• 한국지반공학회논문집
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• 제38권6호
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• pp.29-39
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• 2022

도심지 원형 수직구 굴착 시 주변 지반의 침하는 포장 하부에 설치된 인프라시설의 안정성 뿐만 아니라 상부구조의 안정성에 큰 영향을 미친다. 배면지반의 침하량을 예측하는 방법은 지반조건, 벽체 변위, 해석 방법 등에 따라 달라지므로 근접시공 설계자는 합리적으로 침하량을 예측해야한다. 본 연구에서는 3차원 유한요소해석을 활용하여 굴착심도별로 지하수의 침투에 따른 영향을 고려하기 위해 비정상류, 정상류, 지하수를 고려하지 않은 조건으로 배면지반의 침하와 벽체의 변위 그리고 토압분포를 검토하였다. 수치해석결과, 배면지반의 침하량과 침하영향범위는 비정상류 상태가 정상류 상태보다 크게 발생하였으나 벽체의 수평변위는 반대로 정상류 상태가 비정상류 상태보다 크게 나타났다. 침하량의 크기는 굴착 깊이에 따라 다르게 나타났으며 굴착 깊이 별로 토사층에서 가장 크고 풍화암층, 연암층 순으로 감소하였다. 또한 수압을 포함한 수평응력값을 기존의 Rankine 토압식과 비교했을 때 토사지반에서는 유사한 경향을 보이나 암반층에서는 수치해석 결과보다 작은 토압형태가 나타남을 확인 할 수 있었다.

• 한국자동차공학회논문집
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• 제7권9호
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• pp.36-47
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• 1999

Three-way catalyst converter, cleaning up the exhaust gas contamination of SI engine, has the best efficiency when A/F ratio is near the stoichiometry . The feedback control using oxygen sensors in the exhaust manifold has limits caused by the system delays. So the accurate measurement of air flow rate to an engine is essential to control the fuel injection rate especially on transient condition like the rapid throttle opening and closing. To measure the rapid change of flow rates. the air flow meter for the engine requires quick response, flow reversal detection, and linearity . Tjhe proposed integration type air flow meter (IFM), composed of an ultrasonic flow meter with an integration circuit, has significantly improved the measurement accuracy of air mass inducted through the throttle body. The proposed control method estimated the air mass at the cylinder port using the measured air mass at the throttle . For the fuel dynamic model, the two constant fuel model is introduced . The control parameters from air and fuel dynamics are tuned to minimize the excursion of the air fuel ratio. As a result A/F ratio excursion can be reduced within 5% when throttle rapidly opens and closes at the various engine conditions.

• 대한수학회지
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• 제48권6호
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• pp.1153-1170
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• 2011

In this paper, spatial decay estimates for the time dependent compressible viscous isentropic flow in a semi-infinite three dimensional pipe are derived. An upper bound for the total energy in terms of the initial boundary data is obtained as well. The results established in this paper may be viewed as a version of Saint-Venant's principle in transient compressible Navier-Stokes flow.

• 한국수자원학회:학술대회논문집
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• 한국수자원학회 2006년도 학술발표회 논문집
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• pp.1395-1399
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• 2006

The current paper focuses the analysis of leakage detection in water pipeline systems by means of the transient analysis. In order to obtain pressure variation for evaluation the existing methodology, an extensive experimental process has been carried out in a single pipeline system. Several experimental tests were performed with and without a leakage in the system. Using the unsteady friction and improved unsteady friction factors, reasonable match between the computed and measured pressure were presented on the condition of the flow situations. The transient method attempts to estimate the leakage in water pipelines using observed pressure data collected during transient events on the system.

• 상하수도학회지
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• 제20권2호
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• pp.207-214
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• 2006

The current paper focuses the analysis of leakage detection in water pipeline systems by means of the transient method. In order to obtain essential data for evaluation the existing methodology, an extensive experimental process has been carried out in a single pipeline system, Several experimental tests were performed with and without a leakage in the system. Using the unsteady friction and improved unsteady friction factors gives reasonable match between the computed and measured results on the condition of the flow situations presented in the paper. The transient method attempts to estimate the leakage in water pipelines using observed pressure data collected during transient events on the system.

