• 제목/요약/키워드: Nucleate boiling heat transfer coefficient

검색결과 64건 처리시간 0.022초

수평단관 상의 유하액막 열전달 (Falling Film Heat Transfer on a Horizontal Single Tube)

  • 김동관;김무환
    • 설비공학논문집
    • /
    • 제12권7호
    • /
    • pp.642-648
    • /
    • 2000
  • Falling film heat transfer analyses with aqueous lithium bromide solution were peformed to investigate the transfer characteristics of the copper tubes. Finned(knurled) tube and a smooth tube were selected as test specimens. Averaged generation fluxes of water and the heat transfer performances(heat flux, heat transfer coefficient) were obtained. The results of this work were compared with the data reported previously. As the film flow rate of the solution increased, the generation fluxes of water decreased for both tubes. The reason is estimated by the fact that the heat transfer resistance with the film thickness increased as the film flow rate increased. The effect of the enlarged surface area at the knurled tube was supposed to be dominant at a small flow rate. The generation fluxes of water increased with the increasing degree of tube wall superheat. Nucleate boiling is supposed to occur at a wall superheat of 20 K for a smooth tube, and at 10 K for a knurled tube. The heat transfer performance of the falling film was superior to pool boiling at a low wall superheat below 10 K for both tubes tested. The knurled tube geometry showed good performance than the smooth tube, and the increased performance was mainly came from the effect of the increased heating surface area.

  • PDF

내경 4.57mm 관내 CO2의 증발 열전달 특성 (Evaporation Heat Transfer Characteristics of Carbon Dioxide in a Diameter Tube of 4.57mm)

  • 손창효
    • 한국산학기술학회논문지
    • /
    • 제9권3호
    • /
    • pp.574-579
    • /
    • 2008
  • 수평관내 $CO_2$의 증발 열전달 계수를 실험적으로 조사하였다. 냉매 순환루프의 주요 구성품은 수액기, 변속냉매 펌프, 질량 유량계, 예열기, 증발기(시험부)로 구성된다. 시험부는 내경 4.57 mm의 수평 평활 스텐레스관이다. 실험은 질량유속 $400{\sim}900kg/m^2s$, 포화온도 $5{\sim}20^{\circ}C$, 열유속 $10{\sim}40kW/m^2$인 조건에서 수행하였다. 실험결과로부터 $CO_2$의 열전달은 대류비등보다는 핵비등에 더 많은 영향을 받는 것을 알 수 있었고, $CO_2$의 질량유속은 핵비등에 많은 영향을 미치지 않는 것으로 나타났다. 실험결과와 종래의 상관식을 비교해 본 결과, 기존의 상관식은 실험데이터를 과소예측하였지만, 정 등의 상관식은 좋은 일치를 보였다. 따라서, 수평관내 $CO_2$의 증발 열전달 계수를 예측할 수 있는 정확한 상관식의 개발이 필요하리라 판단된다.

와이어붙이관의 핵비등 열전달촉진 (Enhancement of Nucleate Pool Boiling of a Wire-Wrapped Tube)

  • 김내현;김정식;남기일
    • 대한기계학회논문집
    • /
    • 제18권5호
    • /
    • pp.1235-1244
    • /
    • 1994
  • In this study, experimental results of the nucleate boling of wire-wrapped tubes are provided. Both water and R-113 were boiled. Solid stainless steel wires, stranded copper wires and stranded nylon wires were tested. Solid stainless wire is effective to enhance the boiling of water. The performance is approximately the same(or slightly better at certain conditions) as that of GEWA-T tubes. For the test range of wire diameter 0.6 $mm{\le}d{\le}2.6 mm$, the optimum gap width increases as the wire diameter increases. The maximum heat transfer coefficient was obtained for the 1.0 mm diameter wire, and it is 1.6 times larger than that of the GEWA-T at the heat flux of 20 $kW/m^{2}.$ Solid stainless wire is also effective to enhance the boling of R-113 at low heat fluxes. The performance of the wire-wrapped tube approaches that of GEWA-T. At high heat fluxes, however, the enhancement decreases. The reason may be attributed to the cavity shape and the high wettability of the refrigerants. Stranded copper or nylon wire is effective to enhance the boiling of R-113. The performance is approximately the same(or slightly better) as that of GEWA-T tubes. Maximum heat transfer was obtained for the stranded nylon wire, and it is approximately 1.4 times larger than that for the GEWA-T at the heat flux of 20 $kW/m^{2}.$ The reason may be atrributed to the favorable thermal environment in the restricted regions formed by twisted wires.

