• 소성∙가공
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• 제23권7호
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• pp.405-412
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• 2014

As a major type of heat exchanger, the steam generator (SG) produces steam from heat energy of a nuclear power plant reactor. The steam produced by the steam generator flows into a turbine, and plays an important role in electric power generation. The heat transfer tubes in the steam generator consist of approximately 10,000 U-shaped tubes, which perform a structural role and act as thermal boundaries. The heat transfer tubes conduct the thermal energy between the primary coolant (about $320^{\circ}C$, $157kgf/cm^2$) obtained from the reactor and the secondary coolant (about $260^{\circ}C$, $60kgf/cm^2$) as part of the secondary system. Recently, the heat transfer tubes in the steam generator of the pressurized water reactor (PWR) are primarily produced from Alloy 600 and Alloy 690 seamless tubes. As a pilot study to find process parameters for the cold U-bending process using rotary draw bending, numerical and experimental investigations were conducted to produce U-shaped tubes from long straight SUS304L seamless tubes. 3D finite element simulations were run using ABAQUS Explicit with consideration of the elastic recovery. The process parameters studied were the angular speed, the operation period and the bending angle. Experimental verifications were conducted to insure the suitability of the final U-shaped configurations with respect to both ovality and wall thickness.

• 한국산학기술학회논문지
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• 제17권12호
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• pp.723-729
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• 2016

본 연구에서는 핀-관형 히트파이프와 평행류형 히트파이프 제작하여 시험하였으며 분리형 히트파이프의 작동유체의 충진량은 40~60(% vol.), 풍량은 300~1,400 사이에서 변화시켜가며 온도교환 효율, 열회수량, 공기측 압력강하를 비교하였다. 온도교환 효율은 두 종류의 히트파이프 모든 경우에서 저 풍량에서는 작동유체 충진량이 40(%vol.)일 때가 가장 높았으며 풍량이 증가함에 따라 최대 효율을 가지는 작동유체 충진량이 다름을 알 수 있었고, 환기량이 작을수록 온도교환 효율이 높게 나타났다. 평행류형 히트파이프 60(%vol.)의 실험결과에서 보는 것과 같이 작동 유체를 너무 많이 충진하게 되면 오히려 낮은 온도교환 효율을 보이는데 이는 관벽의 액막이 두터워지면서 열전달 효과를 악화시킨 결과로 최적 충진량이 40~50(%vol.) 사이에 있음을 알 수 있다. 풍량 변화에 따른 공기측 압력강하 비교에서는 증발부 히트파이프가 응축부 히트파이프 보다 크게 계측 되었는데 증발부 표면에 생긴 결로수의 영향으로 생각된다. 평행류형 히트파이프는 핀-관형 히트파이프와 비교하여 냉매 충진량은 48%, 체적은 41%에서 동등이상의 성능을 보였으며, 공기측 압력강하도 37% 정도로 좋은 성능을 나타내었다.

• 조명전기설비학회논문지
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• 제20권7호
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• pp.58-64
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• 2006

최근 탈취, 탈색, 정수처리 및 배연가스의 정화에 많이 이용되고 있는 오존의 효과적인 발생에 많은 관심이 모아지고 있다. 전기 방전에 의한 오존 발생 방법 중 유전체 배리어 방전이 보다 낮은 전력을 소모하며, 또한 저전압 동작이 가능하여 가장 효과적인 것으로 생각되고 있다. 본 연구에서는 오존발생농도 및 에너지효율을 개선하기 위하여 알루미나 유전체 및 알루미나 유전체와 알루미나 비드를 충진한 무성방전관을 제작하여 무성방전특성을 연구하였다. 또한 오존발생특성을 무성방전특성과 연관하여 논하였으며, 특히 방전시 유전체에 축적되는 벽전하 및 소비전력특성의 관점에서 논하였다. 결과, 비드를 가진 방전관의 경우 축적되는 벽전하량은 비드가 없는 방전관에 비하여 약 2.5배 정도였으며, 발생되는 오존농도 및 에너지 수율 또한 개선되었다.

• 한국실내디자인학회논문집
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• 제36호
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• pp.14-21
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• 2003

The Propose of this research was to consider how the New Media Architecture was applied to contemporary architecture according to the analysis of the design method process of Toyo Ito. Sendai Mediatheque by Toyo Ito stands as one of the most symbolic statement In New Media architecture. The four principal architectural elements of the Mediatheque are the digital image, the continuous space, the tube, and the skin facade. The digital image express forms of communication, person-to-person and person-to-thing, and they vary according to the media utilized on each level. The three skin elements of the Mediatheque are a double skin of MPG, skin of louvers, skin of fine-floor decking. The tubes act as columns while enveloping light, air, water, electricity the passage of people, as well as the means of transferring material. The thirteen tubes of different sizes prevent the erection of wall and suggest places instead of rooms. Instead of being limited to certain specified actions in clearly defined rooms, people are free to choose places for their actions in the continuous space.

• Journal of Electrical Engineering and Technology
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• 제12권4호
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• pp.1406-1416
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• 2017

In complex and large-scale industries, properly designed fault detection and identification (FDI) systems considerably improve safety, reliability and availability of target processes. In thermal power plants (TPPs), generating units operate under very dangerous conditions; system failures can cause severe loss of life and property. In this paper, we propose a bagged auto-associative kernel regression (AAKR)-based FDI approach for steam boilers in TPPs. AAKR estimates new query vectors by online local modeling, and is suitable for TPPs operating under various load levels. By combining the bagging method, more stable and reliable estimations can be achieved, since the effects of random fluctuations decrease because of ensemble averaging. To validate performance, the proposed method and comparison methods (i.e., a clustering-based method and principal component analysis) are applied to failure data due to water wall tube leakage gathered from a 250 MW coal-fired TPP. Experimental results show that the proposed method fulfills reasonable false alarm rates and, at the same time, achieves better fault detection performance than the comparison methods. After performing fault detection, contribution analysis is carried out to identify fault variables; this helps operators to confirm the types of faults and efficiently take preventive actions.

