• Proceedings of the Korea Society for Energy Engineering kosee Conference
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• 1998.05a
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• pp.95-103
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• 1998

오늘날 전기 철도 차량의 속도제어방식에는 A.C모터의 속도를 제어하는 방식을 많이 사용하고 있고 이 경우 여러 개의 GTO thyristor와 다이오드가 필요하다. 그런데 이러한 반도체 소자들은 전기 부하의 일부를 저항열로 소모하며 반도체의 용량에 따라 차이가 있으나 전기 철도 차량의 경우 약 1~2㎾의 열이 발생한다. 따라서 이들 소자들이 적정온도범위(100~12$0^{\circ}C$미만)를 유지하기 위해서는 소자의 내부저항열을 외부로 방출시켜야 한다. 지난 30여 년 동안 이러한 반도체 소자 냉각에는 강제대류, 침적 비등, 히트파이프식 냉각방법이 적용되어 왔다. 최근에는 히트파이프식 냉각방법이 유지보수, 크기 및 중량 등 여러 측면에서 상대적으로 유리하기 때문에 히트파이프식 냉각방법을 주로 사용하고 있다. (중략)

• 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 Korean Society of Propulsion Engineers
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• v.22 no.1
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• pp.1-6
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• 2018

Temperatures of cryogenic nitrogen jet inside an injector and at three different downstream positions (0.9, 10.6, and 28.1d) were measured with thermocouples in sub- and supercritical states. The jet temperature decreased while cooling the supply line and injector. The jet experienced from flash boiling, boiling and then no boiling according to decreasing temperature. As an analogy to flash-boiling at the subcritical state, pseudo-flash boiling has been assumed considering the existence of pseudo-boiling at the supercritical state. By showing an area where the temperature did not increase downstream, the plausibility of pseudo-flash boiling is proposed.

• Journal of ILASS-Korea
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• v.13 no.3
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• pp.143-148
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• 2008

In the present study, the correlation between the Nusselt number and Reynolds number was developed for forced convection and nucleate boiling region in spray cooling. Also the effect of droplet subcooling on spray cooling heat transfer was investigated. Full cone spray nozzles were employed for spray cooling experiment, and water and FC-77 were used for developing the correlation. From the experimental results, the correlation between the Nusselt number and Reynolds number based on droplet-flow-rate was developed. The correlation shows good predictions with ${\pm}30%$ error for water and FC-77.

• 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.

• Journal of the korean Society of Automotive Engineers
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• v.15 no.1
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• pp.17-24
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• 1993

사출성형 문제는 열전달과 유체유동이 복합된 문제라고 할수 있다. 사출성형 공정은 충진(filling), 보압(packing) 및 냉각과정(cooling phase)으로 이루어 진다. 충진과정은 높은 점성의 Non-Newtonian유체가 몰드내의 캐버티로 사출됨으로써 이루어지며 플라스틱의 점성도는 플라스틱의 온도 및 유동속도와 관련이 크며 이 flow-rate는 점도와 더불어 변화한다. CAE 유동해석 프로그램은 유체의 흐름과 열전달을 이용하여 충진과정을 이해하는데 이용되고 있다. 본 고에서는 사출성형 과정 중 충진과정에 대한 컴퓨터 시뮬레이션과 그 적용사례에 대하여 살펴본다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.707-712
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• 1996

