• 대한설비공학회지:설비저널
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• 제15권3호
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• pp.264-272
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• 1986

The performance of vertical and horizontal tubes with multiple fins of rectangular and triangular cross section was investigated theoretically for boiling heat transfer. A simple method for numerical program assuming one-dimensional heat flow was used to predict the performance of these finned tubes and their bundles. The object of the new study was to develop optimum fin design, especially in tube bundles, considering from a viewpoint to minimize the space in which the maximum heat flux density was expected.

• Nuclear Engineering and Technology
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• 제44권4호
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• pp.429-436
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• 2012

Critical heat flux (CHF) is the thermal limit of a phenomenon in which a phase change occurs during heating (such as bubbles forming on a metal surface used to heat water), which suddenly decreases the heat transfer efficiency, thus causing localized overheating of the heating surface. The enhancement of CHF can increase the safety margins and allow operation at higher heat fluxes; thus, it can increase the economy. A very interesting characteristic of nanofluids is their ability to significantly enhance the CHF. Nanofluids are nanotechnology-based colloidal dispersions engineered through the stable suspension of nanoparticles. All experiments were performed in round tubes with an inner diameter of 0.01041 m and a length of 0.5 m under low pressure and low flow (LPLF) conditions at a fixed inlet temperature using water, 0.01 vol.% $Al_2O_3$/water nanofluid, and SiC/water nanofluid. It was found that the CHF of the nanofluids was enhanced and the CHF of the SiC/water nanofluid was more enhanced than that of the $Al_2O_3$/water nanofluid.

• 오토저널
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• 제10권5호
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• pp.69-82
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• 1988

Heat transfer experiment is carried out during the performance test of the 4-cylinder 4-stroke cycle turbo-charged gasoline engine. Cycle simulation employing the measured pressure in cylinder, the cooling water temperature and flow rate and others is carried out in order to calculate the gas temperature in cylinder. In this simulation combustion process was simulated by Annand's two zone model and suction, compression, and other processes are calculated completely. From this simulation, we can obtain not only the heat transfer coefficient but also the flame speed, turbulent burning velocity, flame factor and the boiling condition of cooling passage. The results are investigated with engine speed, equivalence ratio and spark advance.

• 대한기계학회논문집B
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• 제37권4호
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• pp.343-352
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• 2013

본 연구에서는 열전달 표면의 형상과 그 위에서의 유동 속도의 변화에 따른 풀 비등 열전달계수의 변화를 살펴보기 위해 평판, 낮은 핀, Thermoexcel-E, Turbo-B 표면을 사용하여 유동 속도를 변화시켜가며 임계 열유속까지 열전달계수를 측정하였다. 작동 유체로는 증류수를 사용하였고 사각 평면 히터($9.53{\times}9.53mm$)를 이용하여 네 가지 표면에서 임계 열유속까지의 데이터를 얻을 수 있도록 장치를 제작하였고 $60^{\circ}C$에서 유동 속도를 0, 0.1, 0.15, 0.2m/s로 변화시켜가며 데이터를 취했다. 실험 데이터를 보면 모든 표면에서 유동이 있을 때의 임계 열유속은 유동이 없을 때에 비해 높은 것으로 나타났다. 또한 표면적의 증가와 기포 이탈에 충분한 핀 간격 등으로 인해 낮은 핀 표면의 임계 열유속은 평판이나 Turbo-B, Thermoexcel-E 표면보다 훨씬 놓았고 평판에 비해서는 무려 5배 정도의 향상을 보였다. 한편 대형 냉동기의 증발기용으로 개발된 Turbo-B와 Thermoexcel-E 표면은 물에서 기포의 이탈 지름이 크므로 열전달계수와 임계 열유속 모두 예상보다 큰 효과를 나타내지 않았다. $50kW/m^2$이하의 저열유속에서는 모든 표면에 대해 유동 속도 증가에 따라 열전달계수가 증가하였다. 결론적으로 핵발전소의 증기발생기에 적용하기에는 낮은 핀 형상의 표면이 가장 좋은 것으로 나타났다.

• 열처리공학회지
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• 제23권5호
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• pp.249-256
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• 2010

Water jet impingement cooling has been widely used in a various engineering applications; especially in cooling of hot steel plate of steelmaking processes and heat treatment in hot metals as an effective method of removing high heat flux. The effects of cooling water temperature on water jet impingement cooling are primarily investigated for hot steel plate cooling applications in this study. The local heat flux measurements are introduced by a novel experimental technique that has a function of high-temperature heat flux gauge in which test block assemblies are used to measure the heat flux distribution during water jet impingement cooling. The experiments are performed at fixed flow rate and fixed nozzle-to-target spacing. The results show that effects of cooling water temperature on the characteristics of jet impingement heat transfer are presented for five different water temperatures ranged from 5 to $45^{\circ}C$. The local heat flux curves and heat transfer coefficients are also provided with respect to different boiling regimes.

