• 수산해양기술연구
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• 제30권1호
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• pp.33-44
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• 1994

This work studies for boiling and condensation heat transfer performance of trapezoidally shaped integral-fin tubes having fin densities from 748fpm to 1654fpm. For comparison, tests are made using a plain tube having the same inside and outside diameter as that of the root of fins of finned tubes. Hahne's theoretical model and Webb's theoretical model are used to predict the R-11 boiling heat transfer coefficient and condensing heat transfer coefficient respectively for plain tube and all integral-fin tubes. Experiments are carried out using R-11 as working fluid. This work is limited to film-wise condensation and pool boiling on the outside surface of plain tube and 4 low integral-fin tubes. In case of condensation, the refrigerant condenses at saturation state of 32$^{\circ}C$ on the outside tube surface cooled by coolant and in case of boiling. the refrigerant evaporates at saturation state of 1bar on the outside tube surface. The amount of non-con-densable gases in the test loop is reduced to a negligible value by repeated purging. The actual boiling and condensing processes occur on the outside tube surfaces. Hence the nature of this surface geometry affects the heat transfer performances of condenser and evaporator in refrigerating system. The condensation heat transfer coefficient of integral-fin tube is enhanced by both extended tube surface area and surface tension. The ratio of the condensation heat transfer coefficients of finned to plain tubes is greater than that of surface area of finned to plain tubes, while ratio of the boiling heat transfer coefficient of finned to plain tubes shows reverse result. As a result, low integral-fin tube can be used in condenser more effectively than used in evaporator.

• 설비공학논문집
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• 제12권5호
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• pp.502-510
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• 2000

Evaporation heat transfer characteristics were studied in a horizontal tube using R22/R114 non-azotropic refrigerant mixture. the heat transfer coefficient was high in the upper part for pure refrigerants, and heat transfer coefficient was low in the lower part for refrigerant mixtures. In the low quality region where nucleate boiling was dominant, the average heat transfer coefficient was low. In the region where forced convection was dominant, heat transfer coefficient was high. Results show that the heat transfer coefficient for pure refrigerants obtained by experiments were lower than those of Yoshida et al. but agreed well with Jung et al., and Chen et al. data. But the heat transfer coefficients for refrigerant mixtures were lower about 20% than those predicted by the equation for pure refrigerant.

• Journal of Advanced Marine Engineering and Technology
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• 제23권5호
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• pp.679-686
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• 1999

This study is to investigate the effect of a substantial drag reduction caused by the polymer(A611P) when the working fluids flow to the vertical direction in the vertical cylindrical equipment of closed flow system. The drag reduction is associated with the mechanical degrada-tion thermal degradation and heat transfer. By ignore the heat fluxs within the closed system the pressure drop due to the polymer concentration the flow velocity and flow time have been mea-sured. By taking into account the mechanical and thermal degradation in the closed system an experiment has been focused on the determination of the condition which could improve the pump capacity in the heat union electric power plant. Under the condition of non-boiling it has been found out that the change of heat flux has little influence on the drag reduction.

• 설비공학논문집
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• 제25권9호
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• pp.484-492
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• 2013

Nucleate pool boiling heat transfer coefficients (HTCs) are measured with HFC32/HFC152a mixture at several compositions. All data are taken at the liquid pool temperature of $7^{\circ}C$, on a horizontal plain square surface of $9.53{\times}9.53$ mm, with heat fluxes of 10 $kW/m^2$ to 100 $kW/m^2$ with an interval of 10 $kW/m^2$, in the increasing order of heat flux. Test results show that the HTCs of these mixtures are up to 45% lower than those of the ideal HTCs calculated by a linear mixing rule with pure fluids' HTCs, due to the mass transfer resistance associated with non-azeotropic refrigerant mixtures. Pool boiling data show the deduction in HTCs with an increase in GTD of the mixture. The present mixture data agree well with five well known correlations, within 20% deviation.

• Nuclear Engineering and Technology
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• 제54권5호
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• pp.1851-1859
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• 2022

Experimental research on flow characteristics of open natural circulation system was performed, to figure out the mechanism of the open natural circulation behaviors. The influence factors, such as the heating power, the inlet subcooled and the level of cooling tank on the flow characteristics of the system were examined. It was shown that within the scope of the experimental conditions, there are five flow types: single-phase stable flow, flash and geyser coexisting unstable flow, flash stable flow, flash unstable flow, and flash and boiling coexisting unstable flow. The geyser flow in flash and geyser coexisting unstable flow is different from classic geysers flow. The flow oscillation period and amplitude of the former are more regular, is a newly discovered flow pattern. By drawing the flow instability boundary diagram and sorting out the flow types, it is found that the two-phase unstable flow is mainly characterized by boiling and flash, which determine the behavior of open natural circulation respectively or jointly. Moreover, compared with full liquid level system, non-full liquid level system is more prone to boiling phenomenon, and the range of heat flux density and undercooling degree corresponding to unstable flow is larger.

