• 설비공학논문집
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• 제19권2호
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• pp.169-174
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• 2007

In process of reinforced concrete (RC) box structure, the heat of hydration may cause serious thermal cracking. This paper reports results of hydration heat control in mass concrete using the oscillating heat pipe. There were three RC box molds ($1.2m{\times}1.8m{\times}2.4m$) which were different from each other. One was not equipped with pulsating heat pipe. The others were equipped with pulsating heat pipe. All of them were cooled with natural air convection. The pulsating heat pipe was composed of 10 turns of serpentine type copper pipe whose outer and inner diameters were 4 and 2.8 mm respectively. The working fluid was R-22 and charging ratio was 40% by volume. The temperature of the concrete core was approximately $55^{\circ}C$ in the winter without pulsating heat pipe. For a concrete with pulsating heat pipe, however, the temperature difference with the outdoor one reduced up to $12^{\circ}C$. The index figure of crack was varied from 0.75 to 1.38.

• 수도
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• 통권70호
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• pp.91-98
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• 1994

• 복합신소재구조학회 논문집
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• 제2권3호
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• pp.18-24
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• 2011

이 연구에서 GRP 관의 하중-처짐 거동을 조사, 보고하였다. 지중매성 GRP관은 높은 내화학성, 높은 부식저항성, 경량성, 관표면의 매끄러움, 지반-관의 상호작용 고려에 따른 경제성 등의 탁원한 역학적, 물리적 특성들로 인해 건설현장에서 광범위하게 사용되고 있다. 지중에 매설되는 연성관을 설계하기 위해서는 ASTM D 2412 (2010)에 따라야 한다. ASTM D 2412 (2010)에 따라 설계할 경우, 관의 원강성 (PS)을 편평시험에 따라 먼저 결정해야 하는데, 이 시험이 귀찮고 노동력을 필요로 한다. 이러한 문제를 해결하기 위해 UTM에 설치된 형태의 GRP관의 하중-처짐 거동을 유한요소법에 따라 모사하였으며, 유한요소법에 의한 모사에는 재료의 탄성계수와 단면의 기하학적 치수 등 기초적인 자료를 사용하였다. 이와 같은 연구로부터, 관재료가 관의 단면내에서 비교적 일정하지 않음에도 불구하고 수직방향의 관변형이 3%와 5%가 발생할 경우, 편평시험과 수치해석적 연구 결과가 15%이내의 차이로 하중의 예측이 가능함을 알 수 있었다.

• 복합신소재구조학회 논문집
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• 제4권3호
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• pp.38-44
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• 2013

Glass fiber reinforced plastic (GRP) pipes buried underground are attractive for use in harsh environments, such as for the collection and transmission of liquids which are abrasive and/or corrosive. In this paper, we present the result of investigation pertaining to the structural behavior of GRP flexible pipes buried underground. In the investigation of structural behavior such as a ring deflection, experimental and analytical studies are conducted. In addition, vertical ring deflection is measured by the field test and finite element analysis (FEA) is also conducted to simulate behavior of GRP pipe buried underground. Based on the results from the finite element analyses considering soil-pipe interaction the vertical ring deflection behavior of buried GRP pipe is predicted. In addition, analytical and experimental results are compared and discussed.

• Nuclear Engineering and Technology
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• 제47권3호
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• pp.332-339
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• 2015

The leak before break (LBB) concept is widely used in designing pipe lines in nuclear power plants. According to the concept, the amount of leaking liquid from a pipe should be more than the minimum detectable leak rate of a leak detection system before catastrophic failure occurs. Therefore, accurate estimation of the leak rate is important to evaluate the validity of the LBB concept in pipe line design. In this paper, a program was developed to estimate the leak rate through circumferential cracks in pipes in nuclear power plants using the Henry-Fauske flow model and modified Henry-Fauske flow model. By using the developed program, the leak rate was calculated for a circumferential crack in a sample pipe, and the effect of the flow model on the leak rate was examined. Treating the crack morphology parameters as random variables, the statistical behavior of the leak rate was also examined. As a result, it was found that the crack morphology parameters have a strong effect on the leak rate and the statistical behavior of the leak rate can be simulated using normally distributed crack morphology parameters.

