• 제목/요약/키워드: Nucleate Boiling Heat Transfer

검색결과 142건 처리시간 0.025초

절삭유 냉각용 낮은 핀관의 응축 및 비등 열전달 성능에 관한 연구 (A Study on the Performance of the Condensation and the Boiling Heat Transfer of Low Fin Tubes Used in Cooling of the Cutting Oil)

  • 이종선
    • 한국생산제조학회지
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    • 제8권4호
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    • pp.68-78
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    • 1999
  • Heat transfer performance is studied for boiling and condensation of R-11 on integral-fin tubes. Nine tubes with trapezoidal integral-fins having fin densities from 748 to 1654fpm and 10,30 grooves and finned tubes with caves of 0.55 and 0.64 mm height respectively are tested. in case of condensation CFC-11 condensates at saturation stat of 32$^{\circ}C$ on the outside surface cooled by inside cooling water flows. And in case of boiling the refrigerant evaporates at a saturation state of 1 bar on the outside tube surface and heat is supplied by hot water which circulates inside of the tube,. The tube having fin transfer coefficient concerns fin tubes with caves show higher valve than low fin tube having find density of 1299fpm and 30grooves. The overall heat transfer coefficient of fin tube with caves is about 5155 W/mK at 2.8m/s of water velocity, The value is abuot 2.7 times higher than plain tube and 1.3 times higher than low fin tube having fin density of 1299fpm and 30 grooves.

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

  • 서만수;이지성;김정한;강선일
    • 한국추진공학회지
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    • 제24권3호
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    • pp.59-70
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    • 2020
  • 본 논문에서는 기존 적층형 배관의 총 열전달 계수 경험식을 활용할 때 발생하는 한계점을 해결하고자, 외부 총 열전달 계수의 강제 대류 열전달 계수 항을 독립적으로 도출하는 간소화된 모델링을 제안하고, 이를 극저온 환경의 실험 결과로 확인하였다. 액체 산소 냉각 나선형 열교환기가 액체 질소와 열교환하는 실험 장치를 구성하고 열교환기의 열전달량을 계측하여, 외부 총 열전달 계수를 도출하였다. 측정된 외부 총 열전달 계수가 모델링으로 예측 곡선과 일치함을 확인하였다.

마이크로 휜 표면의 분무냉각 열전달에 관한 실험적 연구 (Experimental Study on Spray Cooling Heat Transfer of Micro-Fins Surfaces)

  • 김영찬
    • 한국분무공학회지
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    • 제14권4호
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    • pp.178-183
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    • 2009
  • Spray cooling heat transfer was experimentally investigated for water sprays impacting on mico-fins structured surfaces in the single phase and nucleate boiling regions. The heat transfer surfaces consist of cubic fins and triangular grooved fins. The spray produced using full cone spray nozzles, and experiments were made under the test condition of $Q=4.92{\times}10^{-6}{\sim}15.83{\times}10^{-6}\;m^3/s$, $T_f=35{\sim}55^{\circ}C$. From the experimental results, it was found that cubic fins surface had the largest heat flux enhancement relative to the smooth surface.

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Thermoexcel-E 촉진 표면에서 임계 열유속까지의 풀 비등 열전달계수 (Pool Boiling Heat Transfer Coefficients Up to Critical Heat flux on Thermoexcel-E Enhanced Surface)

  • 이요한;강동규;장철한;정동수
    • 설비공학논문집
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    • 제24권9호
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    • pp.685-692
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    • 2012
  • In this work, nucleate pool boiling heat transfer coefficients(HTCs) of 5 refrigerants of different vapor pressure are measured on horizontal Thermoexcel-E square surface of 9.53 mm length. Tested refrigerants are R32, R22, R134a, R152a and R245fa. HTCs are taken from 10 $kW/m^2$ to critical heat fluxes for all refrigerant at $7^{\circ}C$. Wall and fluid temperatures are measured directly by thermocouples located underneath the test surface and in the liquid pool. Test results show that critical heat fluxes(CHFs) of Thermoexcel-E enhanced surface are greatly improved as compared to that of a plain surface in all tested refrigerants. CHFs of all refrigerants on the Thermoexcel-E surface are increased up to 100% as compared to that of the plain surface. The improvement of Thermoexcel-E surface in CHF, however, is lower than that of the low fin surface. HTCs on Thermoexcel-E surface increase with heat flux. But after certain heat flux, HTCs began to decrease due to the difficulty in bubble removal caused by the inherent complex nature of this surface. Therefore, at heat fluxes close to the critical one, sudden decrease in HTCs needs to be considered in thermal design with Thermoexcel-E surface.

