• 대한약리학회지
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• 제12권2호
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• pp.43-49
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• 1976

The facts that $PGE_2$ produced diuresis in the rabbit when given into a lateral ventricle of the brain and that $PGF_{2{\alpha}}$ is abundantly found in the brain prompted us to investigate the effects of $PGF_{2{\alpha}}$ introduced directly into the ventricle on the renal function. $PGF_{2{\alpha}}$ given intraventriculary in doses of $10{\mu}g\;and\;100{\mu}g$ elicited prompt diuresis, 10-fold increase of sodium excretion and two-fold increment of potassium excretion. Free water reabsorption also increased along with the increased osmolar clearance. Neither renal plasma flow nor glomerular filtration rate did change significantly. This, along with the fact that the percentage of reabsorbed sodium filtered decreased from 99.5 to 93.9, indicates the tubular site of the diuretic and natriuretic action. Atropine pretreatment did not influence the renal effects of intraventricular $PGF_{2{\alpha}}$. Intravenously administered $PGF_{2{\alpha}}$ in doses of 30 to $100{\mu}g$ did not produce any significant change in renal function. Intraventricular $PGF_{2{\alpha}}$ had no effect on the systemic blood pressure, whereas intravenous administration brought about a transient hypotension. These observations suggest that $PGF_{2{\alpha}}$ induces diuresis and natriuresis via central mechanism, that the site of the action resides in renal tubules, and that the reabsorption of sodium is inhibited in the proximal tubule, possibly through mediation of certain humoral agent. Overall, it is suggested that $PGF_{2{\alpha}}$ might play a roll in regulating renal function through the center.

• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2011년도 제37회 추계학술대회논문집
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• pp.981-984
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• 2011

에틸렌 연료의 이중모드 스크램제트 연소기에서 연소와 충격파 열 발생의 과도 과정을 고해상도 기법을 이용하여 수치적으로 연구하였다. 연료 분사 이후 질량 공급에 의한 아음속 유동 감속을 위하여 연소기 확장부에 조절용 공기를 공급한다. 공기와 연료가 충분히 혼합된 수 ms 이후 점화가 이루어지며, 압력 상승은 격리부에 흡입구 노즐까지 전진하는 충격파 열을 형성한다. 이후 후방 공기공급을 중단하면 배출 과정이 진행되면서 후방 공기 공급 이전 상태로 서서히 복원된다. 본 연구의 결과는 이중모드 스크램제트 연소기에서 작동 영역과 특징의 이해를 돕는 상세 과정을 보여주었다.

• 한국멀티미디어학회논문지
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• 제8권10호
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• pp.1322-1328
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• 2005

점성 유체를 담고 쳐는 실린더가 회전운동을 시작하면 회전 원판의 원심력과 에크만 펌핑 효과에 의해 실린더 외벽의 각운동량이 유체에 전달되는 과정에서 자오면상의 유동이 생기게 되고, 이 때 유체의 특성에 따라 유동장의 운동량 획득 특성이 다르게 나타나게 된다. 본 연구에서는 뉴턴 유체와 비-뉴턴 유체의 유동장 획득에 대한 정보를 가시화 영상에서 검출하고 이를 기반으로 유체의 특성을 분석하는 방법을 제안한다. 영상으로부터 운동량이 가장 크게 변화하는 전단면(shear front)의 위치를 알아내기 위해서, 유체의 운동량이 영상에서의 밝기정보로 나타나도록 실험환경을 구성한다. 입력 영상으로부터 유체의 운동량과 흐름을 가시화 할 수 있도록 가시화 매개 물질을 사용하여 영상을 획득하고, 영상에서 에크만 경계층의 전단면을 찾아내어 이동거리를 계산함으로써 유체의 특성을 분석하는 방안을 제시한다. 또한 유동장에 대해, LDV(Laser Doppler Velocimetry)로 측정한 값과 영상으로부터 얻은 값을 비교함으로써 제안된 방법에 대한 정확성을 검증하고, 검증된 데이터를 기반으로 비-뉴턴 유체와 뉴턴 유체에 대한 특성을 분석한다.