• 설비공학논문집
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• 제24권6호
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• pp.515-520
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• 2012

A daylighting system includes three parts; light collector, light transformer and light distributor. A DBLP(Double blind light pipe) daylighting system consists of a double blind light collector, a mirror duct type light transformer and a prism film light pipe distributor. The double blinds for a light collection are used to track the sun's altitude and azimuth movements throughout the day. Behind both sets of blinds is the light transformer, which is based on a rectangular cone shaped light duct. The light transformer was designed to efficiently deliver the light into the light pipe within a 30 degree radial spread for the efficient light into the distributor. In this study, DBLP system efficiency was simulated, evaluated and optimized by Tracepro as a popular ray trace light design simulation program. The results indicated that DBLP system efficiency evaluated a maximum 22.4% in case of Spring/Fall season solar noon time. While the overall average system efficiency in the morning and afternoon is evaluated about 10%.

• 한국화재소방학회논문지
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• 제29권3호
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• pp.21-30
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• 2015

본 연구는 스프링클러설비용 CPVC관과 신축배관 접속부분에서의 누수저감을 위하여 신축배관을 연결하기 위한 밸브소켓과 신축배관 너트부분에 삽입되는 수밀 고무패킹 재질에 대한 국내 및 국외 관련 규격의 검토와 관련 시험 등을 통해 대책을 제안하고자 한다. 누수시험을 통해 밸브소켓 재질은 신축배관 너트부분이 금속제인 경우 금속제로 사용하거나 신축배관 너트부분의 재질을 합성수지제로 사용하여야함을 알 수 있었다. 또한 밸브소켓의 적정 품질 확보를 위해서는 나사산 규격과 검사기준으로 KS B 0221(관용평행나사)와 나사산 검사규격을 KS B 5223(관용 평행나사 게이지)에 따르도록 관련 기준을 개정할 필요가 있다. 그리고 신축배관 너트부분에 설치되는 수밀용 고무링 소재에 대해 세부적인 기준이 없어 NBR과 EPDM 소재가 함께 사용되고 있으나 수밀성이 우수한 EPDM 소재가 사용되도록 관련 기준을 개정할 필요가 있다.

• 한국가스학회지
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• 제13권2호
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• pp.7-13
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• 2009

관망 내 배관의 간섭 거동에 따른 지하 매설 배관의 영향선 분석을 위하여 실제 환경에 부합 하도록 지하의 상부와 하부에 각각 하수관거와 가스관을 매설하여 유한요소모델을 구현하였으며, 두 배관의 교차 정도에 따라 하부 가스 배관의 영향선을 분석하였다. 하수관거와 가스관은 각각 1.0m와 3.39m의 매설심도를 가지며, 두 배관이 이루는 교차각은 $0{\sim}90^{\circ}$에 대하여 해석을 실시하였다. 본 연구에서는 Ring Deflection과 Bending Stress의 결과로부터, 교차각에 따른 영향선을 분석하였으며, 그 결과 두 배관이 이루는 교차각과 하부 배관의 영향선은 일치함을 알 수 있었다. 따라서 배관의 간섭 거동에 따른 하부 배관의 영향선은 두 배관의 교차각과 깊은 관계가 있다고 판단된다.

• Nuclear Engineering and Technology
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• 제52권1호
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• pp.19-26
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• 2020

Small nuclear reactor features higher power capacity, longer operation life than conventional power sources. It could be an ideal alternative of existing power source applied for special equipment for terrestrial or underwater missions. In this paper, a 25kWe heat pipe cooled reactor power source applied for multiple use is preliminary designed. Based on the design, a thermal-hydraulic analysis code for heat pipe cooled reactor is developed to analyze steady and transient performance of the designed nuclear reactor. For reactor design, UN fuel with 65% enrichment and potassium heat pipes are adopted in the reactor core. Tungsten and LiH are adopted as radiation shield on both sides of the reactor core. The reactor is controlled by 6 control drums with B₄C neutron absorbers. Thermoelectric generator (TEG) converts fission heat into electricity. Cooling water removes waste heat out of the reactor. The thermal-hydraulic characteristics of heat pipes are simulated using thermal resistance network method. Thermal parameters of steady and transient conditions, such as the temperature distribution of every key components are obtained. Then the postulated reactor accidents for heat pipe cooled reactor, including power variation, single heat pipe failure and cooling channel blockage, are analyzed and evaluated. Results show that all the designed parameters satisfy the safety requirements. This work could provide reference to the design and application of the heat pipe cooled nuclear power source.

• 설비공학논문집
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• 제24권5호
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• pp.428-432
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• 2012

In the waste collection system, living waste is collected through the piping network. There are many confluent pipes in a piping network. These confluent pipes were often clogged up with waste. The optimal configuration of the confluent pipes has been defined by the design guide. However, nobody know how this design guide were determined. Therefore, in this paper, we found the design data for the confluent pipe configuration in order to avoid the waste clogging in a piping network. The distance between connected point on the confluent pipes should be longer than the previous design guide.