• 대한기계학회논문집B
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• 제32권2호
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• pp.125-132
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• 2008

The bubble dynamics and heat transfer associated with nucleate boiling in parallel microchannels is studied numerically by solving the equations governing conservation of mass, momentum and energy in the liquid and vapor phases. The liquid-vapor interface is tracked by a level set method which is modified to include the effects of phase change at the interface and contact angle at the wall. Also, the reversible flow observed during flow boiling in parallel microchannels has been investigated. Based on the numerical results, the effects of contact angle, wall superheat and the number of channels on the bubble growth and reversible flow are quantified.

• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1388-1395
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• 2017

The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a key piece of equipment for compact small reactors. The present study developed and verified a thermal-hydraulic design and performance analysis computer code for a countercurrent H-OTSG installed in a small pressurized water reactor. The H-OTSG is represented by one characteristic tube in the model. The secondary side of the H-OTSG is divided into single-phase liquid region, nucleate boiling region, postdryout region, and single-phase vapor region. Different heat transfer correlations and pressure drop correlations are reviewed and applied. To benchmark the developed physical models and the computer code, H-OTSGs developed in Marine Reactor X and System-integrated Modular Advanced ReacTor are simulated by the code, and the results are compared with the design data. The overall characteristics of heat transfer area, temperature distributions, and pressure drops calculated by the code showed general agreement with the published data. The thermal-hydraulic characteristics of a typical countercurrent H-OTSG are analyzed. It is demonstrated that the code can be utilized for design and performance analysis of an H-OTSG.

• 대한기계학회논문집B
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• 제28권8호
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• pp.996-1003
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• 2004

The bubble motion during nucleate boiling in a microchannel is investigated by numerically solving the equations governing conservation of mass, momentum and energy in the liquid and vapor phases. The liquid-vapor interface is tracked by a level set method which is modified to include the effects of phase change at the interface and contact angle at the wall. Also, the evaporative heat flux from the thin liquid film that forms underneath a growing bubble attached to the wall is incorporated in the analysis. Based on the numerical results, the effects of channel size, contact angle, wall superheat and waiting period on the bubble growth and heat transfer in a microchannel are quantified.

• Nuclear Engineering and Technology
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• 제55권9호
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• pp.3164-3182
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• 2023

The CRUD on the fuel cladding under the pressurized water reactor (PWR) operating condition causes several issues. The CRUD can act as thermal resistance and increases the local cladding temperature which accelerate the corrosion process. The hideout of boron inside the CRUD results in axial offset anomaly and reduces the plant's shutdown margin. Recently, there are efforts to revise the acceptance criteria of emergency core cooling systems (ECCS), and additionally require the modeling of the thermal resistance effect of the CRUD during the performance analysis. There is an urgent need for the evaluation of the effect of the CRUD deposition on the cladding heat transfer under PWR operating conditions, but the experimental database is very limited. The experimental facility called DISNY was designed and constructed to analyze the CRUD-related multi-physical phenomena, and the performance analysis of the constructed DISNY facility was conducted. The thermal-hydraulic and water chemistry conditions to simulate the CRUD growth under PWR operating conditions were established. The design characteristics and feasibility of the DISNY facility were validated by the MARS-KS code analysis and separate performance tests. In the current study, detailed design features, design validation results, and future utilization plans of the proposed DISNY facility are presented.

• 설비공학논문집
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• 제27권12호
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• pp.652-658
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• 2015

The Bubble Jet Loop Heat Pipe (BJLHP) is designed to operate in the horizontal orientation. The motion of the bubble generated by boiling working fluid on a heater surface in the evaporating section of the BJLHP helps the working fluid transfer heat to the condensing portion. In this study, we changed the position of the heater in the evaporating section from concentric to eccentric. The concentric heater is located at the center of the tube in the evaporating part, and the eccentric heater is located at the bottom of the inner surface of the same tube. We used R-134a as the working fluid, and the charging ratio was 50%vol. We measured the temperatures of the evaporating and condensing sections by changing the input electric power from 50 W to 200 W, measuring every 50 W. The results of the experiment show that the effective thermal conductivity of BJLHP using an eccentric heater is four times higher than the BJLHP obtained using a concentric heater. Additionally, we conducted a visualization experiment on the evaporating portion of BJLHP to determine why the effective thermal conductivity was higher. The working fluid was water, and we took pictures of the flow visualization for BJLHP. Nucleate boiling with the eccentric heater was more intense and generated more bubbles. Therefore, the eccentric heater was more saturated by the liquefied working fluid.