• 한국안전학회지
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• 제35권4호
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• pp.84-91
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• 2020

The Korean nuclear industry developed the SPACE (Safety and Performance Analysis Code for nuclear power plants) code and this code adpots two-phase flows, two-fluid, three-field models which are comprised of gas, continuous liquid and droplet fields and has a capability to simulate three-dimensional model. According to the revised law by the Nuclear Safety and Security Commission (NSSC) in Korea, the multiple failure accidents that must be considered for accident management plan of nuclear power plant was determined based on the lessons learned from the Fukushima accident. Generally, to improve the reliability of the calculation results of a safety analysis code, verification work for separate and integral effect experiments is required. In this reason, the goal of this work is to verify calculation capability of SPACE code for multiple failure accident. For this purpose, it was selected the experiment which was conducted to simulate a Multiple Steam Generator Tube Rupture(MSGTR) accident with Passive Auxiliary Feedwater System(PAFS) operation by Korea Atomic Energy Research Institute (KAERI) and focused that the comparison between the experiment results and code calculation results to verify the performance of the SPACE code. The MSGR accident has a unique feature of the penetration of the barrier between the Reactor Coolant System (RCS) and the secondary system resulting from multiple failure of steam generator U-tubes. The PAFS is one of the advanced safety features with passive cooling system to replace a conventional active auxiliary feedwater system. This system is passively capable of condensing steam generated in steam generator and feeding the condensed water to the steam generator by gravity. As the results of overall system transient response using SPACE code showed similar trends with the experimental results such as the system pressure, mass flow rate, and collapsed water level in component. In conclusion, it could be concluded that the SPACE code has sufficient capability to simulate a MSGTR accident.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 추계학술대회 논문집 전력기술부문
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• pp.46-48
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• 2005

This paper discusses a probabilistic method for power system security assessment. The security analysis relates to the ability of the electric power systems to survive sudden disturbances such as electric short circuits or unanticipated loss of system elements. It consists of both steady state and dynamic security analyses, which are not two separate issues but should be considered together. In steady state security analysis including voltage security analysis, the analysis checks that the system is operated within security limits by OPF (optimal power flow) after the transition to a new operating point. Until now, many utilities have difficulty in including dynamic aspects due to computational capabilities. On the other hand. dynamic security analysis is required to ensure that the transition may lead to an acceptable operating condition. Transient stability, which is the ability of power systems to maintain synchronism when subjected to a large disturbance. is a principal component in dynamic security analysis. Usually any loss of synchronism may cause additional outages and make the present steady state analysis of the post-contingency condition inadequate for unstable cases. This is the reason for the need of dynamic studies in power systems. Probabilistic criterion can be used to recognize the probabilistic nature of system components while considering system security. In this approach. we do not have to assign any predetermined margin of safety. A comprehensive conceptual framework for probabilistic static and dynamic assessment is presented in this paper. The simulation results of the Western System Coordinating Council (WSCC) system compare an analytical method with Monte-Carlo simulation (MCS).

• 한국철도학회논문집
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• 제10권6호
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• pp.645-649
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• 2007

접지시스템은 고장전류를 대지로 방출시켜 대지전위상승을 억제하는 역할을 한다. 본 논문에서는 넓은 주파수 범위에서 접지임피던스를 분석하기 위하여 서지임피던스측정기를 설계 제작하였다. 본 측정기는 서지발생회로, 고속 샘플/홀드회로 및 주변 전자회로로 구성되어 있으며, 서지발생치고는 상승시간 $50ns\sim500ns$ 범위에서 최대 5kV까지 발생시킬 수 있다. 제작한 서지임피던스 측정기는 심타접지극으로 구성된 접지계에서 실질적 평가가 수행되었다. 실험 결과로부터 접지계의 서지임피던스는 인가전압의 상승시간에 따라 증가하는 경향을 나타내므로, 접지임피던스는 여러가지 고속의 서지파형으로 평가되어야함을 확인하였다.

• Nuclear Engineering and Technology
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• 제52권8호
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• pp.1626-1637
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• 2020

This work covers an important point of the benchmark released by the expert group on Uncertainty Analysis in Modeling of Light Water Reactors. This ambitious benchmark aims to determine the uncertainty in light water reactors systems and processes in all stages of calculation, with emphasis on multi-physics (coupled) and multi-scale simulations. The Gesellschaft für Anlagen und Reaktorsicherheit methodology is used to propagate the thermal-hydraulic uncertainty of macroscopic parameters through TRACE5.0p3/PARCSv3.0 coupled code. The main innovative points achieved in this work are i) a new thermal-hydraulic model is developed with a highly-accurate 3D core discretization plus an iterative process is presented to adjust the 3D bypass flow, ii) a control rod insertion occurrence -which data is obtained from a real PWR test- is used as a transient simulation, iii) two approaches are used for the propagation process: maximum response where the uncertainty and sensitivity analysis is performed for the maximum absolute response and index dependent where the uncertainty and sensitivity analysis is performed at each time step, and iv) RESTING MATLAB code is developed to automate the model generation process and, then, propagate the thermal-hydraulic uncertainty. The input uncertainty information is found in related literature or, if not found, defined based on expert judgment. This paper, first, presents the Gesellschaft für Anlagen und Reaktorsicherheit methodology to propagate the uncertainty in thermal-hydraulic macroscopic parameters and, then, shows the results when the methodology is applied to a PWR reactor.

