• 제목/요약/키워드: Bubble departure frequency

검색결과 9건 처리시간 0.017초

미세 입자로 충전된 캐비티에서의 열 기포 형성 (Formation of Thermal Bubble from Particle-Filled Microcavity)

  • 정광훈;이헌주;장영수;이윤표;김호영
    • 대한기계학회논문집B
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    • 제31권3호
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    • pp.248-255
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    • 2007
  • Thermal bubble formation is a fundamental process in nucleate boiling heat transfer and many microelectromechanical thermal systems. One of the established facts is that heterogeneous nucleation is originated from vapors trapped inside cavities. Based on this, we performed an experimental study on the formation of thermal bubbles from microcavity fabricated by microfabrication technology on a copper plate. The cavity was filled with aluminum particles to enhance thermal bubble formation. We observed the thermal bubble behaviors, such as bubble incipience, diameter, frequency and coalescence during nucleate boiling. The experimental data showed that the superheat required to trigger the bubble formation was significantly reduced when the cavity was filled with microparticles. We found that the initial increase of superheat led to the increase of both the departure diameter and frequency while the further increase of superheat caused multiple bubbles to coalesce resulting in the decrease of departure frequency.

Computational Fluid Dynamic Simulation of Single Bubble Growth under High-Pressure Pool Boiling Conditions

  • Murallidharan, Janani;Giustini, Giovanni;Sato, Yohei;Niceno, Bojan;Badalassi, Vittorio;Walker, Simon P.
    • Nuclear Engineering and Technology
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    • 제48권4호
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    • pp.859-869
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    • 2016
  • Component-scale modeling of boiling is predominantly based on the Eulerian-Eulerian two-fluid approach. Within this framework, wall boiling is accounted for via the Rensselaer Polytechnic Institute (RPI) model and, within this model, the bubble is characterized using three main parameters: departure diameter (D), nucleation site density (N), and departure frequency (f). Typically, the magnitudes of these three parameters are obtained from empirical correlations. However, in recent years, efforts have been directed toward mechanistic modeling of the boiling process. Of the three parameters mentioned above, the departure diameter (D) is least affected by the intrinsic uncertainties of the nucleate boiling process. This feature, along with its prominence within the RPI boiling model, has made it the primary candidate for mechanistic modeling ventures. Mechanistic modeling of D is mostly carried out through solving of force balance equations on the bubble. Forces incorporated in these equations are formulated as functions of the radius of the bubble and have been developed for, and applied to, low-pressure conditions only. Conversely, for high-pressure conditions, no mechanistic information is available regarding the growth rates of bubbles and the forces acting on them. In this study, we use direct numerical simulation coupled with an interface tracking method to simulate bubble growth under high (up to 45 bar) pressure, to obtain the kind of mechanistic information required for an RPI-type approach. In this study, we compare the resulting bubble growth rate curves with predictions made with existing experimental data.

저압에서의 과냉각 비등 현상에 대한 CFD의 유효성 검토 (CFD validation for subcooled boiling under low pressure)

  • 최용석;김유택;임태우
    • Journal of Advanced Marine Engineering and Technology
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    • 제40권4호
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    • pp.275-281
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    • 2016
  • 본 연구에서는 전산유체역학(CFD)을 이용하여 저압에서의 과냉각 비등 현상에 대한 수치해석적 연구를 수행하였다. 과냉각 비등 현상을 시뮬레이션하기 위해서 벽비등 모델을 사용하였으며, 벽비등 모델은 기포 이탈 직경, 핵 사이트 밀도 그리고 기포 이탈 빈도로 구성된 하위모델을 필요로 한다. 전산유체역학 코드 CFX는 실험 자료에 근거한 기본 모델을 제공한다. 하지만 이러한 모델은 대부분 고압조건에서 개발되었기 때문에 저압조건에서는 잘 맞지 않는 것으로 보인다. 따라서 본 연구에서는 저압조건에서 과냉각 비등 현상에 대해서 CFD의 유효성을 검토하였다. 수치해석적 결과는 기존의 실험 결과와 비교하였다. 수치해석은 질량유속 $250{\sim}750kg/m^2s$, 열유속 $0.37{\sim}0.77MW/m^2$ 그리고 출구압력 0.11 MPa범위에서 수행되었다. 저압조건에서 개발된 상관식을 적용함으로써 수치해석의 정확성을 높일 수 있었다.