• 에너지공학
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• 제7권2호
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• pp.194-201
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• 1998

전기 철도 차량의 A.C 모터 속도제어에는 여러 개의 GTO thyristor와 다이오드가 필요하다. 그런데 이러한 반도체 소자들은 약 1~2 kW의 열을 발생하기 때문에 냉각장치가 필요하며 이러한 반도체의 냉각에는 Perfluorocarbon(PFC)을 작동유체로 하는 히트파이프를 많이 사용하고 있다. 본 연구에서는 PFC 히트파이프의 증발 및 응축 열전달 계수에 미치는 관련변수로 주입율, 관의 내부 표면상태, 경사각, 증기압, 열유속 등의 영향을 파악하고, 열전달 계수를 예측할 수 있는 상관식을 제시하고자 하였다. 이를 위해 내부 표면에 그루브가 설치된 동관과 표면이 매끈한 외경 15.88mm인 동관을 이용하여 주입율이 다른 총 길이 520mm의 PFC 히트파이프와 열사이폰을 제작하고 실험을 수행하였다. 증발 열전달 계수는 열유속 15~45 kW/$m^2$의 범위일 때 2 kW/$m^2$K~5.5 kW/$m^2$K 사이의 분포를 보였다. 실험결과는 수정계수 CR=1.3을 적용할 때 Rohsenow의 핵비등 상관식과 실험치가 매우 접근된 결과를 보였으며 이러한 결과는 내부 벽면 그루브의 열전달 촉진효과이다. 응축 열전달 계수의 측정치는 1.5kW/$m^2$K~3.5kW/$m^2$K 사이의 분포를 보였으며 Nusselt 막응축 모델에 수정계수 CN=4를 도입함으로써 매우 접근된 예측이 가능하였다. 증발부 체적에 대한 작동유체 주입율은 40~100%의 범위가 적절하였다. 그리고 30$^{\circ}$이상의 경사각에서는 경사각의 영향이 미소하였다.

• Journal of Mechanical Science and Technology
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• 제17권10호
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• pp.1507-1519
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• 2003

The two-phase flow patterns for both non-loop and loop type oscillating capillary tube heat pipes (OCHPs) were presented in this study. The detailed flow patterns were recorded by a high-speed digital camera for each experimental condition to understand exactly the operation mechanism of the OCHP. The design and operation conditions of the OCHP such as turn number, working fluid, and heat flux were varied. The experimental results showed that the representative flow pattern in the evaporating section of the OCHP was the oscillation of liquid slugs and vapor plugs based on the generation and growth of bubbles by nucleate boiling. As the oscillation of liquid slugs and vapor plugs was very speedy, the flow pattern changed from the capillary slug flow to a pseudo slug flow near the annular flow. The flow of short vapor-liquid slug-train units was the flow pattern in the adiabatic section. In the condensing section, it was the oscillation of liquid slugs and vapor plugs and the circulation of working fluid. The oscillation flow in the loop type OCHP was more active than that in the non-loop type OCHP due to the circulation of working fluid in the OCHP. When the turn number of the OCHP was increased, the oscillation and circulation of working fluid was more active as well as forming the oscillation wave of long liquid slugs and vapor plugs in the OCHP. The oscillation flow of R-142b as the working fluid was more active than that of ethanol and the high efficiency of the heat transfer performance of R -142b was achieved.

• 대한기계학회논문집
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• 제19권6호
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• pp.1518-1528
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• 1995

The deformation and departure processes of a bubble attached to the wall are studied experimentally and numerically to understand the phenomena of the nucleate boiling heat transfer enhancement under DC electric field. An air-bubble is injected in a dielectric liquid with different electric fields generated by changing three types of electrode system (Type 1,2 and 3) in the bubble generator. Experimental variables are the electric field strength and the distance and the shape of the electrodes under DC electric field. From experimental results, it is observed that the bubble under Dc electric field is elongated in the same direction as the electric field and the contact angle increases. For the parallel plate electrode which generates a uniform electric field, bubble departure volume doesn't seem to decrease within our experimental range. However, when a needle is raised a few millimeters from the lower electrode to make a nonuniform electric field around the needle, bubble departure volume decreases continuously with the increase of an applied voltage. The reduction effect of bubble departure volume is the most effective under a strong nonuniform electric field generated with Type 3. As the nonuniformity of the electric field due to the shape of a electrode increases, the terminal velocity and the acceleration of a bubble increase largely. For the comparison with visualization results, the deformation of a bubble attached to the electrode is carried out by a numerical method. Numerical results show good agreement qualitatively with experimental results.