• 한국산학기술학회논문지
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• 제9권3호
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• pp.574-579
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• 2008

수평관내 $CO_2$의 증발 열전달 계수를 실험적으로 조사하였다. 냉매 순환루프의 주요 구성품은 수액기, 변속냉매 펌프, 질량 유량계, 예열기, 증발기(시험부)로 구성된다. 시험부는 내경 4.57 mm의 수평 평활 스텐레스관이다. 실험은 질량유속 $400{\sim}900kg/m^2s$, 포화온도 $5{\sim}20^{\circ}C$, 열유속 $10{\sim}40kW/m^2$인 조건에서 수행하였다. 실험결과로부터 $CO_2$의 열전달은 대류비등보다는 핵비등에 더 많은 영향을 받는 것을 알 수 있었고, $CO_2$의 질량유속은 핵비등에 많은 영향을 미치지 않는 것으로 나타났다. 실험결과와 종래의 상관식을 비교해 본 결과, 기존의 상관식은 실험데이터를 과소예측하였지만, 정 등의 상관식은 좋은 일치를 보였다. 따라서, 수평관내 $CO_2$의 증발 열전달 계수를 예측할 수 있는 정확한 상관식의 개발이 필요하리라 판단된다.

• 항공우주기술
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• 제5권2호
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• pp.134-142
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• 2006

헬륨분사를 통한 극저온 추진제의 과냉각 방식은 발사체의 이륙 전에 액체산소의 bulk boiling을 억제하고 과냉각 상태를 유지하기 위한 효과적인 방법들 중의 하나이다. 본 자료에서는 이러한 헬륨 분사 냉각 시스템에 대한 이론적 고찰을 통해 열전달과 질량전달 조건을 이해하고, 해석 모델을 제시하였다. 해석 모델의 주요 특징은 유한 열전달과 무한질량전달 개념을 이용하여 분사 시스템을 표현한 것이다. 또한, 실험과 해석결과의 비교를 통하여 해석 모델을 검증하였으며, 헬륨 분사량의 변화, 탱크 압력의 변화 등 조건 변화에 따른 결과를 살펴보았다.

• Nuclear Engineering and Technology
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• 제53권12호
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• pp.3918-3929
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• 2021

In this study, we experimentally investigate of a two-phase natural circulation loop that functions as a passive containment cooling system (PCCS). The experimental apparatus comprises two loops: a hot loop, for simulating containment under severe accidents, and a natural circulation loop, for simulating the PCCS. The experiment is conducted by controlling the pressure and inlet temperature of the hot loop in the range of 0.59-0.69 MPa (abs) and 119.6-158.8 ℃, respectively. The heat balance of the hot loop is established and compared with a natural circulation loop to assess the thermal reliability of the experimental apparatus, and an additional system is installed to measure the vapor mass flow rate. Furthermore, the thermal-hydraulic characteristics are considered in terms of a temperature, mass flow rate, heat transfer coefficient (HTC), etc. The flow rate of the natural circulation loop is induced primarily by flashing, and a distortion is observed in the local HTC because of the fully develop as well as subcooled boiling. As a result, we present the amount of heat capacity that the PCCS can passively remove according to the experimental conditions and compared the heat transfer performance using Chen's and Dittus-Boelter correlation.

• Nuclear Engineering and Technology
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• 제42권6호
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• pp.620-635
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• 2010

In this paper we describe current activities on the project Multi-Scale Modeling and Analysis of convective boiling (MSMA), conducted jointly by the Paul Scherrer Institute (PSI) and the Swiss Nuclear Utilities (Swissnuclear). The long-term aim of the MSMA project is to formulate improved closure laws for Computational Fluid Dynamics (CFD) simulations for prediction of convective boiling and eventually of the Critical Heat Flux (CHF). As boiling is controlled by the competition of numerous phenomena at various length and time scales, a multi-scale approach is employed to tackle the problem at different scales. In the MSMA project, the scales on which we focus range from the CFD scale (macro-scale), bubble size scale (meso-scale), liquid micro-layer and triple interline scale (micro-scale), and molecular scale (nano-scale). The current focus of the project is on micro- and meso-scales modeling. The numerical framework comprises a highly efficient, parallel DNS solver, the PSI-BOIL code. The code has incorporated an Immersed Boundary Method (IBM) to tackle complex geometries. For simulation of meso-scales (bubbles), we use the Constrained Interpolation Profile method: Conservative Semi-Lagrangian $2^{nd}$ order (CIP-CSL2). The phase change is described either by applying conventional jump conditions at the interface, or by using the Phase Field (PF) approach. In this work, we present selected results for flows in complex geometry using the IBM, selected bubbly flow simulations using the CIP-CSL2 method and results for phase change using the PF approach. In the subsequent stage of the project, the importance of effects of nano-scale processes on the global boiling heat transfer will be evaluated. To validate the models, more experimental information will be needed in the future, so it is expected that the MSMA project will become the seed for a long-term, combined theoretical and experimental program.

• 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.