전기장을 이용한 핵비등 열전달 촉진에 관한 실험적 연구 (Experimental study on nucleate boiling heat transfer enhancement using an electric field)

  • 권영철;김무환;강인식
    • 대한기계학회논문집B
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    • 제21권12호
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    • pp.1563-1575
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    • 1997
  • To understand EHD nucleate boiling heat transfer enhancement, EHD effects on R-113 nucleate boiling heat transfer in a non-uniform electric field were investigated. The pool boiling heat transfer and the dynamic behavior of bubbles in d.c./a.c. electric fields under a saturated or subcooled boiling were studied by using a plate-wire electrode and a high speed camera. From the pool boiling heat transfer study, the shift of the pool boiling curve, the increase of the heat transfer and the delay of ONB and CHF points to higher heat fluxes were observed. From the dynamic behavior of bubbles, it was observed that bubbles departed away from the whole surface of the heated wire in radial direction due to EHD effects by a nonuniform electric field. With increasing applied voltages, the bubble size decreased and the active nucleation site and the departure number of bubbles showed the different trend. The present study indicates that the EHD nucleate boiling heat transfer is closely connection with the dynamic behavior of bubbles and the secondary flow induced near the heated surface. Therefore, the basic studies on the bubble behavior such as bubble frequency, bubble diameter, bubble velocity and flow characteristics are necessary for complete understanding of the enhancement mechanism of the boiling heat transfer using an electric field.

핵비등에서 기포의 동특성에 대한 전기장의 효과 (Effects of an Electric Field on the Dynamic Characteristics of Bubbles in Nucleate Boiling)

  • 권영철;장근선;권정태;김무환
    • 설비공학논문집
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    • 제12권11호
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    • pp.963-971
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    • 2000
  • In order to investigate the effects of an electric field on EHD(Electro-hydrodynamic) nucleate boiling hat transfer characteristics in a nonuniform electric field under saturated pool boiling, the basic study has been performed experimentally. In the present study, the working fluid is R-113 and the plate-wire electrode system is used to generate a steep electric field gradient. Boiling parameters are investigated by using a high speed camera. The electric field distribution around a wire is obtained to understand the effect of an electric field on bubble departure/movement. The experimental results show EHD effects are much more considerable when the applied voltage increases. Bubbles depart away from the heated wire in radial direction. It is confirmed that the mechanisms of EHD nucleate boiling are closely connected with the dynamic behavior of bubbles. The boiling parameters are significantly changed by the electric field strength. With increasing applied voltages, the bubble size decreases and the nucleation site density, bubble velocity and bubble frequency increase.

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Experimental study on the influence of heating surface inclination angle on heat transfer and CHF performance for pool boiling

  • Wang, Chenglong;Li, Panxiao;Zhang, Dalin;Tian, Wenxi;Qiu, Suizheng;Su, G.H.;Deng, Jian
    • Nuclear Engineering and Technology
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    • 제54권1호
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    • pp.61-71
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    • 2022
  • Pool boiling heat transfer is widely applied in nuclear engineering fields. The influence of heating surface orientation on the pool boiling heat transfer has received extensive attention. In this study, the heating surface with different roughness was adopted to conduct pool boiling experiments at different inclination angles. Based on the boiling curves and bubble images, the effects of inclination angle on the pool boiling heat transfer and critical heat flux were analyzed. When the inclination angle was bigger than 90°, the bubble size increased with the increase of inclination angle. Both the bubble departure frequency and critical heat flux decreased as the inclination angle increased. The existing theoretical models about pool boiling heat transfer and critical heat flux were compared. From the perspective of bubble agitation model and Hot/Dry spot model, the experimental phenomena could be explained reasonably. The enlargement of bubble not only could enhance the agitation of nearby liquid but also would cause the bubble to stay longer on the heating surface. Consequently, the effect of inclination angle on the pool boiling heat transfer was not conspicuous. With the increase of inclination angle, the rewetting of heating surface became much more difficult. It has negative effect on the critical heat flux. This work provides experimental data basis for heat transfer and CHF performance of pool boiling.

