a plate-wire electrode and a high speed camera. From the pool boiling heat transfer study, the shift of the pool boiling curve, the increase of the heat transfer and the delay of ONB and CHF points to higher heat fluxes were observed. From the dynamic behavior of bubbles, it was observed that bubbles departed away from the whole surface of the heated wire in radial direction due to EHD effects by a nonuniform electric field. With increasing applied voltages, the bubble size decreased and the active nucleation site and the departure number of bubbles showed the different trend. The present study indicates that the EHD nucleate boiling heat transfer is closely connection with the dynamic behavior of bubbles and the secondary flow induced near the heated surface. Therefore, the basic studies on the bubble behavior such as bubble frequency, bubble diameter, bubble velocity and flow characteristics are necessary for complete understanding of the enhancement mechanism of the boiling heat transfer using an electric field.

Saturation Boiling Heat Transfer on a Heated Surface With Impinging Water Jet (충돌수분류에 의한 포화비등열전달)

  • Ohm, Ki-Chan;Seo, Jeong-Yun
    • The Magazine of the Society of Air-Conditioning and Refrigerating Engineers of Korea
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    • v.15 no.2
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    • pp.182-187
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    • 1986
  • Experimental measurements of the heat transfer and heat flux to a jet impinging on a heated surface were obtained in the nucleate boiling regimes. Tes-variables were jet at velocity and aspect ratio ($b/\ell$) of the heated surface. A slope of nucleate boiling curve increased with increasing the aspect ratio of the heated surface, namely approaching a rectangular square, and it is shown that surface tension has an important role for the onset of nucleate boiling heat transfer. A generalized correlation of the jet nucleate boiling heat transfer. A generalized correlation of the jet nucleate boiling heat transfer was found using a pi theorem.

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Prediction of Nucleate Pool Boiling Heat Transfer Coefficients of Ternary Refrigerant R407C

  • Kwak, Kyung-Min;Bai, Cheol-Ho;Chung, Mo
    • International Journal of Air-Conditioning and Refrigeration
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    • v.6
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    • pp.93-103
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    • 1998
  • The nucleate boiling heat transfer experiments are performed using a ternary refrigerant R407C which is a candidate of alternatives of HCFC 22. The boiling phenomena of R-32, R-125 and R-134a which are the constituent refrigerants of R407C are also investigated. The nucleate boiling heat transfer coefficients of R407C are less than those of HCFC 22 which have the similar physical and transport properties. In our experimental pressure range, which is similar to the operational pressure of air conditioning system, the deterioration of boiling heat transfer coefficients of mixture refrigerant R407C does not appear for moderate wall superheat region. Since nucleate boiling heat transfer coefficients cannot be obtained from ideal mixing law of mixture, Thome's method was used to predict. To account for the heat flux effect and system pressure in Thome's method, the correcting factor, a(P.L1T), was introduced and obtained from experiments for ternary refrigerant R407C.

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An experimental study on nucleate boiling of ternary refrigerant R407C (삼중 혼합 냉매 R407C의 핵비등 열전달 특성에 관한 실험적 연구)

  • Kim, S.H.;Kwak, K.M.;Bai, C.H.;Chung, M.
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.9 no.3
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    • pp.276-283
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    • 1997
  • The nucleate boiling heat transfer experiments are performed using a ternary refrigerant R407C which is a candidate of alternatives of HCFC 22. The boiling phenomena for R-32, R-125, and R-134a which are the constituent refrigerants of R407C are also investigated to give the foundation of theoretical research for the mixture component boiling. The nucleate boiling heat transfer coefficients of R407C is less than those of HCFC 22 which has the similar physical and transport properties. Since the experimental results show the deterioration of boiling heat transfer coefficients of ternary mixture refrigerants R407C, the boiling heat transfer coefficients of R407C cannot be obtained by the linear combination of boiling heat transfer coefficients from its constituent components R-32, R125, and R134a.

