• Journal of the Korean Institute of Intelligent Systems
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• v.25 no.2
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• pp.161-167
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• 2015

In this paper, a novel thermoelectric cooling system utilizing condensed water is introduced and its electrical equivalent circuit model is proposed. The introduced system can deals with the condensed water and improves efficiency by spraying the condensed water on heat sink. The electrical equivalent circuit model is derived by combining the circuit model of the classical thermoelectric cooling system with equation of heat exchange. Because the parameters of the model can be defined from not other experimental data but just the data sheet of the thermoelement, the model can be useful to design and develop the controller of the proposed system. We verify that the proposed model is valid and the introduced system is more efficient than the previous thermoelectric cooling system through simulations.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.37 no.12
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• pp.1069-1078
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• 2013

Recently, condensation heat exchangers have been studied for applications to the passive cooling systems of nuclear plants. To design vertical-type condensation heat exchangers in secondary passive cooling systems, TSCON (Thermal Sizing of CONdenser), a thermal sizing program for a condensation heat exchanger, was developed at KAERI (Korea Atomic Energy Research Institute). In this study, the existing condensation heat transfer correlation of TSCON was evaluated using 1,157 collected experimental data points from the heat exchanger of a secondary passive cooling system for the case of pure steam condensation. The investigation showed that the Shah correlation, published in 2009, provided the most satisfactory results for the heat transfer coefficient with a mean absolute error of 34.8%. It is suggested that the Shah correlation is appropriate for designing a condensation heat exchanger in TSCON.

• The Magazine of the Society of Air-Conditioning and Refrigerating Engineers of Korea
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• v.15 no.1
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• pp.67-81
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• 1986

냉각탑, 밀폐식냉각탑, 증발식응축기는 증발식냉각기의 분류에 속한다. 열은 증발에 의해 제거되어, 중력에 따라 유하하는 수 film으로 부터 충전물, 또는 밀폐식냉각탑, 증발식응축기의 관군상을 흐르는 공기에 전달된다. 따라서 공기측에서의 열과 물질의 이동프로세스는 기본적으로는 동일하다. 각 형식에서의 차이는 냉각되는 유체측에서의 열저항의 형태가 다르다는 점이다. 이 무저항은 냉각탑에서는 아주 작으나 다른 두 경우에 있어서는 계산상 고려하지 않으면 안된다. 이 논문은 이들 세 형식에 대해 통일된 이론을 적용할 수 있다는 것을 보여주기 위한 것이다. 그러므로 열 및 물질이동저항의 계산을 위한 식에 대해 논의하고 있다. 또한 복잡성을 피하기 위해, Merkel의 근사식을 공기측의 열 및 물질이동계산에 이용하였다.

• Proceedings of the KIEE Conference
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• 2002.07b
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• pp.747-749
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• 2002

초전도 마그네트 시스템의 냉각방법 중, 액체 헬륨등의 극저온 유체를 이용한 액체냉각방식이 극저온 냉동기를 이용한 직접 전도냉각 방식에 비해 신뢰도가 높은 열적 안정성으로 인하여 현재도 많은 초전도 마그네트 시스템이 액체냉각방식을 이용하고 있다. 그러나, 고가의 극저온 액체의 재충전으로 인하여 경제성이 낮고 취급이 불편한 단점이 있다 이러한 액체냉각방식의 단점을 보완하고자 극저온 유체를 시스템 안에서 직접 응축하여 재충전을 하지 않는 재응축형 시스템을 개발하여 실험하였다. 실험에 사용한 초전도 마그네트 시스템은 상온보아 1270 mm. 최대자장 0.3 T로 설계되었고, 금속 전류도입선과 HTS 전류도입선을 복합적으로 사용하였으며, 복사차폐막 냉각용 극저온 냉동기와 헬륨 재응축용 극저온 냉동기를 사용하였다. 초전도 마그네트는 200 A에서 1600 gauss의 자장으로 운전하였고 극저온 용기에서는 0.05 bar의 압력으로 액체 헬륨이 증발하지 않고 유지되었다.