공작기계 절삭유 냉각용 낮은 핀관의 열전달 성능에 관한 연구 (A Study on the Performance of Heat Transfer of Low Fin Tubes Used in Cooling of the Cutting Oil of the Machine Tool)

  • 조동현
    • 한국공작기계학회:학술대회논문집
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    • 한국공작기계학회 1998년도 추계학술대회 논문집
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    • pp.125-133
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    • 1998
  • Nine tubes with trapezoidal integral-fins having fin densities from 748 to 1654fpm and 10,30 grooves and finned tubes with caves of 0.55 and 0.64mm height respectively are tested. A plain tube having same diameter as the finned tubes is also tested for comparison. In case of condensation CFC-11 condensates at saturation state of 32$^{\circ}C$ on the outside surface cooled by inside cooling water flows. And in case of boiling the refrigerant evaporates at a saturation state of 1bar on the outside tube surface and heat is supplied by hot water which circulates inside of the tube. The tube having fin density of 1299fpm and 30grooves has the best condensation overall heat transfer coefficient. However, as far as boiling heat transfer coefficient concerns, fin tubes with cave show higher value than low fin tube having fin density of 1299fpm and 30 grooves.

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수평 전열관내 비공비 혼합냉매 R134a/R123의 강제대류비등 열전달에 관한 연구 (A Study on Forced Convective Boiling Heat Transfer of Non-Azeotropic Refrigerant Mixture R134a/R123 Inside Horizontal Smooth Tube)

  • 임태우;한규일
    • 대한기계학회논문집B
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    • 제27권3호
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    • pp.381-388
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    • 2003
  • An experimental study was carried out to measure the heat transfer coefficient in flow boiling to mixtures of HFC-l34a and HCFC-123 in a uniformly heated horizontal tube. Tests were run at a pressure of 0.6 MPa and in the ranges of heat flux 1-50 kw/$m^2$, vapor quality 0-100 % and mass velocity 150-600 kg/$m^2$s. Heat transfer coefficients of mixture were less than the interpolated values between pure fluids both in the low quality region where the nucleate boiling is dominant and in the high quality region where the convective evaporation is dominant. Measured data of heat transfer are compared to a few available correlations proposed for mixtures. The correlation of Jung et. al. satisfactorily predicted the present data, but the data in lower quality was overpredicted and underpredicted the high quality data. The correlation of Kandlikar considerably underpredicted most of the data. and showed the mean deviation of 35.1%.

낮은 핀관에서 대체냉매의 풀비등 열전달계수 (Pool boiling heat transfer coefficients of alternative refrigerants on low fin tubes)

  • 송길홍;이준강;정동수;김종보
    • 설비공학논문집
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    • 제10권4호
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    • pp.411-422
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    • 1998
  • In this study, experiments were carried out to provide nucleate pool boiling heat transfer data for a plain tube and 4 different low fin tubes employing 2 refrigerant mixtures of R410A, R407C, and 12 pure fluids. Low fin tubes were machined on a 19.05mm nominal outside diameter copper block according to the manufacturer's low fin tube specifications. Cartridge heaters were used to generate uniform heat flux on the tubes. For all refrigerants, heat flux varied from 10㎾/$\m^2$ to 80㎾/$\m^2$. It is found that heat transfer coefficients(HTCs) of high vapor pressure refrigerants are usually higher than those of low pressure fluids. On the other hand, the fin effect was more prominent with low pressure refrigerants than with high pressure ones. Optimum fin density as well as the increase in heat transfer coefficient with the increase in fin density were found to be strongly fluid dependent. HTCs of Rl23, a low pressure alternative refrigerant, were similar to those of Rll while HTCs of R134a, an intermediate pressure alternative refrigerant, were roughly 20% higher than those of Rl2. Finally, HTCs of R32, R125, R143a, and R410A were all higher than those of R22 by 30~50%.