• 한국연소학회:학술대회논문집
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• 한국연소학회 2012년도 제45회 KOSCO SYMPOSIUM 초록집
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• pp.107-109
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• 2012

In Korean coal power plants, rising coal prices have recently led to the rapid utilization of low lank coals such as sub-bituminous coal with low calorific values and low ash fusion temperatures. Using these coals beyond the design range has resulted in important issues including slagging and fouling, which cause negative effects in boiler performances and unstable operations. The purpose of this study is to observe slagging and fouling characteristics resulted from burning various ranks of pulverized coals. We have tested 3 different coals: FLAME(bituminous), KCH(sub-bituminous) and MOOLARBEN(bituminous)coals in the pilot system $50kW_{th}$ scale. A stainless steel tube with preheated air inside was installed in the downstream in order to simulate water wall. Collected ash on the probe and the slag inside the furnace near burner were analyzed by SEM (scanning electron microscopy) to verify the formation degree, surface features and color changes of the pasty ash particles. Induced coupled plasma and energy dispersive X-ray spectroscopy were also performed to figure out the chemical characteristics of collected samples. As a result, KCH was observed that more slag was developed inside the walls of the furnace and on the probe than the other two kinds of coals, as shown in the calculate slagging and fouling indices as well.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2000년도 춘계학술대회논문집B
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• pp.373-378
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• 2000

An experimental investigation on the incipience of nucleate boiling in forced flow of water is performed as a verification and extension of previous analysis. The effects of the subcooling, Reynolds number and surface curvature on the onset of nucleate boiling(ONB) in a concentric annulus flow channel with smooth inner heating surface is investigated experimentaly. Through flow visualization, the boiling phenomenon was observed directly and the experimental results were examined to find ONB heat flux. The results show that the variation of heat flux at ONB is increased linearly as the Reynolds number and subcooling are increased. The effect of surface curvature is very great specially for a small radius when radius of the inner heating tube is increased, the heat flux at ONB is almost inversely increased for the range of this investigation. It is found that the effect of convex surface curvature on ONB heat flux is very significant for a small radius.

• Nuclear Engineering and Technology
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• 제42권3호
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• pp.297-304
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• 2010

In the design of advanced light water reactors (ALWRs) and in the safety assessment of currently operating nuclear power plants, it is necessary to evaluate the possibility of experiencing a degraded core accident and to develop innovative safety technologies in order to assure long-term debris cooling. The objective of this experimental study is to investigate the enhancement factors of dryout heat flux in debris beds by coolant injection from below. The experimental facility consists mainly of an induction heater, a double-wall quartz-tube test section containing a steel-particle bed and coolant injection and recovery condensing loop. A fairly uniform heating of the particle bed was achieved in the radial direction and the axial variation was within 20%. This paper reports the experimental data for 3.2 mm and 4.8 mm particle beds with a 300 mm bed height. The dryout heat density data were obtained for both the top-flooding and the forced coolant injection from below with an injection mass flux of up to $1.5\;kg/m^2s$. The dryout heat density increased as the rate of coolant injection increased. At a coolant injection mass flux of $1.0\;kg/m^2s$, the dryout heat density was ${\sim}6.5\;MW/m^3$ for the 4.8 mm particle bed and ${\sim}5.6\;MW/m^3$ for the 3.2 mm particle bed. The enhancement factors of the dryout heat density were 1.6-1.8.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 추계학술발표회논문집(1)
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• pp.534-539
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• 1997

A CHF table method has been assessed in this study for rod bundle CHF predictions. At the conceptual design stage for a new reactor, a general critical heat flux (CHF) prediction method with a wide applicable range and reasonable accuracy is essential to the thermal-hydraulic design and safety analysis. In many aspects, a CHF table method (i.e., the use of a round tube CHF table with appropriate bundle correction factors) can be a promising way to fulfill this need. So the assessment of the CHF table method has been performed with the bundle CHF data relevant to pressurized water reactors (PWRs). For comparison purposes, W-3R and EPRI-1 were also applied to the same data base. Data analysis has been conducted with the subchannel code COBRA-IV-I. The CHF table method shows the best predictions based on the direct substitution method. Improvements of the bundle correction factors, especially for the spacer grid and cold wall effects, are desirable for better predictions. Though the present assessment is somewhat limited in both fuel geometries and operating conditions, the CHF table method clearly shows potential to be a general CHF predictor.

• 태양에너지
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• 제17권4호
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• pp.45-56
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• 1997

본 연구는 제설설비에 히트파이프를 사용할때 기술적, 경제적 문제에 대해서 고찰하고, 히트파이프식의 제설구조물를 제작 설비하는 경우의 적용범위와 작동조건에 따라 전열효과를 실험적으로 검토한 것이다. 제설 제빙용으로 개발된 히트파이프식 설비는 히트파이프 배열의 피치에 관계없이 상호보완적으로 작동하였으며 제설설비를 위해 충분한 성능을 보였다. 작동액체의 충전량은 증발기의 체적을 기준으로 하여 $0.96{\sim}1.3$배인 경우가 가장 적합 하였다. 가열액체의 온도가 증가할수록 안정한 운전이 가능하였고 경사도는 4.5도에서 9도사이가 가장 양호했다. 경사가 크고 가열매체 입구온도가 증가할 때 온도진동수는 증가하고 진폭은 감소하고 열전달 효과는 크게 나타났다.