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'The Effect of Heating Surface Conditions on the Nucleate Boiling Heat Transfer' (핵비등열전달에 미치는 전열면표면조건의 영향)

  • Cha J. Y.;Yim C. S.;Seo J. Y.
    • The Magazine of the Society of Air-Conditioning and Refrigerating Engineers of Korea
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    • v.5 no.3
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    • pp.169-177
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    • 1976
  • The importance of surface conditions of nucleate boiling is well recognized and it has been known that the heat transfer to boiling liquid is closely related to the bubble population density. The bubble population density should depend on various factors such as heat flux, surface roughness, surface contamination, properties of liquid, etc. In this paper the effect of surface conditions on heat transfer in nucleate boiling is treated. The experiments were carried out with distilled water boiler, on the horizontal heating surfaces, sintered with various bronze particle, under atmospheric pressure. In addition, experimental investigation for the polished bronze surface was performed. By studing a coefficient Xb defined by eq. (9), which represents the bubble foaming ability of heating surface, generalized fomula on the heat transfer in the nucleate toiling were expressed. The coefficient $X_b$, determined empirically, is not constant and indicates a major influence of the sintered metal surfaces on the $\Delta$, necessary to sustain nucleate boiling at any given heat flux. In this study, the main results are obtained as follows; (1) At low temperature difference, the coefficient $X_b$ of sintered metal surface was found to he higher than the polished surface throughout the full range of experiments. (2) The optimum sintered structure showing the maximum coefficient $X_b$ has been confirmed to exist and it is encountered when particle diameter is $256{\mu}$.

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Coupled CFD-FE Analysis Method for IC Engine Cooling Water Jacket under Subcooled Nucleate Boiling Conditions (핵비등 열전달 효과를 고려한 내연기관 냉각수로의 CFD-FE 연성해석 기법)

  • Lee, Myung-Hoon;Kim, Dong-Kwang;Lee, Sang-Kyoo;Rhim, Dong-Ryul
    • Transactions of the Korean Society of Automotive Engineers
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    • v.14 no.5
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    • pp.9-16
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    • 2006
  • The present study is to simulate coolant flow in IC engine cooling passages under subcooled nucleate boiling conditions and investigate thermal stress analysis of the solid part. To consider nucleate boiling heat transfer effect, Chen's empirical formula is used through user subroutine programing in CFD code and then nucleate boiling model is compared with Robinson's experimental results, which shows reasonable agreement. This Chen's nucleate boiling model is applied to single cylinder IC engine model and we do cylinder liner thermal stress analysis using commercial FEM code.

A New Correlation on Heat Transfer Coefficient in Horizontal Multi Channels (수평 다채널에서의 열전달 계수에 관한 새로운 상관식)

  • CHOI, Yong-Seok;LIM, Tae-Woo
    • Journal of Fisheries and Marine Sciences Education
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    • v.28 no.5
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    • pp.1388-1394
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    • 2016
  • This paper presents a experimental study of two-phase flow boiling of FC-72 in multi channels. Flow boiling heat transfer coefficients are obtained with mass flux ranging from 152.9 to $353.9kg/m^2s$ and heat flux from 5.6 to $46.1kW/m^2$. The experimental results show that the heat transfer is governed by nucleate boiling mechanism in the low heat flux region. However, it is found that the effects of nucleate boiling and forced convection boiling are combined as the heat flux increases. A new correlation to predict the heat transfer coefficient is developed by using the dimensionless number such as Reynolds number, Weber number, boiling number. This correlation shows good predictive accuracy against the measured data.

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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Study on the characteristics of nucleate boiling heat transfer with changing of surface roughness (표면거칠기의 변화에 따른 핵비등열전달의 특성에 관한 연구)

  • 김춘식;정대인;배종욱
    • Journal of Advanced Marine Engineering and Technology
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    • v.7 no.1
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    • pp.64-78
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    • 1983
  • In nucleate boiling, bubbles are created by the expansion of entrapped gas or vapor at small cavities in the surface of heat transfer. Namely, surface roughness is the important factor of heat transfer. This paper deals with the characteristics of boiling curve according to surface roughness. Freon-113 is used as the experimental fluid. The results are as follows; 1. In the case of the same as "q=C$\Delta$T$^{n}$ ", the lower numberical index "n", the larger heat transfer coefficient and the lower wall superheat "$\Delta$T" is obtained for the rougher surface. 2. In the working of every kind of heat transfer sruface with boiling, improvement of capabilities of heat transfer can be devised by adding suitable roughness on the heat transfer surface. 3. When the metal nets of moderate mesh number are established, the capabilities of heat transfer can be improved in evaporation of liquid in vessels. But in the case that the sucession of bubbles in checked by using the nets which are too tight, the generation of bubbles union decreases critical heat flux. decreases critical heat flux.

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