• 한국콘텐츠학회논문지
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• 제6권11호
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• pp.310-316
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• 2006

상수도관망에서 발생하는 누수현상은 수자원의 손실뿐만 아니라 압력손실로 인한 추가적 가압 설비의 필요성 및 누수 되는 관로 주변의 토질의 약화 등을 초래하여 관망의 유지관리를 어렵게 하고, 심각한 경제적 손실을 야기하고 있다. 본 연구는 구역고립으로 인한 수압과 유량 등을 상시 모니터링 하여 누수사고의 적극적인 대처와 누수발생을 미연에 방지함으로써 유수율을 향상시킬 수 있다. 실제 구역고립 후 계속되는 수압조절 및 유입유량의 모니터링에 인하여 구역 내 유수율 산정결과 평균 유수율은 88.94%로서 부산광역시 2003년도의 유수율 79.5%보다 9.44% 높게 조사되었다.

• 한국콘텐츠학회:학술대회논문집
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• 한국콘텐츠학회 2005년도 추계 종합학술대회 논문집
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• pp.115-118
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• 2005

상수도관망에서 발생하는 누수현상은 수자원의 손실뿐만 아니라 압력손실로 인한 추가적 가압 설비의 필요성 및 누수되는 관로 주변의 토질의 약화 등을 초래하여 관망의 유지관리를 어렵게 하고, 심각한 경제적 손실을 야기하고 있다. 이에 구역고립으로 인한 수압과 유량 등을 상시 모니터링하여 누수사고의 적극적인 대처와 누수발생을 미연에 방지함으로써 유수율을 향상 시킬 수 있다 .실제 구역고립 후 계속되는 수압 조절 및 유입유량의 모니터링으로 인하여 구역내 유수율 산정결과 평균 유수율은 88.94%로서 부산광역시 2003년도의 유수율 79.5%보다 9.44% 높게 조사되었다.

• Nuclear Engineering and Technology
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• 제40권3호
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• pp.239-250
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• 2008

If there is a water flow with a range of temperature inside a pipe, the wanner water tends to float on top of the cooler water because it is lighter, resulting in the upper portion of the pipe being hotter than the lower portion. Under these conditions, such thermal stratification can play an important role in the aging of nuclear power plant piping because of the stress caused by the temperature difference and the cyclic temperature changes. This stress can limit the lifetime of the piping, even leading to penetrating cracks. Investigated in this study is the effect of thermal stratification on the structural integrity of the pressurizer surge line, which is reported to be one of the pipes most severely affected. Finite element models of the surge line are developed using several element types available in a general purpose structural analysis program and stress analyses are performed to determine the response characteristics for the various types of top-to-bottom temperature differentials due to thermal stratification. Fatigue analyses are also performed and an allowable environmental correction factor is suggested.

• Nuclear Engineering and Technology
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• 제49권7호
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• pp.1463-1471
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• 2017

In order to monitor the pipe thinning caused by flow-accelerated corrosion (FAC) that occurs in coolant piping systems, a shear horizontal ultrasonic pitch-catch waveguide technique was developed for accurate pipe wall thickness monitoring. A clamping device for dry coupling contact between the end of the waveguide and pipe surface was designed and fabricated. A computer program for multi-channel on-line monitoring of the pipe thickness at high temperature was also developed. Both a four-channel buffer rod pulse-echo type and a shear horizontal ultrasonic waveguide type for high-temperature thickness monitoring system were successfully installed to the test section of the FAC proof test facility. The overall measurement error can be estimated as ${\pm}10{\mu}m$ during a cycle from room temperature to $200^{\circ}C$.

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.322-336
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• 2021

This paper presents a numerical prediction of the transient hydraulic loads acting on the tubes and external supports of a pressurized water reactor (PWR) steam generator (SG) during blowdown following a sudden feedwater line break (FWLB). A simplified SG model was used to easily demonstrate the prediction. The blowdown discharge flow was treated as a flashing flow to realistically simulate the transient flow fields inside the SG and the connected broken feedwater pipe. The effects of the SG initial pressure or the broken feedwater pipe length on the intensities or magnitudes of transient hydraulic loads were investigated. Then predictions of the decompression pressure wave-induced impulsive pressure differential loads on SG tubes and the transient blowdown loads on SG external supports were demonstrated and the general aspects of transient responses of such transient hydraulic loads to the FWLB were discussed.