• 대한기계학회논문집B
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• 제21권1호
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• pp.68-78
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• 1997

A numerical study on the transient vapor flow and heat transfer is performed to investigate the ideal switching operation of heat source in a high temperature heat pipe. The cylindrical 2-dimensional compressible laminar vapor flow is assumed for the vapor space and the conjugate heat transfer for the heat pipe wall, wick and vapor space is calculated. The different boundary conditions such as constant heat flux, convective or radiative boundary at the outer wall are used respectively to compare the influence of boundary conditions on the transient operation. The transient temperature profile and the internal flow of the entire pipe for the switching operation are described as a result. The results show that the transient time is not significantly affected by the boundary conditions at the outer wall in present study. During the transition, two independent flows are observed temporarily on the right side and left side of the heat pipe. It is also found that the trend of temperature variation in the vapor region is different from the variation in the wick and wall region.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집E
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• pp.474-481
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• 2001

This paper addresses a numerical method for predicting transient temperature distributions in the wall of a curved pipe subjected to internally thermal stratification flow. A simple and convenient numerical method of treating the unsteady conjugate heat transfer in the non-orthogonal coordinate systems is presented. The proposed method is implemented in a finite volume thermal-hydraulic computer code based on a cell-centered, non-staggered grid arrangement, the SIMPLEC algorithm, a higher-order bounded convection scheme, and the modified version of momentum interpolation method. Calculations are performed for the transient evolution of thermal stratification in two curved pipes, where the one has thick wall and the other has so thin wall that its presence can be negligible in the heat transfer analysis. The predicted results show that the thermally stratified flow and transient conjugate heat transfer in a curved pipe with a finite wall thickness can be satisfactorily analyzed by the present numerical method, and that the neglect of wall thickness in the prediction of pipe wall temperature distributions can provide unacceptably distorted results.

• 대한토목학회논문집
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• 제10권2호
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• pp.59-65
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• 1990

3차원 비정상류모형을 사용하여 출도대지(出島台地)의 소유역에 있어서 인위적및 자연적 요인이 지하수유동에 미치는 영향에 대하여 고찰하였다. 3차원 비정상류모형의 검정을 위하여, 모형에 의한 수치해석해와 Theis의 해석해를 비교한 결과 서로 좋은 대응을 나타내었다. 모의발생은 용수로(用水路)를 통하여 관개가 시작되는 5월 1일부터 30일간 행하였다. 지하수 유동양상을 포텐샬도로 나타내었으며 그에 대한 고찰이 있었다. 본 해석으로 부터 인위적 영향을 받는 지역의 지하수유동계를 해석하기 위해서는 3차원 비정상류모형이 유용하다고 사료되었다.

• Nuclear Engineering and Technology
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• 제54권5호
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• pp.1674-1685
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• 2022

The ball valve is an important device in the pipeline transportation system of nuclear power plants. Its operational stability and safety directly affect the normal working of nuclear power plants. In this study, the transient numerical simulation of the opening and closing process of a ball valve was conducted on the basis of the flow interruption capability experiment of the ball valve by using the moving mesh method and inlet and outlet variable boundary conditions. The flow rate and pressure difference with time of the opening and closing process of the ball valve were studied. The internal flow characteristics of the ball valve under different relative openings were analyzed in conjunction with the typical back-step flow structure. Results show that the transient numerical results agree well with the experimental results. The internal flow characteristics of the ball valve are similar at the same opening during opening and closing process. At small opening, the spool and outlet channels easily form a back-step flow structure. The disappearance and generation of backflow vortices during opening and closing occur at 85% opening and 75% opening, respectively. With the decrease in opening degree, the difference in vortex core area in the flow channel of the ball valve spool in the opening and closing process gradually appears. The research results provide some reference value for the design and optimization of ball valves.

• Nuclear Engineering and Technology
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• 제17권4호
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• pp.256-266
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• 1985

냉각재 유량상실 사고가 가압경수형 원자로인 고리 1호기에 대하여 해석되었다. 냉각재 유량 상실 사고는 그 심각도에 따라 다음과 같이 3가지로 분류된다. 즉, 일부 유량 상실사고, 완전 유량 상실 사고, 그리고 펌프 축 고착 사고이다. 사고 해석은 계통 과도 현상 및 평균 노심분석, DNBR 계산, 그리고 고온점 분석의 3단계로 수행된다. 원자로 계통과도 현상 코드인 KTRAN이 본 사고를 빠른 시간에 모사할 수 있도록 개발되었다. DNBR계산을 위해서는 열수력학 코드인 SCAN및 COBRA IV-I가 채택되었으며, 고온점 분석을 위해서는 연료봉 과도 현상 코드인 LTRAN이 쓰였다. 이러한 전산코드 시스템은 과도 현상 해석에 빨리 응답하여야 한다. 왜냐하면 사고가 발생한 후 수 초안에 심각한 상태에 이르기 때문이다. 불행히도 KTRAN코드에 의하여 이러한 목적은 충족되지 않았다. 그러나 다른 계통 해석 코드에 비하여 잔은 계산 시간에도 불구하고 KTRAN에 의한 계산 결과는 FSAR의 결과와 전반적으로 잘 일치함으로써 KTRAN코드가 사고 해석에 유용함이 밝혀졌다.