• Nuclear Engineering and Technology
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• 제14권3호
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• pp.122-137
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• 1982

고리 1호기 일부 반응도사고에 대한 민감도 분석을 수행하였다. 본 민감도 분석에 고려한 반응도 사고는 비교적 진행속도가 빠른 사고로서 미임계나 저출력 시동조건에서 발생한 제어뱅크 인출사고와 제어봉 일출사고가 이에 속한다. 본 분석작업은 다음과 같이 세단계로 수행하는 바 원자로 평균출력의 변동 계산과 최고점에서의 열전달계산 그리고 DNBR계산 단계로 나눌 수 있다. 계산에 사용된 전산코드들은 본 분석을 위하여 개발하거나 기존 전산코드들을 수정ㆍ보완하여 제작하였으며 신뢰도도 평가하였다. 원자로 설계 및 운전변수들이 사고발생시 원자로의 거동에 미치는 영향을 조사하기 위하여 민감도 분석을 수행하였다. 본 민감도 분석 결과에 근거하여 고리 1호기 반응도사고 분석에 사용된 최종안전분석보고서의 가정과 초기조건이 타당한가를 조사하였고, 또한 계산 결과도 보수적이고 신뢰할 수 있는지 판별하였다. 고리 1호기 반응도사고 분석에 사용된 가정 및 초기조건을 재검토하고 민감도를 분석한 결과 최종안전분석보고서의 해석결과는 보수적이고 신뢰 할 수 있는 것으로 평가되었다.

• 한국작물학회지
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• 제47권6호
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• pp.395-401
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• 2002

보리의 조숙 품종을 육성하기 위해서는 조기 출수인자에 단기 등숙성 인자를 도입하는 것이 중요하므로 출수기, 성숙기 및 등숙기간의 유전에 관한 정보를 얻고자 4개 품종(사천6호, 오월보리, 동보리1호, Reno), F$_1$, F$_2$세대의 종자를 포장에 파종, 재배하여 출수기, 성숙기 및 등숙기간을 조사하였다. 1. 출수기는 4월 3일-4월 26일, 성숙기는 5월 15일-5월 27일, 등숙기간은 31일-42일로 교배친 및 F$_1$ 조합간 차이가 현저하였다. 2. 부분 이면교잡에 의한 분산분석 결과, 출수기에 대해서 동보리1호(출수기 늦음)는 우성으로, 오월보리는(출수기 빠름) 열성으로, 출수기 유전은 유전자의 상가적 작용이 큰 부분우성으로 나타났다. 3. 성숙기에 대해서 동보리 1호가 우성으로, 오월보리가 열성으로, 성숙기 유전은 유전자의 상가적 작용 큰 부분우성으로 나타났다. 4. 등숙기간에 대해서 Reno(등숙기간이 짧음)가 우성으로 오월보리(등숙기간이 길음)은 열성으로 유전자의 상가적 작용이 큰 부분우성으로 나타났다. 5. 출수기, 성숙기에 대한 일반조합능력의 분산량은 고도의 유의성이 인정되고, GCA분산이 SCA분산보다 출수기는 10.1-29.5배, 성숙기는 9.9-121배 높아서 유전자의 상가적 작용이 컸으며, 사천6호와 오월보리는 출수와 성숙이 빠른 방향으로, 동보리 1호와 Reno은 늦어지는 방향으로 효과를 보였다. 6. 등숙기간에 대해선 GCA 효과는 F$_1$과 F$_2$ 세대간 유의적 차이가 있었고 GCA/SCA비가 크므로 유전자의 상가적 작용이 현저하였다. 7 포장 출수기, 성숙기는 결빙방지 단백질의 농도, 광합성의 광저해에 대한 내성, 포장 내동성과 고도의 정의 상관을, 등숙기간은 각 형질들과 부의 상관을 보였다. was "glossy and smooth" in all cases and preference about the texture was high. The Doenjang with added P. japonica Powder had a saltier taste and the Doenjang with P. japonica Powder had the least sweet taste. In the flavor and overall Preference, the Doenjang with P. japonica powder was the lowestEX>로 측정되었고, 계사내 지붕의 표면 온도는 최고 $29^{\circ}C$가 측정되었다. 계사 내 표면 온도 및 닭의 표면 온도는 계사내 공기온도의 영향을 많이 받는 것으로 나타났다.ill in a good agreement with those predicted by Rohsenow's formula, which was based on nucleate boiling. For the condenser, the wall temperatures were practically uniform, and the measured values of condensation heat transfer coefficient were 1.7 times higher than the predicted values obtained from Nusselt's film condensation theory on tilted plate. Using those two expressions, a correlation was formulated as a function of heat flux and tilt angle, to determine the total thermal resistance of a tilted thermosyphon.