수평원관내 $CO_2$의 증발열전달 (Evaporation Heat Transfer of Carbon Dioxide in a horizontal Round Tube)

  • 경남수;장승일;최선묵;손창효;오후규
    • 대한설비공학회:학술대회논문집
    • /
    • 대한설비공학회 2005년도 동계학술발표대회 논문집
    • /
    • pp.262-267
    • /
    • 2005
  • The evaporation heat transfer coefficient of $CO_2$ in a horizontal round tube was investigated experimentally. The experiments were conducted without oil in a closed refrigerant loop which was driven by a magnetic gear pump. The main components of the refrigerant loop are a receiver, a variable-speed pump, a mass flow meter, a pre-heater and evaporator(test section). The test section was made of a horizontal stainless steel tube with the inner diameter of 7.75 mm, and length of 5 m. The experiments were conducted at mass flux of 200 to 500 $kg/m^2s$, saturation temperature of $-5^{\circ}C$ to $5^{\circ}C$, and heat flux of 10 to 40 $kW/m^2$. The test results showed the evaporation heat transfer of $CO_2$ has great effect on more nucleate boiling than convective boiling. The evaporation heat transfer coefficients of $CO_2$ are highly dependent on the vapor quality, heat flux and saturation temperature. In comparison with teat results and existing correlations, correlations failed to predict the evaporation heat transfer coefficient of $CO_2$, therefore, it is necessary to develop reliable and accurate predictions determining the evaporation heat transfer coefficient of $CO_2$ in a horizontal tube.

  • PDF

세관내 이산화탄소의 증발 열전달 및 압력강화 (Evaporation Heat Transfer and Pressure Drop of $CO_2$ in a Small diameter Tube)

  • 장승일;최선묵;김대희;박기원;오후규
    • 한국마린엔지니어링학회:학술대회논문집
    • /
    • 한국마린엔지니어링학회 2005년도 전기학술대회논문집
    • /
    • pp.189-194
    • /
    • 2005
  • The evaporation heat transfer and pressure drop of $CO_2$ in a small diameter tube was investigated experimentally. The experiments were conducted without oil in a closed refrigerant loop which was driven by a magnetic gear pump. The main components of the refrigerant loop are a receiver, a variable-speed pump, a mass flow meter, a pre-heater and evaporator(test section). The test section was made of a horizontal stainless steel tube with the inner diameter of 4.57 mm, and length of 4 m. The experiments were conducted at mass flux of 200 to 700 $kg/m^2s$, saturation temperature of $0^{\circ}C$ to $20^{\circ}C$, and heat flux of 10 to 20 $kW/m^2$ . The test results showed the evaporation heat transfer of $CO_2$ has great effect on more nucleate boiling than convective boiling. The evaporation heat transfer coefficients of $CO_2$ are highly dependent on the vapor quality, heat flux and saturation temperature. The evaporation pressure drop of C02 are highly dependent on the mass flux. In comparison with test results and existing correlations, correlations failed to predict the evaporation heat transfer coefficient and pressure drop of $CO_2$, therefore, it is necessary to develop reliable and accurate predictions determining the evaporation heat transfer coefficient and friction pressure drop of $CO_2$ in a horizontal tube.

  • PDF

A Dry-Spot Model for the Prediction of Critical Heat Flux in Water Boiling in Bubbly Flow Regime

  • Ha, Sang-Jun;No, Hee-Cheon
    • 한국원자력학회:학술대회논문집
    • /
    • 한국원자력학회 1997년도 추계학술발표회논문집(1)
    • /
    • pp.546-551
    • /
    • 1997
  • This paper presents a prediction of critical heat flux (CHF) in bubbly flow regime using dry-spot model proposed recently by authors for pool and flow boiling CHF and existing correlations for forced convective heat transfer coefficient, active site density and bubble departure diameter in nucleate boiling region. Without any empirical constants always present in earlier models, comparisons of the model predictions with experimental data for upward flow of water in vertical, uniformly-heated round tubes are performed and show a good agreement. The parametric trends of CHF have been explored with respect to variations in pressure, tube diameter and length, mass flux and inlet subcooling.

  • PDF

강재 열처리용 다점 열유속 측정 기술 개발 (Development of Multi-point Heat Flux Measurement for Steel Quenching)

  • 이정호;오동욱;도규형;김태훈
    • 열처리공학회지
    • /
    • 제25권4호
    • /
    • pp.181-189
    • /
    • 2012
  • The demand on quantitative measurement of the heat flux is motivated in making higher-quality steel product through a water quenching process of plate mill. To improve a spatial degree of heat flux measurement, the multi-point heat flux measurement was carried out by a unique experimental technique that has a combination of the existing single-point heat flux gauge. The corresponding heat flux can be easily determined by Fourier's law in a conventional way. The multi-point heat flux gauge developed in this study can be applicable to measure the surface heat flux, the surface heat transfer coefficient during a water quenching applications of steelmaking process. The results exhibit different heat transfer regimes; such as single-phase forced convection, nucleate boiling, and film boiling, that are occurred in close proximity on the multi-point heat flux gauge quenched by water impinging jet.

