• Title/Summary/Keyword: 포화 핵비등

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Study on the Relationships between Single Bubble Growth Behavior and Bubble Shape Assumption in Pool and low-He Flow Boiling (풀비등과 저Re수 흐름비등에서의 기포의 형상과 성장에 대한 연구)

  • Kim, Jeong-Bae
    • Journal of the Korean Solar Energy Society
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    • v.29 no.3
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    • pp.73-82
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    • 2009
  • 포화상태 핵비등과 저 Re수의 흐름비등에서 얻어진 실험결과를 바탕으로 하여, 기포가 성장하는 동안의 등가 기포 직경과 열전단율의 거동에 대한 기포 형상 가정의 효과를 제시하기 위한 해석적인 연구를 수행하였다. 이러한 목적을 달성하기 위하여, 등가 기포 반경이 기포가 성장하는 동안 촬영된 기포의 이미지로부터 얻어질 수 있는 형상 가정을 이용하여 계산되었다. 그리고 열전달율을 포화상태 핵비등 동안 미세크기의 히터와 휘스톤브리지 회로를 이용하여 측정하였다. 그리고, 기포 형상 가정의 효과를 실험결과와 비교하였고, 이를 통해 단일 기포의 성장 거동을 분석하기 위한 기포 형상 가정이 매우 중요함을 보였다.

Heat Transfer Characteristics under Saturated Nucleate Pool Boiling for Various Heating Surface Angles using Heater with Artificial Cavity (인공 캐비티를 가진 히터를 이용한 가열면 경사각에 따른 포화상태 풀 핵비등 열전달 기초연구)

  • Kim, Jeong-Bae
    • Journal of the Korean Solar Energy Society
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    • v.29 no.4
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    • pp.7-14
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    • 2009
  • Nucleate pool boiling experiments with constant heat flux condition were performed using pure R11 and R113 for various surface angles under saturated pool condition. A circular heater of 1 mm diameter, with artificial cavity in the center, fabricated using MEMS technique and the high-speed controller were used to maintain the constant heat flux. Images of bubble growth were taken at 5,000 frames per second using a high-speed CCD camera. The bubble geometry was obtained from the captured bubble images. The effects of surface angles on the bubble growth behaviors were analyzed as dimensional scales for the initial and thermal growth regions. The parameters for the bubble growth behaviors were bubble radius, bubble growth rate, sliding velocity, bubble shape and advancing and receding contact angles. These phenomena require further analysis for various surface angles, but this study will provide good experimental data with constant heat flux boundary condition for such works.

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

  • Jeong, Seunghyuck;Jung, Satbyoul;Kim, Hyungdae
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.39 no.6
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    • pp.519-526
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    • 2015
  • To measure the physical parameters of the simple microlayer model for the prediction of the heat flux and heat transfer rate due to the evaporation of the microlayer during nucleate boiling, the microlayer geometry was experimentally examined. The parameters, including initial thickness, moving velocity and microlayer radius, were measured by total reflection and interferometry techniques using a laser. Single-bubble nucleate boiling experiments were conducted using saturated water on a horizontal surface under atmospheric pressure. The geometric characteristics of the microlayer underneath the bubbles periodically nucleating at a nucleation site at an average heat flux of $200kW/m^2$ were analyzed. The experimental results in the present study show that the maximum initial thickness of the microlayer and the horizontal moving velocity are $5.4{\mu}m$ and 0.12 m/s, respectively.

A Study on Saturated Boiling Heat Transfer in Upward Rectangular Impinging Water Jet System (연직상향(鉛直上向) 사각충돌수분류(四角衝突水噴流)의 포화비등 열전달에 관한 연구)

  • Lee, J.S.;Ohm, K.C.;Seo, J.Y.
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.3 no.5
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    • pp.395-403
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    • 1991
  • The purpose of this investigation was to characterize nucleate boiling and burn-out heat flux for rectangular free jet with saturated water impinging perpendicularly and upward against a flat uniform heat flux surface. Heat flux measured for Reynolds number based on rectangular nozzle width and for aspect ratio. The result of nucleate boiling heat transfer was presented nondimensional experimental equation including Nusselt, Boiling, Subcooling, Reynolds and Weber number. The effect of aspect ratio of heated surface in the burn-out heat flux had not appeared distinctly. But for the same aspect ratio, burn-out heat flux increased linearly with increment of nozzle exit velocity.

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

  • Lee, Kwang-Won;Baik, Se-Jun;Han, Sang-Good;Joo, Kyung-Oin;Yang, Jae-Young
    • Nuclear Engineering and Technology
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    • v.27 no.4
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    • pp.503-517
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    • 1995
  • A mechanistic model for forced convective transition boiling has been developed to predict transition boiling heat flux realistically. This model is based on a postulated multi­stage boiling process occurring during the passage time of an elongated vapor blanket specified at a critical heat flux condition. Between the departure from nucleate boiling (DNB) and the departure from film boiling (DFB) points, the boiling heat transfer is established through three boiling stages, namely, the macrolayer evaporation and dryout governed by nucleate boiling in a thin liquid film and the unstable film boiling. The total heat transfer rate during the transition boiling is the sum of the heat transfer rates after the DNB weighted by the time fractions of each stage, which are defined as the ratio of each stage duration to the vapor blanket passage time. The model predictions are compared with some available experimental transition boiling data. From these comparisons, it can be seen that the transition boiling heat fluxes including the maximum heat flux and the minimum film boiling heat flux are nil predicted at low qualities/high pressures near 10 bar.

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Development of a Computer Program for Thermal Sizing of a Copper Bonded Steam Generator (구리밀봉 증기발생기의 열적크기 계산을 위한 프로그램 개발)

  • 김의광;김연식;어재혁;김성오;백병준
    • Journal of Energy Engineering
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    • v.12 no.2
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    • pp.84-92
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    • 2003
  • A one-dimensional thermal-hydraulic analysis computer program is developed for thermal sizing of a copper bonded steam generator. It is assumed that the conduction heat transfer of copper region between the hot side and the cold side tube is one-dimensional and its thermal resistance is derived as a function of a tube pitch. The flow regions of the water/steam side are divided into four regions: subcooled, saturated, film boiling, and super-heated. The number of tube selected ranges from 250 to 3500 and the pitch to tube diameter (P/D) ratios are 1.4, 1.6 and 1.8 for the parametric study calculation. The calculation results showed that when the number of tube was 2500, the length of the heating tube was about 12 m and the outside diameter of the steam generator was about 3 m. If the P/D ratio increases, the thermal resistance of copper component also increases, however the length of the heating tube is not so much increased.

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

  • Son, Chang-Hyo
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.9 no.3
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    • pp.574-579
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    • 2008
  • The evaporation heat transfer coefficient of $CO_2$ (R-744) in a horizontal tube was investigated experimentally. 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 4.57mm. The experiments were conducted at mass flux of 400 to $900kg/m^2s$, saturation temperature of 5 to $20^{\circ}C$, 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. In comparison with test results and existing correlations, All of the existing correlations for the heat transfer coefficient underestimated the experimental data. However Jung et al.'s correlation showed a good agreement with the experimental data. Therefore, it is necessary to develope accurate predictions determining the evaporation heat transfer coefficient of $CO_2$ in horizontal tubes.