• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집D
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• pp.447-452
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• 2001

Quenching phenomena of hemispherical downward facing convex surfaces with narrow gaps have been investigated experimentally. Experiments employed test sections having 1 and 2 mm in gap thickness and 1 atm in system pressure. From interpretations of the temperature and the heat flux history, it was found that the flooding inside the gap was restricted by CCFL phenomena and quenching process was propagated from lower to upper region of the internal copper shell. The ratio of the maximum heat fluxes at 1 mm to 2mm in gap thickness was the almost same that obtained by steady state experiments. The quenching scenario of the hemispherical downward facing surface with narrow gap has been suggested.

• 대한기계학회논문집
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• 제16권6호
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• pp.1195-1204
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• 1992

본 연구에서는 등온 평면의 온도가 0.0.deg. C부터 8.0.deg. C까지, 그리고 주위물의 온 도가 1.0.deg. C부터 10.0.deg. C까지 일 대 상향 및 하향면 주위에서 일어나는 자연대류를 유한 차분법(FDM)으로 수치해석하여 등온면 주위에서 일어나는 유동형태, 속도분포, 평균 Nusselt수를 구하여 유동 및 열전달특성을 구명하였다.

• Nuclear Engineering and Technology
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• 제35권4호
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• pp.274-285
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• 2003

Film boiling heat transfer coefficients for a downward-facing hemispherical surface are measured from the quenching tests in DELTA (Downward-boiling Experimental Loop for Transient Analysis). Two test sections are made of copper to maintain Bi below 0.1. The outer diameters of the hemispheres are 120 mm and 294 mm, respectively. The thickness of both the test sections is 30 mm. The effect of diameter on film boiling heat transfer is quantified utilizing results obtained from the two test sections. The measured heat transfer coefficients for the test section with diameter 120 mm lie within the bounding values from the laminar film boiling analysis, while those for diameter 294 mm are found to be greater than the numerical results on account of the Helmholtz instability. There is little difference observed between the film boiling heat transfer coefficients measured from the two test sections. In addition, the higher thermal conductivity of copper results in the higher minimum heat flux in the tests. For the test section of diameter 120 mm, the Leidenfrost point is lower than that for the test section of diameter 294 mm. Destabilization of film boiling propagates radially inward for the 294 mm test section versus radially outward for the 120 mm Test Section.

• 대한기계학회논문집B
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• 제35권7호
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• pp.701-708
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• 2011

기울어진 평판에서 발생하는 자연대류 열전달현상을 $R_{a_L}$ $1.69{\times}10^{11}$과 $7.23{\times}10^{12}$에 대하여 실험적으로 연구하였다. 유사성을 이용하여 열전달실험을 물질전달 실험으로 대체하였고 물질전달계로 전기도금계를 사용하였다. 평판의 기울기는 상향수평에서 하향수평까지 $10^{\circ}$씩 변화시켰다. 하향평판에서는 수직 벽면에 대한 자연대류 열전달 상관식에서 g 대신 g $cos{\theta}$로 대체함으로써 열전달계수를 구할 수 있다는 기존의 이론과 일치하는 결과를 얻었다. 상향평판의 경우 경계층이 벽면을 따라 발달되는 경우와 벽면으로부터 박리되는 2가지 영역으로 구분되는데 박리에 따른 열전달 증가를 확인하였다. 아울러 도금패턴을 이용하여 박리지점을 시각화하였고 박리지점에 대한 분석이 수행되었다.

• 오토저널
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• 제10권1호
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• pp.26-32
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• 1988

A study has been conducted experimentally on the natural convection heat transfer characteristics of fin arrays on a horizontal flat plate in air. The effects of fin heights and Rayleigh numbers are mainly investigated. The experimental results are as follows; 1. The mean fin and mean total Nusselt numbers increase as dimensionless fin heights increase at 0.67.leg.H/s.leg.1.67. The mean plate Nusselt numbers increase in case of upward facing fins, but they decrease in case of downward facing fins. 2. The mean Nusselt numbers increase as Rayleigh numbers increase. 3. The mean fin surface Nusselt numbers has its maximum outside surface (Y$_{1}$) where there is no interference from each other fin. 4. The mean total Nusselt numbers in case of upward facing fins increase by 47% and 26%, respectively at H/S=0.67 and 1.67 than those in case of downward facing fins for Ra$_{s}$=6.50*10$^{3}$.>.

