• 제목/요약/키워드: 강제대류 비등

검색결과 18건 처리시간 0.018초

수평 원관의 비등 열전달에서 강제대류의 영향 (The effect of forced convection on boiling heat transfer from a horizontal tube)

  • 이승홍;이억수;정은행
    • 설비공학논문집
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    • 제10권5호
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    • pp.558-568
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    • 1998
  • This paper presents the results of experiments involving external forced convection on boiling heat transfer from electrically heated horizontal tube to water in cross flow. In these experiments, all of the following primary variables were varied: heat flux, cross flow velocity, pressure and degree of subcooling. Local surface temperatures were measured at nine peripheral positions. Surface temperature distributions are classified into four groups as a function of heat flux. The characteristics of the boiling curve at different velocity, degree of subcooling and pressure are examined.

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2상 마이크로 채널 히트 싱크에서의 유동 비등 열전달에 관한 연구 (Study on flow boiling heat transfer in two-phase micro-channels heat sink)

  • 최용석;임태우
    • Journal of Advanced Marine Engineering and Technology
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    • 제39권7호
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    • pp.702-708
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    • 2015
  • 본 연구에서는 FC-72를 작동 유체로 사용하여 이상 유동 비등에 관한 실험을 수행하였다. 마이크로 채널은 깊이 0.2mm, 폭 0.45mm, 길이 60mm 그리고 채널의 개수는 15개로 구성되었다. 실험은 질량유속과 열유속 각각 $200-400kg/m^2s$, $5.6-49.0kW/m^2$ 범위와 증기 건도 0.02-0.93 범위에서 수행되었다. 실험 결과에 따르면 낮은 건도(x<0.2)영역에서는 핵비등에 의한 열전달이 지배적으로 작용하며, 그 이상의 증기 건도 영역에서는 핵비등과 강제 대류 비등의 영향이 복합적으로 작용하는 것으로 나타났다. 핵비등과 강제 대류 비등은 각각 비등수와 대류수에 관한 함수로 표현할 수 있으며, 실험에서 얻어진 열전달 계수는 기존의 상관식에 의한 열전달 계수와 비교하였다.

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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강제대류 아냉각비등에서 급격한 기포발생점의 예측 (Prediction of the Onset of Significant Void in Forced-Convection Subcooled Boiling)

  • 이상천;남상철
    • 대한기계학회논문집
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    • 제18권3호
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    • pp.681-689
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    • 1994
  • A model to predict the onset of significant void (OSV) in vertical flow between parallel plates has been developed. The model was compared to the experimental data of Whittle and Forgan (1967) and Dougherty et al. (1990), showing excellent agreement. The model was also compared with the Saha-Zuber(1974) correlation, which has been widely used in computer codes for nuclear safety analysis. The present theory is more conservative than this correlation, and further shows that, contrary to this correlation, the Stanton number is not solely related to the Peclet number. This may explain the large error margins required for the Saha-Zuber correlation, and also the scatter beyond the error margins specified by the authors. The steady-state OSV heat fluxes for equal and unequal heating cases between parallel plates were compared. The arithmetic mean of heat fluxes for unequal heating cases is less than the heat flux for equal heating cases. The result may imply that OSV is controlled by local thermal parameters rather than bulk parameters.

수평관내 3성분 혼합냉매의 강제대류비등 열전달 (Forced convective boiling heat transfer for a ternary refrigerant mixture inside a horizontal tube)

  • 오종택
    • 설비공학논문집
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    • 제11권6호
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    • pp.912-920
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    • 1999
  • The forced convective boiling heat transfer coefficients of R-407C were measured inside a horizontal tube 6.0mm I.D. and 4.0m long. The heat transfer coefficients increased according to an increase in heat flux at constant mass flux. Because nucleation was completely suppressed in the two-phase flow region with high quality, heat transfer coefficients in forced convective evaporation were higher than those in nucleate boiling region. Average heat transfer coefficients of R-407C were about 30 percent lower than the pure refrigerant correlation, due to mass transfer resistance at the gas-liquid interface. However, the total experimental data shows an agreement with the predicted data for ternary refrigerant mixtures with a mean deviation of 30%.

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강제대류 및 핵비등영역에 있어서 액적유량과 분무냉각 열전달의 상관관계에 관한 연구 (Correlation of Droplet Flow Rate and Spray Cooling Heat Transfer in Forced Convection and Nucleate Boiling Region)

  • 김영찬
    • 한국분무공학회지
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    • 제13권3호
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    • pp.143-148
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    • 2008
  • In the present study, the correlation between the Nusselt number and Reynolds number was developed for forced convection and nucleate boiling region in spray cooling. Also the effect of droplet subcooling on spray cooling heat transfer was investigated. Full cone spray nozzles were employed for spray cooling experiment, and water and FC-77 were used for developing the correlation. From the experimental results, the correlation between the Nusselt number and Reynolds number based on droplet-flow-rate was developed. The correlation shows good predictions with ${\pm}30%$ error for water and FC-77.

