• 제목/요약/키워드: Nucleate Boiling Heat Transfer

검색결과 142건 처리시간 0.022초

충돌과냉수분류(衝突過冷水噴流)의 비등열전달(沸騰熱傳達)에 관한 연구(硏究) (A Study on Boiling Heat Transfer in a Impinging Subcooled Water Jet System)

  • 이강진;이종수;엄기찬;조용철;서정윤
    • 설비공학논문집
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    • 제5권1호
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    • pp.10-17
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    • 1993
  • This paper describes the boiling heat transfer phenomena to be divided into three regions, nonboiling, nucleate boiling and burn-out in the impinging subcooled water jet system. In the nonboiling region, Nusselt number is a function of Prandtl number, Reynolds number and ${\Delta}T_{sub}/T_{ast}$ In the nucleate boiling region, the heat flux increases with increment of the nozzle exit velocity. But the degree of liquid subcooling does not affect the shape of the nucleate boilng curve. The dimensionless correlations can be expressed in the form of $q{\ell}/K_f{\Delta}T_{ast}=C(Bo{\cdot}C_p{\cdot}{\Delta}T_{sat}/Vo^2)^m{\cdot}(Re/We)^n$. The burn-out heat flux increases linearly with increment of the nozzle exit velocity, but independs of degree of subcooling and the supplementary water height.

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평판 표면에서 HFC32/HFC152a 혼합냉매의 풀 비등 열전달계수 (Pool Boiling Heat Transfer Coefficient of HFC32/HFC152a on a Plain Surface)

  • 강동규;이요한;정동수
    • 설비공학논문집
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    • 제25권9호
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    • pp.484-492
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    • 2013
  • Nucleate pool boiling heat transfer coefficients (HTCs) are measured with HFC32/HFC152a mixture at several compositions. All data are taken at the liquid pool temperature of $7^{\circ}C$, on a horizontal plain square surface of $9.53{\times}9.53$ mm, with heat fluxes of 10 $kW/m^2$ to 100 $kW/m^2$ with an interval of 10 $kW/m^2$, in the increasing order of heat flux. Test results show that the HTCs of these mixtures are up to 45% lower than those of the ideal HTCs calculated by a linear mixing rule with pure fluids' HTCs, due to the mass transfer resistance associated with non-azeotropic refrigerant mixtures. Pool boiling data show the deduction in HTCs with an increase in GTD of the mixture. The present mixture data agree well with five well known correlations, within 20% deviation.

수평관내 이산화탄소의 증발 열전달 특성 (Evaporative Heat Transfer Characteristics of Carbon Dioxide in a Horizontal Tube)

  • 손창효;이동건;김영률;오후규
    • 설비공학논문집
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    • 제16권12호
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    • pp.1134-1139
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    • 2004
  • The evaporative heat transfer coefficient of $CO_2$ (R-744) in a horizontal 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 consists of a smooth, horizontal stainless steel tube of inner diameter of 7.75 mm. The experiments were conducted at mass flux of 200 to 500 kg/m$^2$s, saturation temperature of -5 to 5$^{\circ}C$, and heat flux of 10 to 40kW/m$^2$. The test results showed the heat transfer of $CO_2$ has a greater effect on nucleate boiling more than convective boiling. Mass flux of $CO_2$ does not affect nucleate boiling too much, and the effect of mass flux on evaporative heat transfer of $CO_2$ is much smaller than that of refrigerant R-22 and R-134a. In comparison with test results and existing correlations, correlations failed to predict the evaporative heat transfer coefficient of $CO_2$, therefore, it is necessary to develope reliable and accurate predictions determining the evaporative heat transfer coefficient of $CO_2$ in a horizontal tube.