수평 평활관내 $CO_2$ 증발열전달 및 압력강하에 관한 연구 (Study on $CO_2$ Evaporation Heat Transfer and Pressure Drop in a Horizontal Smooth Tube)

  • 이상재;최준영;이재헌;권영철
    • 설비공학논문집
    • /
    • 제19권9호
    • /
    • pp.615-621
    • /
    • 2007
  • Experimental study on the heat transfer characteristics of $CO_2$ in a horizontal smooth tube was carried out to investigate the heat transfer coefficient and pressure drop during evaporation of $CO_2$. The experiment apparatus consisted of a test section, a DC power supply, a heater, a chiller, a mass flow meter, a pump and a measurement system. Experiment was conducted for various mass fluxes ($200{\sim}1200kg/m^2s$), heat flukes ($10{\sim}100kW/m^2$) and saturation temperatures (-5, 0, $5^{\circ}C$). With increasing the heat flux, the evaporation heat transfer coefficient increased. But the variation of the heat transfer coefficient on the increase of the mass flux was not large. And the significantly drops of the heat transfer coefficient was observed at any heat flux and mass flux because of the change of the flow pattern in the tube. With increasing the saturation temperature, the heat transfer coefficient increased due to the promotion of a nucleate boiling. The measured pressure drop during evaporation increased with increasing the mass flux and decreasing the saturation temperature.

마이크로관 내 증발열전달에 관한 연구 (A Study on the Evaporative Heat Transfer in Microtubes)

  • 황윤욱;김주혁;김민수
    • 설비공학논문집
    • /
    • 제17권12호
    • /
    • pp.1113-1122
    • /
    • 2005
  • The experimental heat transfer coefficients have been measured for two-phase convective boiling in two circular microtubes with inner diameters of $430{\mu}m\;and\;792{\mu}m$. While the heat transfer was greatly affected by the heat flux in the low quality region, the mass flux played a role in the high quality region. The smaller microtube had greater heat transfer coefficients. When the heat flux is varied from $20kW/m^2\;to\;30kW/m^2\;at\;G=240kg/m^2s$, the difference between the average heat transfer coefficients of the test tube $A(D_i=430{\mu}m)$ and the test tube $B(D_i=792{\mu}m)$ changes from $32.5\%\;to\;52.1\%$. At $G=370kg/m2^s$, the difference between the average heat transfer coefficients changes from $47.0\%\;to\;53.8\%$. A new correlation for the evaporative heat transfer coefficients in microtubes was developed by considering the following factors; the laminar flow heat transfer coefficient of liquid-phase flow, the enhancement factor of the convective heat transfer, and the nucleate boiling correction factor. The correlation developed in this study predicts the experimental heat transfer coefficients within an absolute average deviation of $8.4\%$.

Perfluorocarbon 히트파이프의 열전달 계수에 관한 연구 (A Study on Heat Transfer Coefficient of a Perfluorocarbon Heat Pipe)

  • 강환국;김철주;김재진
    • 에너지공학
    • /
    • 제7권2호
    • /
    • pp.194-201
    • /
    • 1998
  • 전기 철도 차량의 A.C 모터 속도제어에는 여러 개의 GTO thyristor와 다이오드가 필요하다. 그런데 이러한 반도체 소자들은 약 1~2 kW의 열을 발생하기 때문에 냉각장치가 필요하며 이러한 반도체의 냉각에는 Perfluorocarbon(PFC)을 작동유체로 하는 히트파이프를 많이 사용하고 있다. 본 연구에서는 PFC 히트파이프의 증발 및 응축 열전달 계수에 미치는 관련변수로 주입율, 관의 내부 표면상태, 경사각, 증기압, 열유속 등의 영향을 파악하고, 열전달 계수를 예측할 수 있는 상관식을 제시하고자 하였다. 이를 위해 내부 표면에 그루브가 설치된 동관과 표면이 매끈한 외경 15.88mm인 동관을 이용하여 주입율이 다른 총 길이 520mm의 PFC 히트파이프와 열사이폰을 제작하고 실험을 수행하였다. 증발 열전달 계수는 열유속 15~45 kW/$m^2$의 범위일 때 2 kW/$m^2$K~5.5 kW/$m^2$K 사이의 분포를 보였다. 실험결과는 수정계수 CR=1.3을 적용할 때 Rohsenow의 핵비등 상관식과 실험치가 매우 접근된 결과를 보였으며 이러한 결과는 내부 벽면 그루브의 열전달 촉진효과이다. 응축 열전달 계수의 측정치는 1.5kW/$m^2$K~3.5kW/$m^2$K 사이의 분포를 보였으며 Nusselt 막응축 모델에 수정계수 CN=4를 도입함으로써 매우 접근된 예측이 가능하였다. 증발부 체적에 대한 작동유체 주입율은 40~100%의 범위가 적절하였다. 그리고 30$^{\circ}$이상의 경사각에서는 경사각의 영향이 미소하였다.

  • PDF