• Transactions of the Korean Society of Mechanical Engineers
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• v.7 no.3
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• pp.344-352
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• 1983

격납 용기 내에 비응축성 가스(공기)가 존재하는 경우에 증기의 응축 열전달 계수를 평가하는 방 법을 연구하였다. 유일한 대규모 격납 용기 실험인 CVTR자료를 이용하여 응축 열전달 계수를 계산하여, 현재 원자력 발전소의 냉각재 상실 사고(LOCA) 및 주 증기 배관 파열사고(MSLB)시에 격납 용기의 안전 해석에서 공식적으로 사용되고 있는 Tagami와 Uchida열전달 계수 관계식과 비교해 본 결과 좋은 일치를 보여 주었다.

• 월간낙농육우
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• v.17 no.7 s.183
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• pp.119-121
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• 1997

원유 관리에 필수 기기인 냉각기는 하절기에 환기 불량, 응축기 청소 불량, 전기사정 악화 등으로 빈번한 고장이 발생한다. 따라서 사전예방 점검을 하여 원인제거를 하여야하며 또한 우사 환기를 적절히 시켜 고온으로 인한 스트레스를 최소화 하여야 한다. 하절기에 낙농가가 알아야 할 냉각기 및 우사관리 요령에 대하여 알아보기로 하자.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.35 no.12
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• pp.1293-1300
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• 2011

The configurations of the evaporator and condenser of a water chiller can be determined from the trade-off between the heat transfer area, which is related to the capital cost and the pressure drop, which is associated with the operational cost. In this study, the design of the water chiller focused on minimizing the water pressure drop of both condenser and evaporator for given cooling capacity and requirements. Commercial enhanced tubes were employed to simulate real-life conditions. The results of the present analysis were compared with those obtained by HTRI software for verifying them. The results indicated that a reduction in the water pressure drop, which is associated with the short length of a tube, can be effected by decreasing the number of tube passes and increasing the number of tubes and the tube diameter. However, using a large number of tubes with smaller diameters can reduce the capital cost because the tubes are short. The reduction of the capital cost is due to the fact that a small-diameter tube has low internal thermal resistance and hence contributes to a decrease in the overall thermal resistance per unit length.

• Journal of Energy Engineering
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• v.24 no.1
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• pp.42-50
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• 2015

To evaluate the heat removal capability of a condenser tube in the PCCS of an advanced nuclear power plant, a steam condensation experiment in the presence of noncondensable gas on a vertical tube is performed. The average heat transfer coefficient is measured on a vertical tube of 40 mm in O.D. and 1.0 m in length. The experiments covers the pressures of 2-4 bar, and the mass fraction of air ranges from 0.1 up to 0.7. From the experimental results, the effects of the total pressure and the concentration of air on the condensation heat transfer coefficient are investigated. The measured data are compared with the predictions by Uchida's and Tagami's correlations, and it is revealed that these models underestimate the condensation heat transfer coefficient of the steam-air mixture.

• Journal of Energy Engineering
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• v.27 no.4
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• pp.27-35
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• 2018

The passive containment cooling system (PCCS) has been designed to remove the released decay heat during the accident by means of the condensation heat transfer phenomenon to guarantee the safety of the nuclear power plant. The heat removal performance of the PCCS is mainly governed by the condensation heat transfer of the steam-air mixture. In this study, the heat removal performance of the PCCS was evaluated by using the MARS-KS code with a new empirical correlation for steam condensation in the presence of a noncondensable gas. A new empirical correlation implemented into the MARS-KS code was developed as a function of parameters that affect the condensation heat transfer coefficient, such as the pressure, the wall subcooling, the noncondensable gas mass fraction and the aspect ratio of the condenser tube. The empirical correlation was applied to the MARS-KS code to replace the default Colburn-Hougen model. The various thermal-hydraulic parameters during the operation of the PCCS follonwing a large-break loss-of-coolant-accident were analyzed. The transient pressure behavior inside the containment from the MARS-KS with the empirical correlation was compared with calculated with the Colburn-Hougen model.

• Nuclear Engineering and Technology
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• v.21 no.4
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• pp.308-320
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• 1989

The objective of this work is to investigate the effects of diminished primary coolant inventory and the presence of noncondensible gas during single- and two-phase natural circulation in a PWR loop model. The test model was composed of two loops with a U-tube heat exchanger in each loop. Through a series of tests, it has been confirmed that the two-phase natural circulation flow rates were greatly dependent on primary coolant inventory as previous investigators observed. The primary coolant inventory limit to maintain two-phase natural circulation was found to be the amount of the coolant necessary to keep the waterline of the coolant nozzle hole center in this model. The presence of noncondensible gas impede the single-phase natural circulation, but it did not affect the two-phase natural circulation significantly.