미세 원형 충돌수제트의 부분 대류비등에 있어서 자유표면/잠입 제트의 국소 열전달 특성 (Local Heat Transfer Characteristics in Convective Partial Boiling by Impingement of Free-Surface/Submerged Circular Water Jets)

  • 조형희;우성제;신창환
    • 설비공학논문집
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    • 제14권6호
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    • pp.441-449
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    • 2002
  • Single-phase convection and partial nucleate boiling in free-surface and submerged jet impingements of subcooled water ejected through a 2-mm-diameter circular pipe nozzle were investigated by local measurements. Effects of jet velocity and nozzle-to-imping-ing surface distance as well as heat flux on distributions of wall temperature and heat transfer coefficients were considered. Incipience of boiling began from far downstream in contrast with the cases of the planar water jets of high Reynolds numbers. Heat flux increase and velocity decrease reduced the temperature difference between stagnation and far downstream regions with the increasing influence of boiling in partial boiling regime. The chance in nozzle-to-impinging surface distance from H/d=1 to 12 had a significant effect on heat transfer around the stagnation point of the submerged jet, but not for the free-surface jet. The submerged jet provided the lower cooling performance than the free-surface jet due to the entrainment of the pool fluid of which temperature increased.

Nucleate Pool Boiling of a Structured Enhanced Tube Used in a Flooded Refrigerant Evaporator

  • Kim, Nae-Hyun;Cho, Jin-Pyo;Choi, Kuk-Kwang
    • International Journal of Air-Conditioning and Refrigeration
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    • 제8권2호
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    • pp.23-28
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    • 2000
  • In this study, pool boiling performance of a structured enhanced tube for a flooded refrigerant evaporator was experimentally investigated. Tests were performed for three different refrigerants(R-11, R-123, R-l34a). Compared with the heat transfer coefficients of the smooth tube, the heat transfer coefficients of the enhanced tube were 6.6 times larger for R-11, 6.0 times larger for R-123 and 3.5 times larger for R-l34a, which are comparable with the performance of foreign products. The heat transfer coefficients of R-l34a was higher than those of R-11 or R-123, both for the enhanced tube and for the smooth tube. At 4.4$^\circ$C saturation temperature, however, the heat transfer coefficients of R-l34a was approximately the same as those of R-11. The effect of the saturation pressure on the boiling performance was similar to that of the smooth tube-the heat transfer coefficient increased as the saturation pressure increased.

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4.57 mm 세관 열교환기 내 이산화탄소의 증발열전달 특성 (Evaporation Heat Transfer Characteristics of Carbon Dioxide in the Inner Diameter Tube of 4.57 mm)

  • 구학근
    • Journal of Advanced Marine Engineering and Technology
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    • 제31권2호
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    • pp.145-151
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    • 2007
  • The evaporation heat transfer coefficient of $CO_2$(R-744) in a horizontal tube was investigated experimentally. The main components or the refrigerant loop are a receiver, a variable-speed pump, a mass flow meter, a pre-heater and evaporator(test section). The test section consists of a smooth, horizontal stainless steel tube of inner diameter of 4.57 mm. The experiments were conducted at mass flux of 200 to $500\;kg/m^2s$, saturation temperature of -5 to $5^{\circ}C$, and heat flux of 10 to $40\;kW/m^2$. The test results showed the heat transfer of $CO_2$ has a greater effect on nucleate boiling more than convective boiling. Mass flux of $CO_2$ does not effect nucleate boiling too much. In comparison with test results and existing correlations, the best fit of the present experimental data is obtained with the correlation of Jung et al. But existing correlations failed to predict the evaporation heat transfer coefficient of $CO_2$, therefore, it is necessary to develope reliable and accurate predictions determining the evaporation heat transfer coefficient of $CO_2$ in a horizontal tube.

연성회로기판 기반 수평전열관 표면의 비등기포거동 가시화 실험 연구 (Visualization Experiment for Nucleate Boiling Bubble Motion on a Horizontal Tube Heater Fabricated with Flexible Circuit Board)

  • 김재순;김유나;박군철;조형규
    • 한국가시화정보학회지
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    • 제14권2호
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    • pp.52-60
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    • 2016
  • The Passive Auxiliary Feedwater System(PAFS) is one of the advanced safety concepts adopted in the Advanced Power Reactor Plus(APR+). To validate the operational performance of the PAFS, detailed understanding of a boiling heat transfer on horizontal tube outside is of great importance. Especially, in the mechanistic boiling heat transfer model, it is important to visualize the phenomena but there are some limitations with conventional experimental approaches. In the present study, we devised a heater based on the Flexible Printed Circuit Board (FPCB) for a more comprehensive visualization and subsequently, a digital image processing technique for the bubble motion measurement was established. Using the measurement technique, important parameters of the nucleate boiling are analyzed.

