• Nuclear Engineering and Technology
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• 제54권3호
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• pp.1126-1135
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• 2022

The MARS code has been assessed for the prediction of onset of flow instability (OFI) in a vertical channel. For assessment, we built an experiment database that consists of experiments under various geometry and thermal-hydraulic condition. It covers pressure from 0.12 to 1.73 MPa; heat flux from 0.67 to 3.48 MW/m²; inlet sub-cooling from 39 to 166 ℃; hydraulic diameters between 2.37 and 6.45 mm of rectangular channels and pipes. It was shown that the MARS code can predict the OFI mass flux for pipes reasonably well. However, it could not predict the OFI in a rectangular channel well with a mean absolute percentage error of 8.77%. In the cases of rectangular channels, the error tends to depend on the hydraulic diameter. Because the OFI is directly related to the subcooled boiling in a flow channel, we suggest a modified subcooled boiling model for better prediction of OFI in a rectangular channel; the net vapor generation (NVG) model and the modified wall evaporation model were modified so that the effect of hydraulic diameter and heat flux can be accurately considered. The assessment of the modified model shows the prediction of OFI mass flux for rectangular channels is greatly improved.

• Nuclear Engineering and Technology
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• 제25권1호
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• pp.91-101
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• 1993

가압경수로형 원자로의 정상 비정상 운전시의 열수력학적 거동을 예측하기 위해서는 원자로내기포계수의 분포를 정확히 계산하는 것이 필수적이다. 이러한 기포계수의 정확한 예측을 위하여 많은 모델들이 제시되었다. 이중 drift-flux모델은 그 계산의 정확성과 간결성에 의하여 널리 사용되고 있다. 이러한 drift-flux 모델을 사용하여 보다 더 정확한 기포계수를 예측하기 위해서는 각 상간의 슬립률과 flow regime 에 따른 기포의 운동의 변화가 정확히 고려되어야 한다. Drift-flux 모델에서는 이러한 두 가지 요소가 drift-flux parameter인 $C_{o}$ 와 (equation omitted), 에서 고려된다. 본 연구에서는 이러한 $C_{o}$ 의 실험적 결정을 위하여 원자로 노심을 모사한 4개의 전열봉이 있는 비등이 발생하는 수직사각 유로를 구성하였으며, 완성된 유로내에서 기포계수의 분포 및 기포속도의 분포를 측정하였다. 국부적 기포계수 및 기포속도 분포의 측정에 사용된 방법은 이중탐침법이며 측정이 이루어진 유로내의 유동 상태는 유속이 비교적 느린 low flow rate condition이며 유로내 압력은 3기압 이하이다. 본 실험에서는 액상의 속도는 측정되지 않았으며, 따라서 $C_{o}$ 의 계산을 위하여 (equation omitted)의 실험 상관관계식을 사용하여 유로내 평균 기포계수의 함수로 나타내었다.

• Korean Chemical Engineering Research
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• 제46권3호
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• pp.639-645
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• 2008

십자형 응집-한외여과 막분리 공정 운전시 응집조건에 따른 영향을 살펴보면 급속교반-UF 공정과 응집-침전-UF 공정에서 투과 flux의 변화는 크게 나타나지 않았으며 UF막의 막오염 억제 측면에서는 응집전처리공정으로서 1분간의 짧은 급속혼화만으로도 충분한 것으로 나타났다. 교반강도에 따른 투과 flux의 변화결과 교반강도에 따라 형성되는 floc의 크기가 거의 유사하게 형성되어 교반강도에 따른 영향은 나타나지 않았다. 응집제 주입량에 따른 투과 flux변화를 살펴보면 응집제 주입량이 증가함에 따라 유기물의 제거가 크게 일어나 유기물 부하의 감소와 floc의 크기가 증가함에 따라 다공성 케이크층의 형성에 따른 막저항의 감소로 인하여 투과 flux가 향상되었다. 막의 재질과 전처리 응집공정적용에 따른 여과메카니즘 분석결과 막의 재질에 따라서는 친수성 재질의 막에 비하여 소수성 재질의 막의 경우 막의 공극속으로 입자의 침투가 발생하여 침적 흡착되는 현상과 막의 표면에서 형성되는 cake층에 의한 투과 flux 감소가 주원인이 되었으며 응집공정을 전처리공정으로 적용시 UF단독공정에 비하여 막오염 발생이 저감되었다.

• Nuclear Engineering and Technology
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• 제18권4호
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• pp.273-280
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• 1986

이 연구의 목적은 가혹한 사고후 손상된 원자로심을 모의한 열을 발생하는 데브리층에서의 강제대류 드라이아웃 열유속을 실험적으로 얻고져 한 것이다. 이 연구에서 냉각재 순환장치를 사용하여 대기압하에서 냉각재가 상향 강제대류하는 유도 가열된 강구 입자층에서의 드라이아웃 열유속을 얻었다. 이 실험에서는 주로 강제대류 드라이아웃에 대한 질량유속.입자크기.입자층의 높이 및 냉각재의 서브클링의 영향이 관찰되었다. 실험은 입자직경이 1.5, 2.5, 3.0 및 4.0mm의 탄소강입자를 55mm 내경의 Pyrex 유리용기에 넣어 고주파유도 전류를 통해 가열하여 이루어졌다. 냉각재로서 증류수를 질량유속 0~3.5kg/$m^2$s로 변화시키어 공금하고 층의 높이는 55mm와 110mm, 냉각재 유입온도는 2$0^{\circ}C$와 8$0^{\circ}C$로 변화시켰다. 주요 실험결과는 다음과 같다. (1) 드라이아웃 열유속은 상향 강제 대류 질량유속과 입자크기내의 증가에 따라 증가한다. (2) 질량유속이 없는 경우 드라이아웃 열유속은 기존 연구결과와 같이 입자직경에 의존한다. (3) 얕은 입자층에서의 드라이아웃 열유속은 깊은 입자층의 것보다 얼마간 높다.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 1996년도 추계학술대회 논문집
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• pp.255-259
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• 1996