• 디지털융복합연구
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• 제17권6호
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• pp.169-175
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• 2019

본 연구의 목적은 합류식 하수처리구역 내에 대형 건축물을 건설하는 경우, 정화조를 설치하는 대안과 정화조를 대신하여 전용오수관로를 설치하는 대안의 경제성을 비교분석하는 것이다. 이를 위해 우리나라 대표적 대형 건축물인 롯데월드타워의 사례를 들어 두 대안 간의 비용편익분석을 수행하였다. 롯데월드타워 건물에 정화조를 설치하는 대신에 전용오수관로를 설치할 경우, 회수기간은 6.2년, 순현재가치(NPV)는 약 61.7억 원이 발생하며, B/C비율은 1.93인 것으로 나타났다. 이러한 사례분석 결과는 향후 정화조 폐쇄에 대한 정책수립과 대형 건축물 신축 시 전용오수관로 건설에 대한 타당성을 검토할 때 적용할 수 있는 유용한 지침을 제공해 줄 것으로 보인다. 향후에는 원인자부담금과 전용오수관로 관리책임 부담여부, 악취감소에 따른 경제적 효익 등을 비용편익분석에 추가적으로 고려할 필요가 있다.

• 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.

• Nuclear Engineering and Technology
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• 제51권8호
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• pp.1939-1950
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• 2019

The MELCOR code useful for a plant-specific hydrogen risk analysis has inevitable limitations in prediction of a turbulent flow of a hydrogen mixture. To investigate the accuracy of the hydrogen risk analysis by the MELCOR code, results for the turbulent gas behavior at pipe rupture accident were compared with CFX results which were verified by the American National Standard Institute (ANSI) model. The postulated accident scenario was selected to be surge line failure induced by station blackout of an Optimized Power Reactor 1000 MWe (OPR1000). When the surge line failure occurred, the flow out of the surgeline was strongly turbulent, from which the MELCOR code predicted that a substantial amount of hydrogen could be released. Nevertheless, the results indicated nonflammable mixtures owing to the high steam concentration released before the failure. On the other hand, the CFX code solving the three-dimensional fluid dynamics by incorporating the turbulence closure model predicted that the flammable area continuously existed at the jet interface even in the rising hydrogen mixtures. In conclusion, this study confirmed that the MELCOR code, which has limitations in turbulence analysis, could underestimate the existence of local combustible gas at pipe rupture accident. This clear comparison between two codes can contribute to establishing a guideline for computational hydrogen risk analysis.

• Nuclear Engineering and Technology
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• 제52권4호
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• pp.784-790
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• 2020

The accelerated corrosion by Flow Accelerated Corrosion (FAC) has caused unexpected rupture of piping, hindering the safety of nuclear power plants (NPPs) and sometimes causing personal injury. For the safety, it may be necessary to select some pipes in terms of condition monitoring and to measure the change in thickness of pipes in real time. Direct current potential drop (DCPD) method has advantages in on-line monitoring of pipe wall thinning. However, it has a disadvantage in that it is difficult to quantify thinning due to various thinning shapes and thus there is a limitation in application. The machine learning approach has advantages in that it can be easily applied because the machine can learn the signals of various thinning shapes and can identify the thinning using these. In this paper, finite element analysis (FEA) was performed by applying direct current to a carbon steel pipe and measuring the potential drop. The fundamental machine learning was carried out and the piping thinning model was developed. In this process, the features of DCPD to thinning were proposed.

• Nuclear Engineering and Technology
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• 제49권4호
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• pp.781-786
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• 2017

The presence of crust on the inner walls of metallic ducts impairs transportation because crust completely or partially hinders the passage of fluid to the processing unit and causes damage to equipment connected to the production line. Its localization is crucial. With the development of the electronic imaging system installed at the Argonauta/Nuclear Engineering Institute (IEN)/National Nuclear Energy Commission (CNEN) reactor, it became possible to visualize crust in the interior of metallic piping of small diameter using real-time neutron radiography images obtained with a low neutron flux. The obtained images showed the resistance offered by crust on the passage of water inside the pipe. No discrepancy of the flow profile at the bottom of the pipe, before the crust region, was registered. However, after the passage of liquid through the pipe, images of the disturbances of the flow were clear and discrepancies in the flow profile were steep. This shows that this technique added the assembled apparatus was efficient for the visualization of the crust and of the two-phase flows.