• 대한기계학회논문집
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• 제14권1호
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• pp.197-206
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• 1990

본 연구에서는 수평등온평면의 가장자리에 주위물의 온도와 동일한 수평등온 평판을 부착한 모델을 사용하여 수평평면 선단의 하부에서 유체가 상부로 유입되는 것 을 방지함으로서 특별한 가정없이 단열평판의 선단에서의 경계조건을 직접 구할 수 있 었다.그리고 기존 밀도식의 복잡성과 신뢰도를 개선한 Gebhart등의 밀도식을 사용 하여 수치해석결과의 신뢰도를 증진하였다. 유한착분법을 사용하여 수평등온평면 주 위에서 일어나는 자연대류에 대한 기배방정식을 수치계산하여 주위물의 온도변화가 유 선분포, 온도분포, 국소열전달계수 및 평균 Nusselt수에 미치는 영향을 구명하였고, 상향 및 하향 수평등온면 주위에서 일어나는 자연대류의 유동형태와 열전달 특성을 비 교 검토하였다.

• Nuclear Engineering and Technology
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• 제38권2호
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• pp.139-146
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• 2006

An experimental study was performed to evaluate the effects of surface coating and an enhanced insulation structure on the downward facing boiling process and the critical heat flux on the outer surface of a hemispherical vessel. Steady-state boiling tests were conducted in the Subscale Boundary Layer Boiling (SBLB) facility using an enhanced vessel/insulation design for the cases with and without vessel coatings. Based on the boiling data, CHF correlations were obtained for both plain and coated vessels. It was found that the nucleate boiling rates and the local CHF limits for the case with micro-porous layer coating were consistently higher than those values for a plain vessel at the same angular location. The enhancement in the local CHF limits and nucleate boiling rates was mainly due to the micro-porous layer coating that increased the local liquid supply rate toward the vaporization sites on the vessel surface. For the case with thermal insulation, the local CHF limit tended to increase from the bottom center at first, then decrease toward the minimum gap location, and finally increase toward the equator. This non-monotonic behavior, which differed significantly from the case without thermal insulation, was evidently due to the local variation of the two-phase motions in the annular channel between the test vessel and the insulation structure.

• Nuclear Engineering and Technology
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• 제48권4호
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• pp.915-924
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• 2016

After a severe accident to the nuclear reactor, the in-vessel retention strategy is a key way to prevent the leakage of radioactive material. Nanofluid is a steady suspension used to improve heat-transfer characteristics of working fluids, formed by adding solid particles with diameters below 100nm to the base fluids, and its thermal physical properties and heat-transfer characteristics are much different from the conventional working fluids. Thus, nanofluids with appropriate nanoparticle type and volume concentration can enhance the heat-transfer process. In this study, the moving particle semi-implicit method-meshless advection using flow-directional local grid method is used to simulate the bubble growth, departure, and sliding on the downward-facing heating surface in pure water and nanofluid (1.0 vol.% $Al_2O_3/H_2O$) flow boiling processes; additionally, the bubble critical departure angle and sliding characteristics and their influence are also investigated. The results indicate that the bubble in nanofluid departs from the heating surface more easily and the critical departure inclined angle of nanofluid is greater than that of pure water. In addition, the influence of nanofluid on bubble sliding is not significant compared with pure water.

• Nuclear Engineering and Technology
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• 제49권1호
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• pp.124-133
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• 2017

In-vessel retention by passive external reactor vessel cooling under severe accident conditions is a viable approach for retention of radioactive core melt within the reactor vessel. In this study, a new and versatile coating technique known as "cold spray" that can readily be applied to operating and advanced reactors was developed to form a microporous coating on the outer surface of a simulated reactor lower head. Quenching experiments were performed under simulated in-vessel retention by passive external reactor vessel cooling conditions using test vessels with and without cold spray coatings. Quantitative measurements show that for all angular locations on the vessel outer surface, the local critical heat flux (CHF) values for the coated vessel were consistently higher than the corresponding CHF values for the bare vessel. However, it was also observed for both coated and uncoated surfaces that the local rate of boiling and local CHF limit vary appreciably along the outer surface of the test vessel. Nonetheless, results of this intriguing study clearly show that the use of cold spray coatings could enhance the local CHF limit for downward-facing boiling by > 88%.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 추계학술발표회요약집
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• pp.185-185
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• 2002