수직관내 미포화수의 강제대류 천이비등에 대한 역학적 모델 (A Mechanistic Model for Forced Convective Transition Boiling of Subcooled Water in Vertical Tubes)

  • Lee, Kwang-Won;Baik, Se-Jun;Han, Sang-Good;Joo, Kyung-Oin;Yang, Jae-Young
    • Nuclear Engineering and Technology
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    • 제27권4호
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    • pp.503-517
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    • 1995
  • 강제대류 천이비등 열유속을 보다 실제 적으로 예측하기 위한 역학적 모델을 개발하였다. 이 모델은 가열된 벽면 근처를 어떤 기포기둥(Vapor Blanket)이 통과할 때 일어나는 다단계 비등과정 즉, 임계 기포기둥의 형성, 기포기둥밑의 미소액막(Macrolayer)의 기화 및 고갈, 그리고 얇은 기체막에서 일어나는 불안정한 막비등과정에 기초하였다. 핵비등이탈점 (DNB )과 막비등이탈점 (DFB)사이의 천이비등 곡선상의 열유속은 임계 기포기둥이 주어진 벽면을 통과할 동안 상기한 각 비등과정의 지속 시간비(Time Fraction)를 각 비등열유속에 곱한 후 그것을 합하여 정량화하였다. 이 모델의 예측치를 현재까지 발표된 문헌들에 나타난 실험치와 비교한 결과, 본 모델은 저건도 및 10 bar 근처의 고압조건의 실험치를 잘예측하는 것으로 나타났다.

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수평관내 R-113 냉매의 비등열전달에 관한 연구 (A study on the boiling heat transfer of R-113 in a horizontal tube)

  • 최병철;김원녕;김경근
    • Journal of Advanced Marine Engineering and Technology
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    • 제10권4호
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    • pp.67-77
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    • 1986
  • The information on the heat transfer characteristics, flow pattern and pressure drop, are very important for the desing of general heat exchanger, refrigerating system, air conditioning system and energy recovery system. In these systems, water or lubricating oil contained in working fluid affects greatly the flow and heat transfer condition and this phenomena must be considered in the practical design. An experiment has been performed for studying the flow and heat transfer characteristics of the forced convective horizontal flow of R-113 under the range of the liquid single phase state to the boiling flow state. Basic experimental results are obtained in the case that water or lubricating oil does not contaminate in the test fluid. Experimental results are as follows; (1) The local heat transfer coefficients in the nucleate boiling region and transition boiling region are almostly ten times as large as that of liquid single phase flow. (2) The measured heat transfer coefficient in the present experimental range is relatively agreed well with the predicted value from the various experimental results for the boiling flow.

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평면 충돌제트에서 노즐 깃이 단상 및 비등 열전달에 미치는 영향 (The Effect of Nozzle Collar on Single Phase and Boiling Heat Transfer by Planar Impinging Jet)

  • 신창환;임성환;우성제;조형희
    • 대한기계학회논문집B
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    • 제29권7호
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    • pp.878-885
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    • 2005
  • The water jet impingement cooling is one of the techniques to remove the heat from high heat flux equipments. Local heat transfer of the confined water impinging jet and the effect of nozzle collar to enhance the heat transfer are investigated in the fee surface jet and submerged jet. Boiling is initiated from the farthest downstream and increase of the wall temperature is reduced with developing boiling, forming the flat temperature distributions. The reduction in the nozzle-to-surface distance fur H/W$\le$1 causes significant increases and distribution changes of heat transfer. Developed boiling reduces the differences of heat transfer for various conditions. The nozzle collar is employed at the nozzle exit. The distances from heated surface to nozzle collar, Hc are 0.25W, 0.5W and 1.0W. The liquid film thickness is reduced and the velocity of wall jet increases as decreased spacing of collar to heated surface. Heat transfer is enhanced fur region from the stagnation to x/W$\~$8 in the free surface jet and to x/W$\~$5 in the submerged jet. For nucleate boiling region of further downstream, the heat transfer by the nozzle collar is decreased in submerged jet comparing with higher velocity condition. It is because the increased velocity by collar is de-accelerated downstream.