• Journal of the KSME
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• v.24 no.2
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• pp.92-98
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• 1984

열전달영역은 임계열류속점(CHF)을 기준으로 pre-CHF 영역과 post-CHF 영역의 두가지로 대 별된다. Post-CHF 영역에 해당하는 열전달에는 천이비등열전달과 막비등열전달이 있으며 천 이비등은 CHF점과 최소 막비등점 사이에서 일어나는 현상으로 핵비등과 막비등이 조합된 열 전달 기구에 해당하고 막비등은 가열표면이 안정된 증기막에 의해 덮여 있는 상태의 열전달 기 구에 속한다. 전고에서는 pre-CHF와 CHF 열전달 영역의 특성을 살펴보았고 본고에서는 천이 비등과 최소막비등온도 및 막비등에서의 열전달 상관식의 특성을 살펴 보고자 한다.

• Transactions of the Korean Society of Mechanical Engineers
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• v.16 no.1
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• pp.87-94
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• 1992

Film boiling heat transfer characteristics in liquid-liquid systems are studied experimentally. Liquid gallium as a heating liquid, n-pentane, freon-113, and ethanol are used as boiling liquids. In gallium-n-pentane and gallium-freon-113 systems the minimum film boiling point occurred at higher temperature than those observed in copper-boiling liquid systems. However MFB point occurred almost at the same temperature for the case of ethanol. This difference are due to the effects of contact angle and interfacial agitations in gallium-boiling liquid systems. Film boiling heat transfer rate, for the gallium-boiling liquid systems considered in this work, found to be approximately 10% higher than those in copper-boiling liquid systems, whose main cause is believed to be gallium-boiling liquid interfacial agitations affected by the density ratio between gallium and boiling liquid.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.41 no.9
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• pp.597-603
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• 2017

In this study, experiments were conducted on the MFB(minimum film boiling) point of highly heated vertical metal rod quenched in aqueous surfactant solution at various temperature conditions. The aqueous Triton X-100 solution(100 wppm) and pure water were used as the liquid pool. Their temperatures ranged from $77^{\circ}C$ to $100^{\circ}C$. A stainless steel vertical rod of initial center temperature of $500^{\circ}C$ was used as a test specimen. In both liquid pools, as the liquid temperature decreased, the time to reach the MFB point decreased with a parallel increase in the temperature and heat flux of the MFB point. However, over the whole present temperature range, in the aqueous Triton X-100 solution, the time to reach the MFB point was longer, while the temperature and heat flux of the MFB point were reduced when compared with pure water. Based on the present experimental data, this study proposed the empirical correlations to predict the MFB temperature of a high temperature vertical metal rod in pure water and in aqueous Triton X-100 solution.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.22 no.5
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• pp.554-560
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• 2021

CRUD (chalk river unidentified deposits) is a porous material deposited on the surface of nuclear fuel during nuclear power plant operation. The CRUD is composed of metal oxides, such as iron, nickel, and chromium. It is essential to investigate the effects of the CRUD layer on the wall heat transfer between the nuclear fuel surface and the coolant in the event of a nuclear accident. CRUD only negatively affects the temperature of the nuclear fuel due to heat resistance because the effects of the CRUD layer on two-phase boiling heat transfer are not considered. In this study, the physical property models for the porous CRUD layer were developed and implemented into the SPACE code. The effects of boiling heat transfer models on the peak cladding temperature and quenching were investigated by simulating a reflood experiment. The calculation results showed some positive effects of the CRUD layer.

• 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.

• Nuclear Engineering and Technology
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• v.27 no.4
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• pp.544-554
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• 1995