• Korea-Australia Rheology Journal
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• 제21권4호
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• pp.203-211
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• 2009

In flows with deformation rates larger than the inverse Rouse time of the polymer chain, chains are stretched and their confining tubes become increasingly anisotropic. The pressures exerted by a polymer chain on the walls of an anisotropic confinement are anisotropic and limit chain stretch. In the Molecular Stress Function (MSF) model, chain stretch is balanced by an interchain pressure term, which is inverse proportional to the $3^{rd}$ power of the tube diameter and is characterized by a tube diameter relaxation time. We show that the tube diameter relaxation time is equal to 3 times the Rouse time in the limit of small chain stretch. At larger deformations, we argue that chain stretch is balanced by two restoring tensions with weights of 1/3 in the longitudinal direction of the tube (due to a linear spring force) and 2/3 in the lateral direction (due to the nonlinear interchain pressure), both of which are characterized by the Rouse time. This approach is shown to be in quantitative agreement with transient and steady-state elongational viscosity data of two monodisperse polystyrene melts without using any nonlinear parameter, i.e. solely based on the linear-viscoelastic characterization of the melts. The same approach is extended to model experimental data of four styrene-butadiene random copolymer melts in shear flow. Thus for monodisperse linear polymer melts, for the first time a constitutive equation is presented which allows quantitative modeling of nonlinear extension and shear rheology on the basis of linear-viscoelastic data alone.

• 한국수소및신에너지학회논문집
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• 제20권5호
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• pp.378-383
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• 2009

Hydrogen is the primary fuel in fuel cell systems. Because of high inflammation and explosion possibility of hydrogen, fuel cell systems require safety measures to prevent hydrogen hazard upon leakage. In this study, a model enclosure was made by referring to a commercial residential fuel cell system and hydrogen leakage experiments and computational simulations were conducted therein. Hydrogen was injected into the cavity through leakage holes located at the bottom while its flow rate was precisely controlled using MFC. The transient sensor signals from hydrogen sensors installed inside the enclosure were recorded and analyzed. The hydrogen sensor signals showed different delay times depending on their position relative to a leakage point, which indicated that hydrogen generally moves upward and accumulates at the upper region of a closed cavity. The inflammable regions with hydrogen concentration over 4% LEL were observed to locate near the leakage hole initially, and broaden towards the upper cavity region afterward. The simulation result showed that detection time at the hydrogen sensor was similar to the pattern of experimental results. However, the maximum concentration of hydrogen had a gap between experiment and simulation at detect point due to measurement errors and reaction rate.

• 한국환경과학회지
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• 제22권9호
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• pp.1115-1129
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• 2013

The study area is located on the western coast, and the inner development construction has been ongoing since 2011. The purposes of current study are to effectively simulate and quantitatively predict a temporal and spatial distributions of water temperature and salinity due to the stages of inner development construction in saemangeum reclaimed area. The transient-state numerical modeling using EFDC model is done, and the numerical simulation results are validated reasonably by repetitive numerical model calibration procedures with respect to field measurements of water temperature and salinity. The spatial distributions of water temperature and salinity show similar trends before and after construction of the dikes. In spring season, the salinity has maximum value of 21 psu, while, in summer season, the salinity shows 7 psu in a whole modeling domain. Thus, it is clearly observed that salt water is replaced by freshwater. However, the salinity and temperature reach their initial conditions at the end of the year. The salinity after construction of the dikes is lower than that before construction of them at Mankyeong area. On the other hands, after construction of the dikes, the salinity after dredging operations is higher than that before dredging. Because drastical increasing of water volume in Saemangeum Lake leads to increasing of stagnation time at bottom layer, and salt water is easily intruded to the two estuaries. Therefore, it may be concluded that hydrodynamic characteristics on Saemangeum are dominated by either Mankyeong and Dongjin discharge or sluice gates in/out-flow amounts, and thus they must be properly considered when rigorous and reasonable predictions of water temperature and salinity according to the stages of inner development construction.