• International Journal of Air-Conditioning and Refrigeration
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• 제7권
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• pp.79-90
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• 1999

This investigation presents the experimental results of forced convection boiling heat transfer around a circular, electrically heated horizontal cylinder to subcooled water in cross flow. In these experiments, the following primary variables were included: heat flux, flow velocity, pressure and degree of subcooling at inlet. Local surface temperatures were measured at nine peripheral positions. Local surface temperature distributions are classified into four categories depending on the supplied heat flux. The effects of the boiling curve depending on the fluid velocity, degree of subcooling at inlet and pressure are presented.

• 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.

• 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.

• Nuclear Engineering and Technology
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• 제44권8호
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• pp.889-896
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• 2012

Recent progress in the computational fluid dynamics methods of two- and multiphase phase flows has already started opening up new exciting possibilities for using complete multidimensional models to simulate boiling systems. Combining this new theoretical and computational approach with novel experimental methods should dramatically improve both our understanding of the physics of boiling and the predictive capabilities of models at various scale levels. However, for the multidimensional modeling framework to become an effective predictive tool, it must be complemented with accurate mechanistic closure laws of local boiling mechanisms. Boiling heat transfer has been studied quite extensively before. However, it turns out that the prevailing approach to the analysis of experimental data for both pool boiling and forced-convection boiling has been associated with formulating correlations which normally included several adjustable coefficients rather than based on first principle models of the underlying physical phenomena. One reason for this has been the tendency (driven by practical applications and industrial needs) to formulate single expressions which encompass a broad range of conditions and fluids. This, in turn, makes it difficult to identify various specific factors which can be independently modeled for different situations. The objective of this paper is to present a mechanistic modeling concept for both pool boiling and forced-convection boiling. The proposed approach is based on theoretical first-principle concepts, and uses a minimal number of coefficients which require calibration against experimental data. The proposed models have been validated against experimental data for water and parametrically tested. Model predictions are shown for a broad range of conditions.

• 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.

• 설비공학논문집
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• 제12권5호
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• pp.502-510
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• 2000

Evaporation heat transfer characteristics were studied in a horizontal tube using R22/R114 non-azotropic refrigerant mixture. the heat transfer coefficient was high in the upper part for pure refrigerants, and heat transfer coefficient was low in the lower part for refrigerant mixtures. In the low quality region where nucleate boiling was dominant, the average heat transfer coefficient was low. In the region where forced convection was dominant, heat transfer coefficient was high. Results show that the heat transfer coefficient for pure refrigerants obtained by experiments were lower than those of Yoshida et al. but agreed well with Jung et al., and Chen et al. data. But the heat transfer coefficients for refrigerant mixtures were lower about 20% than those predicted by the equation for pure refrigerant.

• 대한기계학회논문집B
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• 제34권11호
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• pp.983-990
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• 2010

본 연구에서는 냉각면의 표면온도가 비교적 낮은 강제대류 및 핵비등영역에서 다양한 종류의 마이크로 휜이 가공된 냉각면의 분무냉각 열전달에 대해 실험적으로 연구하였다. 실험결과로부터 냉각면 표면에 가공된 마이크로 휜은 분무냉각 열전달을 촉진시키며, 냉각휜의 크기와 종류에 상관없이 분무유량이 증가할수록 분무냉각 열전달도 큰 폭으로 증가하고 있음을 알 수 있었다. 또한 희박한 분무영역에서는 냉각면에 가공된 휜의 크기와 형상이 분무냉각 열전달에 큰 영향을 미치고 있으나, 분무유량이 증가할수록 이러한 경향은 점차 약해져 본 실험에서 가장 높은 분무유량조건에서는 편평한 냉각면을 제외한 모든 냉각면의 열유속이 거의 동일하게 나타나고 있음을 알 수 있었다.

• 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 MW_th. 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 MW_th.

• 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.

• 수산해양교육연구
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• 제28권5호
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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.