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낮은 핀 표면과 Turbo-B 촉진 표면에서 임계 열유속까지의 풀 비등 열전달계수 (Pool Boiling Heat Transfer Coefficients Up to Critical Heat flux on Low-fin and Turbo-B Surfaces)

  • 이요한;정동수
    • 설비공학논문집
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    • 제23권3호
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    • pp.179-187
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    • 2011
  • In this work, nucleate pool boiling heat transfer coefficients(HTCs) of 5 refrigerants of differing vapor pressure are measured on horizontal low fin and Turbo-B square surfaces of 9.53 mm length. Tested refrigerants are R32, R22, R134a, R152a and R245fa and HTCs are taken from 10 $kW/m^2$ to critical heat fluxes for all refrigerant at $7^{\circ}C$. Wall and fluid temperatures are measured directly by thermocouples located underneath the test surface and in the liquid pool. Test results show that Critical heat fluxes(CHFs) of all enhanced surfaces are greatly improved as compared to that of a plain surface in all tested refrigerants. CHFs of all refrigerants on the 26 fpi low fin surface are increased up to 240% as compared to that of the plain surface. HTCs on both low fin and Turbo-B surfaces increase with heat flux. After certain heat flux, however, they decrease. CHFs of the Turbo-B enhanced surface are lower than that of the 26 fpi low fin surface. This phenomenon is due to the difference in surface structure of the low fin and Turbo-B surface.

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

  • 정승혁;정샛별;김형대
    • 대한기계학회논문집B
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    • 제39권6호
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    • pp.519-526
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    • 2015
  • 본 연구에서는 핵비등 시 미세액막층의 증발에 의한 열유속과 열전달률 계산을 위한 simple microlayer model 의 물리적 변수들을 측정하기 위하여 미세액막층의 형상을 실험적으로 조사하였다. 레이저를 이용한 전반사 및 간섭 기법을 이용하여 simple microlayer model 을 구성하는 인자들인 미세액막층의 초기 두께 및 수평 이동속도를 측정하였다. 대기압 포화상태의 물을 이용하여 수평 벽면에서 단일기포 핵비등 실험을 수행하였고, 평균 열유속 $200kW/m^2$ 조건에서 동일한 위치에서 발생하는 기포들의 미세액막층의 구조적 특성을 분석하였다. 본 연구의 범위에서 측정한 미세액막층의 최대 초기 두께는 $5.4{\mu}m$ 이었으며, 증발에 의한 미세액막층의 수평 이동속도는 0.12 m/s 이었다.

Power upgrading of WWR-S research reactor using plate-type fuel elements part I: Steady-state thermal-hydraulic analysis (forced convection cooling mode)

  • Alyan, Adel;El-Koliel, Moustafa S.
    • Nuclear Engineering and Technology
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    • 제52권7호
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    • pp.1417-1428
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    • 2020
  • The design of a nuclear reactor core requires basic thermal-hydraulic information concerning the heat transfer regime at which onset of nucleate boiling (ONB) will occur, the pressure drop and flow rate through the reactor core, the temperature and power distributions in the reactor core, the departure from nucleate boiling (DNB), the condition for onset of flow instability (OFI), in addition to, the critical velocity beyond which the fuel elements will collapse. These values depend on coolant velocity, fuel element geometry, inlet temperature, flow direction and water column above the top of the reactor core. Enough safety margins to ONB, DNB and OFI must-emphasized. A heat transfer package is used for calculating convection heat transfer coefficient in single phase turbulent, transition and laminar regimes. The main objective of this paper is to study the possibility of power upgrading of WWR-S research reactor from 2 to 10 MWth. This study presents a one-dimensional mathematical model (axial direction) for steady-state thermal-hydraulic design and analysis of the upgraded WWR-S reactor in which two types of plate fuel elements are employed. FOR-CONV computer program is developed for the needs of the power upgrading of WWR-S reactor up to 10 MWth.