• Nuclear Engineering and Technology
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• 제54권5호
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• pp.1860-1873
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• 2022

Nuclear thermal-hydraulic system analysis codes have been developed to comprehensively model nuclear reactor systems to evaluate the safety of a nuclear reactor system. For analyzing complex systems with finite computational resources, system codes usually solve simplified fluid equations for coarsely discretized control volumes with one-dimensional assumptions and replace source terms in the governing equations with constitutive relations. Wall boiling heat transfer models are regarded as essential models in nuclear safety evaluation among many constitutive relations. The wall boiling heat transfer models of two widely used nuclear system codes, RELAP5 and TRACE, are analyzed in this study. It is first described how wall heat transfer models are composed in the two codes. By utilizing the same method described in Part 1 paper, heat fluxes from the two codes are compared under the same thermal-hydraulic conditions. The significant factors for the differences are identified as well as at which conditions the non-negligible difference occurs. Steady-state simulations with both codes are also conducted to confirm how the difference in wall heat transfer models impacts the simulation results.

• 한국자동차공학회논문집
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• 제4권1호
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• pp.187-197
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• 1996

Many investigations have been made to determine the pressure drop and heat transfer characteristics for single phase flow in tape generated swirl flow. But few studies have been carried out to investigate the heat transfer in two component, two phase swirl flow with non-boiling. An experimental study has been conducted to determine the effects of tape twist ratios on two phase convective heat transfer coefficients, pressure drop, and void fraction distribution in a non-boiling, air-water, two phase flow. The flow conditions were both swirl and non swirl flows. The internal diameter of the test section is 42.5mm. The tape twist ratios of pitch to diameter ratio varied from 4.0 to 10.6. The heating conditions were isothermal and nonisothermal. The flow patterns identified with experiments were bubbly, bubbly-slug, slug, and slug-annular flow in up-flow. This study has concluded that no significant difference in void fraction distribution were observed both isothermal and nonisothermal conditions, the pressure drop for two phase flow with twisted tape swirler increase as the tape twist ratio decrease, and that values of two phase heat transfer coefficient increase when the tape twist ratio decreases.

• 동아시아식생활학회지
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• 제8권2호
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• pp.81-92
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• 1998

The pharmaceutical effects of non-alcoholic berverages made made in Limwonsibyukgi were studied. The type of beverage in Limwonsibyukgi were Tang(boiled herb extract), Ta(tea analog with/ without green tea), Jang(lactic acid fermented beverage), Galsoo and Suksoo. Most receipes for these beverages included boiling leaves, seeds, grains of grasses, trees and cereal, and adding honey and sugar as a sweetener, Each beverage has a pharmaceutical action : thirst elimination, enhancement of physical activity, and treatment of several diseases.

• 대한화학회지
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• 제46권3호
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• pp.252-264
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• 2002

이 연구는 끊는점과 녹는점에 관련된 실험 장치를 교육과정의 변화와 교과서의 유형에 따라 분석하고, 중등 과학교사들을 대상으로 이에 관련된 실험값과 교과서에 제시된 값이 다른 경우에 대한 인식을 조사하였다. 그리고 분별 증류, 온도계 보정의 실험 장치와 실 험 결과에 대한 인식도 조사하였다. 연구 결과, 교유고가정과 교과서의 종류에따라 끓는점과 녹는점에 관련된 실험 장치의 유형은 다양하게 변화되어 왔으며, 교사들의 인식도 전공과 근무 학교에 따라 다양하게 나타났다. 또한, 많은 교사들이 분별 증류 실험에서 실험값이 교과서에 제시된 값과 다른 원인을 교과서 내용의 잘못이나 실험 자체의 문제로 인식하고 있었다. 그리고 중학교에서 온도계 보정의 필요성에 대한 교사들의 인식은 다양하게 나타났는데, 화학을 전공한 교사들이 비화학 전공교사들보다 온도계 보정 필요성에 대한 인식이 더욱 높았다.

• 마이크로전자및패키징학회지
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• 제28권2호
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• pp.45-50
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• 2021

Flip chip 제품의 난이도 증가에 따라 solder wetting 및 신뢰성 관점에서 강점을 갖는 flux 소재에 대한 관심이 높아지고 있다. 지용성 flux의 경우 별도의 세정 공정이 없기 때문에 공정 효율화 측면에서 유리하나, 리플로우 공정이후 반응을 마친 잔여물이 잔존하게 되는 경우 Cu migration 및 delamination을 발생시킬 수 있다. 본 연구에서는 저잔사 flux 구현을 위해 신규 resin에 적합한 solvent 및 activator를 변경 하였으며, package 환경에서 non-wet 및 신뢰성 개선 유무를 확인하였다. 저장 안정성 평가를 통해 신규 소재에 대한 안정성을 확보하였으며, boiling point가 상이한 solvent와 activator 2종 적용 및 activator 함량 증대를 통해 non-wet 미 발생 flux 소재를 확보하였다. 해당 소재에 대한 신뢰성 검증 이후 평면 분석 결과 flux residue 기인성 delamination 현상은 발견되지 않았으며, 이를 통해 저잔사 flux에 대한 최종 조성을 확보하였다.