This paper describes a system for measurement and control of a gas flow. In order to measure the flux of gas and control a vavle according to flux, this system was developed. This system is implemented on the personal computer and its environment is developed tool called TMS. This system includes a main program and Tele-Metering Unit for transmitting correcting flow value based on temperature and pressure in flow computer and AD converter for transmitting instantaneous flow rate, temperature and pressure as interface part of personal computer. This system was made by Visual C++ program. Using this system, inspected data for the recognition of transmitting flow value are generated on the screen, file and printer. The activity, reliability of this system was verified on Daegu-Citygas that aids the system for the acquisition of inspected data by realtime application.

• 한국마린엔지니어링학회:학술대회논문집
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• 한국마린엔지니어링학회 2011년도 전기공동학술대회 논문집
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• pp.309-309
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• 2011

This paper outlines extraction potential of tidal stream resources from the simplified channel in which flow is driven by a head difference between inlet and outlet. Energy extraction alters the flow within a simple channel, and extraction of 10% energy flux in a natural channel would give rise to a flow speed reduction of about 5.7%.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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• pp.386-391
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• 1997

It is important to understand correctly a CHF under low flow condition for the purpose of enhancing the reactor safety and performance in the LWRs. The CHF experiments have been carried out for an internally heated vertical annulus in RCS loop facility. The experimental conditions cover ranges of pressure from 1.82 to 12.08 MPa, mass flux from 300 to 550kg/$m^2$. s and inlet subcooling of 210kJ/kg. The CHF data decrease with increasing pressure at high value of mass flux. For mass flux of about 300kg/$m^2$. s, the CHF rue little influenced by pressure. The CHF data are correlated well by using the dimensionless heat flux and dimensionless mass flux for a fixed inlet subcooling except the data group of 12.08 MPa. It seems that the Doerffer correlation and Katto correlation overestimate the CHF for low pressure and lower value of mass flux within this experimental ranges. The Bowling correlation gives a better prediction than the other two correlations.

• Journal of Mechanical Science and Technology
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• 제16권9호
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• pp.1137-1146
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• 2002

An experiment has been conducted on the flow and heat transfer characteristics of film coolant injected from a row of five holes with compound angle orientations of 35$^{\circ}$ inclination angle and 45$^{\circ}$ orientation angle. The Reynolds number based on the mainstream velocity and injection hole diameter 3.58${\times}$10$^4$. Three-dimensional velocity, film cooling effectiveness and heat transfer coefficient data are presented at three different mass flux ratios of 0.5, 1.0 and 2.0. Flow entrainment has been found between the vortices generated by adjacent injectants. The injectant with compound angle orientation entrains not only the mainstream boundary layer flow but also the adjacent injectant. Because of the flow entrainment, the injectant. With compound angle orientation is characterized by a single vortex while two bound vortices are usually observed in the case of simple angle injection. The strength of the secondary flow depends strongly on the mass flux ratio, which shows significant influence on the film cooling effectiveness and heat transfer coefficient.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1604-1615
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• 2023

In an open-pool type research reactor with a downward forced flow in the core, pipes can be under sub-atmospheric pressure because of the large pressure drop at the reactor core in the atmospheric pool. Sub-atmospheric pressure can result in air inflow into the pipe from the pressure difference between the atmosphere and the inside of the pipe, which in a postulated pipe break scenario can lead to the breakdown of the cooling pump. In this study, a plant-scale experiment was conducted to study air inflow in large piping systems by considering the actual operational conditions of an advanced research reactor. The air inflow rate was measured, and the entrained air was visualized to investigate the behavior of air inflow and flow regime depending on the pipe break size. In addition, the developed drift-flux model for a large vertical pipe with a diameter of 600 mm was compared with other correlations. The flow regime transition in a large vertical pipe under downward flow was also studied using the newly developed drift-flux model. Consequently, the characteristics of two-phase flow in a large vertical pipe were found to differ from those in small vertical pipes where liquid recirculation was not dominant.

• 한국전산유체공학회:학술대회논문집
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• 한국전산유체공학회 2006년도 추계 학술대회논문집
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• pp.93-96
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• 2006

The heat transfer enhancement by pulsatile flow in the plate heat exchanger has been investigated numerically in the present study. The numerical study was performed in the range of the mass flux from 0.04 to 0.12 kg/s. The results showed that the pulsatile flow produces resonating vortex shedding at the groove sharp edges and a strong transient vortex rotation within the grooved channels. As a result, the mixing between the trapped volume in the grooved cavity and the main stream was enhanced. Good agreements between the predictions and measured data are obtained in steady flow. And the heat transfer of pulsatile flow is about 2.4 times than steady flow when frequency is 10 Hz and the mass flux of cold side is 0.04 kg/s.