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헬리컬 증기발생기 코일에서 강제대류 비등 열전달 및 유동의 수치 적 예측 (Numerical Prediction of Forced Convective Boiling Heat Transfer and Flow in Steam Generator Helical Coils)

  • 조종철;김효정;김웅식;유선오
    • 한국전산유체공학회:학술대회논문집
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    • 한국전산유체공학회 2004년도 추계 학술대회논문집
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    • pp.127-130
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    • 2004
  • In this study, three-dimensional numerical calculations are peformed to simulate the flow and heat transfer in helically coiled tube steam generator employing a commercial CFD (Computational Fluid Dynamics) code. The problem considered herein includes the boiling phase change flow of tube side fluid and the single-phase counter-current flow of shell side hot fluid transferring heat to the tube side flow thru the tube wall. Detailed investigations are performed for both shell-side and tube-side flow fields in terms of density and volume fractions of each phase of fluids as well as for the tube wall heat transfer field in terms of heat transfer coefficients.

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수평 평활관내에서 비공비혼합냉매의 강제대류 증발열전달 (Forced Convective Evaporating Heat Transfer of Non-azeotropic Refrigerant Mixtures in a Horizontal Smoothed Tube)

  • 박기원;오후규
    • 설비공학논문집
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    • 제7권2호
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    • pp.225-233
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    • 1995
  • Experiments were performed to investigate the heat transfer characteristics of nonazeotropic mixture R-22+R-114 in a heat pump system. The ranges of parameter, such as heat flux, mass flow rate, and quality were $8,141{\sim}32,564W/m^2$, 24~58kg/h, and 0~1, respectively. The overall compositions of the mixtures were 50 and 100 per-cent of R-22 by weight for R-22+R-114 mixture. The results indicated that there were distinct different heat transfer phenomena between the pure substance and the mixture. In case of pure refrigerant the heat transfer rates for cooling were strongly dependent upon quality of the refrigerant. Overall evaporating heat transfer coefficients for the mixture were somewhat lower than pure R-22 values in the forced convective boiling region. For a given flow rate, the heat transfer coefficient at the circumferential tube wall(top, side, and bottom of the test tube) for R-22/R-114(50/50wt%)mixture, however, was higher than for pure R-22 at side and bottom of the tube. Furthermore, a prediction for the evaporating heat transfer coefficient of the mixtures was developed based on the method of Yoshida et.al.'s. The resulting correlation yielded a good agreement with the data for the refrigerant mixtures.

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경사진 원형관내에서의 강제대류비등 열전달에 대한 실험적 연구 (An Experimental Study on the Convective Boiling in Inclined Tubes)

  • 이홍욱;이준식;박군철
    • 설비공학논문집
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    • 제13권8호
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    • pp.674-681
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    • 2001
  • An experiment is conducted to investigate the effect of the inclination angle on convective boiling heat transfer of a uniformly heated tube. The test section used is a stainless steel tube with10.7mm in inner diameter. The hating length is 3m and is heated directly by an AC current. The test fluid is R-113. Experiment are carried out with mass flow rates of 300, 500 and $700\;kg/m^{2}s$, and heat fluxes varying from 5 to 65 kW/$m^2$. The inclination angles of the tube are $0^{\circ},\;5^{\circ},\;11^{\circ}\;and\;25^{\circ}$. the circumferential temperature variation at low quality region and the location of dryout at high quality region are mainly observed. Circumferential anisothermality occurring at low mass flow rate and low quality conditions is gradually reduced with the increase in the inclination angle and finally disappears at the inclination angle of $25^{\circ}$. Critical quality where dryout is initiated is seriously influenced by the inclination angle. Wall temperature after critical quality is also affected by the inclination angle.

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전열촉진관군의 순수냉매 강제대류비등 (Forced Convective Boiling of Pure Refrigerants in a Bundle of Enhanced Tubes)

  • 김내현;정호종;조진표;최국광
    • 대한기계학회논문집B
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    • 제25권12호
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    • pp.1831-1843
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    • 2001
  • In this study, convective boiling tests were conducted for enhanced tube bundles. The surface geometry consists of pores and connecting gaps. Tubes with three different pore sizes (d$_{p}$ = 0.20, 0.23 and 0.27 mm) were tested using R-123 and R-l34a for the following range: 8 kg/m$^2$s G 26 kg/m$^2$s, 10 kW/m$^2$ q0 40 kW/m$^2$and 0.1 $\chi$ 0.9. The convective boiling heat transfer coefficients were strongly dependent on heat flux with negligible dependency on mass flux or quality. For the present enhanced geometry (pores and gaps), the convective effect was apparent. The gaps of the present tubes may have served routes for the passage of two-phase mixtures, and enhanced the boiling heat transfer. The convective effect was more pronounced at a higher saturation temperature. More bubbles will be generated at a higher saturation temperature, which will lead to enhanced convective contribution. The pore size where the maximum heat transfer coefficient was obtained was larger for R-l34a (d$_{p}$ = 0.27 mm) compared with that for R-123 (d$_{p}$ = 0.23 mm). This trend was consistent with the previous pool boiling results. For the enhanced tube bundles, the convective effect was more pronounced for R-134a than for R-123. This trend was reversed for the smooth tube bundle. Possible reasoning is provided based on the bubble behavior on the tube wall. Both the modified Chen and the asymptotic model predicted the present data reasonably well. The RMSEs were 14.3% for the modified Chen model and 12.7% for the asymptotic model.model.