Pool boiling of dilute aqueous solutions of polyethylene oxide polymer has been experimentally investigated for the purpose of understanding the physical mechanisms of the suppression of vapor explosions in this polymer solution. Tn solid spheres of 22.2mm and 9.5mm-diameter ore heat-ed and quenched in the polymer solutions of various concentrations at 3$0^{\circ}C$. The results showed that minimum film boiling temperature($\Delta$ $T_{MFB}$) in this highly-subcooled liquid rapidly decreased from over $700^{\circ}C$ for pure water to about 15$0^{\circ}C$ as the polymer concentration was increased up to 300ppm for 22.2mm sphere, and it decreased to 35$0^{\circ}C$ for 9.5mm sphere. This large decrease of minimum film boiling temperature in this aqueous polymer solution may explain its ability to suppress spontaneous vapor explosions. Also, tests with applying a pressure wave showed that the vapor film behaved more stable against an external disturbance at higher polymer concentrations. These observations together with the experimental evidences of vapor explosion suppression in dilute polymer solutions suggest that the application of polymeric additives such as polyethylene oxide as low as 300ppm to reactor emergency coolant be considered to prevent or mitigate energetic fuel-coolant interactions during severe reactor accidents.s.

• Proceedings of the Optical Society of Korea Conference
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• 1998.08a
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• pp.196-197
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• 1998

• Proceedings of the Korean Vacuum Society Conference
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• 2016.02a
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• pp.383.2-383.2
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• 2016

임계 열유속 현상은 열전달 시스템에서 가열조건이나 유동조건이 변함에 따라 열전달 표면 부근의 유체상태가 액체에서 기체로 바뀌면서 열전달계수가 급격히 감소하는 현상을 말한다. 임계 열유속 발생 시 핵 비등 영역에서 순간적으로 막 비등 영역으로 넘어가면서 원전 시스템의 물리적 파괴를 일으킬 수 있게 된다. 따라서 임계 열유속 현상은 시스템 설계 및 안전해석 뿐만 아니라, 열교환 및 냉각 장치 설계에서 중요하게 고려되고 있다. 특히, 비등 열전달 시스템에서 임계 열유속 발생 시 시스템의 물리적 손상을 야기하게 된다. 따라서 원전 시스템을 보호하면서 성능을 극대화시키기 위해서는 임계 열유속 향상이 필수적이며, 임계 열유속 향상을 위한 대안 중 하나로서 열적 특성이 우수한 나노유체를 열전달 시스템에 적용하여 임계 열유속 향상을 위한 연구가 지속되고 있다. 따라서 본 연구에서는 산화 처리된 다중벽 탄소나노튜브 나노유체를 사용하여 각각 0.5 m/s, 1.0 m/s, 1.5 m/s의 유속에서 임계 열유속과 열전달 계수를 측정하였다. 그 결과 산화 처리된 다중벽 탄소나노튜브 나노유체의 유속이 증가 할수록 임계 열유속이 증가하는 것을 확인 하였으며, 순수물과 비교하여 최대 62.64% 증가함을 확인하였다. 그리고 산화 처리된 다중벽 탄소나노튜브 나노유체의 비등 열전달 계수 또한 유속이 증가 할수록 비등 열전달 계수가 증가하는 것을 확인하였며 최대 24.29% 증가함을 확인하였다.

• Korean Journal of Air-Conditioning and Refrigeration Engineering
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• v.12 no.9
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• pp.835-842
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• 2000

Film boiling heat transfer of the subcooled turbulent liquid film flow on a horizontal plate was investigated by theoretical and experimental studies. In the theoretical analysis, by solving the integral energy and momentum equations analytically, some generalized expressions for Nusselt number was deduced. Next, by comparing the deduced equations with the experimental data on the turbulent film boiling heat transfer of the subcooled thin liquid film flow, the semi-empirical relation between the Nusselt number based on the modified heat transfer coefficient and the Reynolds number was obtained. The correlating equation was very similar to that of the turbulent heat transfer in a single phase flow, and it was found that the heat transfer was dissipated to increase the liquid temperature.

• Proceedings of the KSME Conference
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• 2004.11a
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• pp.1317-1322
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• 2004

In this report, the heat transfer model of spray cooling on hot surface was developed by focusing on the effect of rebound motion of droplets. In the model, it was assumed that droplets rebound repeatedly on the hot surface and heat transfer upon droplet impact is proportional to sensible heat which heats up the droplets to the saturation temperature. In addition, to take account of the contribution of th heat flux upon impact of rebound droplets, it was assumed that the rebound droplets are distributed following the Gaussian distribution from 0 to L, which distance L is determined by maximum flight distance $L_{max}$. Also the calculated results were compared with existing experimental results.