낮은 핀관의 형상이 LiBr 수용액의 풀 비등에 미치는 영향에 대한 실험적 연구 (An Experimental Study on the Effect of Low Fin Tube Geometry on Pool Boiling of a LiBr Solution)

  • 김내현
    • 대한기계학회논문집B
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    • 제39권7호
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    • pp.591-598
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    • 2015
  • 본 연구에서는 핀 핏치와 핀 높이가 다른 7종류의 낮은 핀관에 대하여 LiBr 농도 0%.~50%, 열유속 $20kW/m^2{\sim}40kW/m^2$, 포화압력 7.38kPa~101.3kPa에서 풀 비등 실험을 수행하였다. 실험 범위에서 최적 낮은 핀관 형상은 핀 핏치 26fpi, 핀 높이 1.8mm로 나타났다. 핀 핏치가 너무 넓으면 전열 면적이 감소하고 핀 핏치가 너무 좁으면 기포의 성장 및 이탈이 원활하지 못하게 되어 최적 핀 핏치가 존재한다. 포화압력이 낮아질수록, LiBr 농도가 증가할수록 열전달계수는 감소하였다. 이는 포화압력이 낮아질수록 기포의 이탈직경은 증가하고 이탈 빈도는 감소하기 때문이다. 또한 LiBr 농도가 증가하면 포화온도는 증가하고 물질확산율은 감소하는데 이에 따라 기포의 성장속도가 감소하고 따라서 열전달계수가 감소하게 된다. 낮은 핀관의 열전달계수는 모든 포화압력과 농도에서 평활관의 열전달계수보다 크게 나타났다. 본 실험자료를 기반으로 상관식을 제시하였다.

전열면의 특수표면화에 의한 열기기의 효율향상에 관하여 (Improved Heat Transfer Coefficient in Heat Exchanger by the Use of Specialized Heating Surface)

  • 임장순
    • 대한설비공학회지:설비저널
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    • 제8권3호
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    • pp.131-150
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    • 1979
  • Recently only a few correlations between various factors due to the different grades of surface roughness for the nucleate pool boiling have been proposed. The main purpose of this work is to test the validity of these types of correlations between related factors to nucleate pool boiling phenomena. The boiling experiments using distilled water were carried out at the heat flux ranging from $7.4\times10^4\;to\;2.4\times10^5kcal/m^2h$ on the sintered porous metal surface with the cavity diameter of 10, n, 40, 70, $100{\mu}$, respectively, at the atmospheric pressure, To determine the bubble sizes, number of nucleation sites, delay and growth time, frequency of bubble emission and rising velocities of bubbles, the high speed motion picture technique was employed. In the correlation $f{\propto}D_b^n$, where f denotes frequency of bubble emission and $D_b$ departure diameter, n, the power factor of $D_b$, have been found to be from -2 to -10/3. The correlation C in the correlation between heat flux q and density of nucleation sites $\frac{N}{A}$, $q=C(\frac{N}{A})^n$, was appeared to be more crucial than the power factor n. The correlation of the heat flux q to the temperature difference ${\Delta}T$ and the density of nucleation sites$\frac{N}{A}$, was proposed to be $$q-460{\Delta}T^{\frac{5}{4}}=K{\Delta}T{\frac{5}{3}}(\frac{N}{A})^{\frac{2}{3}}$$. The values of heat transfer coefficient obtained in this experiments for the porous sintered metal surface appeared to be very high in comparison with the formerly obtained results for the other surfaces.

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Critical heat flux (CHF) in pool boiling under static and rolling conditions

  • Tanjung, Elvira F.;Albdour, Samah A.;Jeong, Yeon Uk;Jo, Daeseong
    • Nuclear Engineering and Technology
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    • 제52권3호
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    • pp.520-529
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    • 2020
  • Experimental investigations were attempted to simultaneously observe the vapor behaviors and critical heat flux under static and rolling conditions. From visualization results, vapor initiated, grew, and detached individually in a vertical direction from the static heated surfaces (at 10, 20, and 30°). While under rolling motion, initiated vapor grew, and interacted with each other, resulting in forming a wider dry spot on the heated surface. Also, it was observed that the vapor drifted upward and stayed on the heated surface longer compared to under static condition. The faster the platform rolls, the longer the vapor stay on the heated surface, significantly decreasing the CHF. On the other hand, as the platform rolls slower (at high rolling period), CHF increases. CHF was decreased with increasing maximum rolling amplitude and inclination angle under both conditions (static and rolling). CHF under rolling conditions was noticed to be lower than under static condition except at maximum rolling amplitude of 10°. The bubble departure frequency at a maximum rolling amplitude of 10° was the highest among all of rolling amplitudes, thereby enhancing the CHF. These results indicate that rolling motion significantly affects vapor behaviors and CHF.