중대사고시 원자로 압력용기내 또는 원자로 공동(cavity) 내에서의 노심용융물은 주입되는 물로 인하여 물과 접촉하는 표면이 냉각되면서 피막층(crust)이 형성된다. 이러한 피막층의 형성은 노심용융물과 냉각수 사이의 열전달 현상에 영향을 미치며 중대사고 발생시 사고 진행에 중요한 역할을 한다. 본 연구에서는 이러한 용융물의 피막층 형성의 해석모델을 수립하기 위해 전이현상과 전도와 대류를 포함하는 2차원 열전달과 상변화를 수반하는 문제를 포함하는 운동량방정식과 에너지방정식을 2차원으로 구성하였으며 에너지방정식은 엔탈피의 함수로 나타내었다. 그리고 이러한 2차원 지배방정식을 해석하기 위해 유한차분법 및 SIMPIER 알고리즘을 이용하였다. 비교대상으로는 한국원자력연구소에서 수행한 냉각수의 비등과 기체주입 효과가 고려되지 않은 실험을 대상으로 하였다. 계산결과 용융물의 피막층은 파동(wave) 형태로 형성되었으며 일정시간이 경과하면 변화가 없는 안정한 상태가 되었다. 용융물 내에서의 온도분포는 액체상태일 경우에는 하부가열면과 상변화가 일어나는 경계면부근을 제외하고는 거의 일정한 온도분포를 나타내고 있으며 용융물이 고화된 피막층에서는 급격한 온도변화를 보여주고 있다.

• Nuclear Engineering and Technology
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• v.25 no.1
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• pp.8-19
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• 1993

The natural convection model of the consolidated system has been developed to make sure the removal of decay heat generated in the spent fuel for the loss of forced cooling accident. The numerical technique employed was based on the ADI scheme. The calculation of heat generation rate in the spent fuel was peformed by the ANS-79 decay heat model, and the nonuniform surface heat flux is assumed with a chopped sine curve for the conservative decay heat generation input. The sensitivity study was performed to examine the possibility of the pool bulk boiling by varying the various parameters, i.e. inter-fuel spacing ratio, heat generation power, and radius of the fuel rod. The application results of this model show that the natural circulation flow through compacted spent fuel bundles enables the pool temperature to control in a safe and effective manner, after the required cooling time. The corresponding acceptance criteria of the cooling time for rearranging the spent fuel rods were also found.

• Journal of the Korean Society of Manufacturing Technology Engineers
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• v.8 no.4
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• pp.68-78
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• 1999

Heat transfer performance is studied for boiling and condensation of R-11 on integral-fin tubes. Nine tubes with trapezoidal integral-fins having fin densities from 748 to 1654fpm and 10,30 grooves and finned tubes with caves of 0.55 and 0.64 mm height respectively are tested. in case of condensation CFC-11 condensates at saturation stat of 32$^{\circ}C$ on the outside surface cooled by inside cooling water flows. And in case of boiling the refrigerant evaporates at a saturation state of 1 bar on the outside tube surface and heat is supplied by hot water which circulates inside of the tube,. The tube having fin transfer coefficient concerns fin tubes with caves show higher valve than low fin tube having find density of 1299fpm and 30grooves. The overall heat transfer coefficient of fin tube with caves is about 5155 W/mK at 2.8m/s of water velocity, The value is abuot 2.7 times higher than plain tube and 1.3 times higher than low fin tube having fin density of 1299fpm and 30 grooves.

• Journal of the Korean Society of Manufacturing Technology Engineers
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• v.8 no.4
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• pp.65-65
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• 1999

Heat transfer performance is studied for boiling and condensation of R-11 on integral-fin tubes. Nine tubes with trapezoidal integral-fins having fin densities from 748 to 1654fpm and 10,30 grooves and finned tubes with caves of 0.55 and 0.64 mm height respectively are tested. in case of condensation CFC-11 condensates at saturation stat of 32℃ on the outside surface cooled by inside cooling water flows. And in case of boiling the refrigerant evaporates at a saturation state of 1 bar on the outside tube surface and heat is supplied by hot water which circulates inside of the tube,. The tube having fin transfer coefficient concerns fin tubes with caves show higher valve than low fin tube having find density of 1299fpm and 30grooves. The overall heat transfer coefficient of fin tube with caves is about 5155 W/mK at 2.8m/s of water velocity, The value is abuot 2.7 times higher than plain tube and 1.3 times higher than low fin tube having fin density of 1299fpm and 30 grooves.