• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2004년도 제22회 춘계학술대회논문집
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• pp.165-172
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• 2004

LE-7A is the main engine of the H-IIA launch vehicle. Under its development, the nozzle suffered from two troubles during startup and shutdown transients of the engine. One is a large side load, which damages the actuator of the nozzle, and the other is damage on regenerative cooling tubes due to high heat load. It has been considered that these problems are caused by a peculiar separation pattern called Restricted Shock Separation (RSS). RSS is observed in several rocket nozzles, for example, LE-7A nozzle, Vulcain nozzle and so on. Their contours are not conventional truncated perfect (TP) nozzle - LE-7A nozzle is a compressed truncated perfect (CTP) nozzle and Vulcain nozzle is a thrust optimized (TO) nozzle. Although it is believed that the occurrence of RSS is affected by the nozzle contour, the mechanisms are not clarified sufficiently yet. In the present paper, a parametric numerical study is carried out to investigate the mechanisms of the occurrence of RSS in CTP nozzles during startup transient. The results show that RSS is caused by the adverse pressure gradient downstream of the Mach disk. The adverse pressure gradient is caused by the interaction of the pressure wave and Mach disk. The method to avoid the occurrence of RSS is also examined. A small step inside the nozzle affects the position of the separation point and prevents RSS. The result shows that the possibility that RSS can be suppressed by controlling the position of the separation point.

• Nuclear Engineering and Technology
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• 제36권6호
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• pp.528-539
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• 2004

It is essential in commercial reactors that the safety limits imposed on the fuel pellets and fuel clad barriers, such as the linear power density (LPD) and the departure from nucleate boiling ratio (DNBR), are not violated during reactor operations. In order to accurately monitor the safety limits of current reactor states, a detailed three-dimensional (3D) core power distribution should be estimated from the in-core detector signals. In this paper, we propose a calculation methodology for detailed 3D core power distribution, using in-core detector signals and core monitoring constants such as the 3D Coupling Coefficients (3DCC), node power fraction, and pin-to-node factors. Also, the calculation method for several core safety parameters is introduced. The core monitoring constants for the real core state are promptly provided by the core design code and on-line MASTER (Multi-purpose Analyzer for Static and Transient Effects of Reactors), coupled with the core monitoring program. through the plant computer, core state variables, which include reactor thermal power, control rod bank position, boron concentration, inlet moderator temperature, and flow rate, are supplied as input data for MASTER. MASTER performs the core calculation based on the neutron balance equation and generates several core monitoring constants corresponding to the real core state in addition to the expected core power distribution. The accuracy of the developed method is verified through a comparison with the current CECOR method. Because in all the verification calculation cases the proposed method shows a more conservative value than the best estimated value and a less conservative one than the current CECOR and COLSS methods, it is also confirmed that this method secures a greater operating margin through the simulation of the YGN-3 Cycle-1 core from the viewpoint of the power peaking factor for the LPD and the pseudo hot pin axial power distribution for the DNBR calculation.

• Nuclear Engineering and Technology
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• 제15권4호
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• pp.236-247
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• 1983

한국원자력 1호기(KNU-1)의 설계 및 운전자료를 이용하여 가압경수로 운전변수들의 변화에 대한 DNBR의 민감도를 분석하였다. 본 민감도 분석에는 원자로 출력, 압력, 냉각수 주입유량, 냉각수 주입온도, 반경방향 및 축방향 출력분포 그리고 축방향 출력편차 등의 운전변수가 고려되었다. 민감도 분석을 위하여는 노심의 열수력 해석용 전산코드인 COBRA-IV-K를 사용하였는데 본 코드는 COBRA-IV-i의 수정판으로써 한국에너지연구소에서 일부 프로그램을 수정하였고 또한 신뢰도도 확인하였다. 민감도 분석을 수행하기 전에 KNU-1 원자로심의 설계 및 운전조건을 근거로 하여 기초 계산을 수행하고 이 결과를 본 민감도 분석의 기본자료로 삼았다. 민감도 분석결과 원자로의 DNBR 열설계에 있어서 가장 민감한 운전변수는 냉각수 주입온도이고 가장 둔감한 변수는 축방향 출력분포라는 것이 밝혀졌다.

• 한국지반환경공학회 논문집
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• 제8권4호
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• pp.67-74
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• 2007

강우시 우수의 침투로 사면의 안정성은 감소되며, 사면활동에 의한 피해를 최소화하기위해 강우시 토사사면에 대한 사면 안정해석시 지표까지 완전히 포화되는 조건으로 설계하도록 설계기준을 강화하고 있다. 그러나 이와 같은 설계방식은 강우강도, 강우지속시간, 지반특성, 사면의 기하학적 특성 등과 관계없이 동일하게 지표까지 완전 포화조건으로 설계함으로써 지나치게 과다하게 설계되는 경향이 있는 등 문제점이 지적되고 있다. 또한 대부분의 토사사면은 불포화상태에 있으며, 불포화특성을 고려한 사면 안정해석이 수행되어야 할 것이다. 본 논문은 강우시 토사 사면이 완전 포화되기까지 소요되는 강우지속시간을 예측할 수 있는 방법을 제시하였다. 이를 위해 본 논문에서는 불포화토의 흙-수분 특성과 포화시 투수계수, 사면의 기하학적 조건, 강우강도 등을 고려하여 불포화토 사면에 대한 유한요소해석을 실시하여 강우시 토사사면이 완전 포화되기 까지 소요되는 강우지속시간을 예측하였으며, 이들 해석결과로부터 간편하게 사용할 수 있는 예측도표를 제시하였다.

• 한국자동차공학회논문집
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• 제15권1호
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• pp.116-124
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• 2007

An optical method to measure the size and number density of soot aggregates in diesel exhaust has been proposed in this study. Two laser beams in co-axial alignment transmit a soot loaded exhaust gas flow, and the transmittance at each wavelength is detected by a photo diode simultaneously. The volume equivalent diameter and number density of soot aggregates in the optical path can be theoretically given by the transmittance values measured at two wavelengths. A test conducted by a single cylinder, 4 cycle, small and DI diesel engine shows that the temporal variations of the size and number density of soot aggregates in the diesel exhaust can be measured by the proposed method at a transient mode operation. It is found that the volume equivalent diameter varied temporally from 70 to 110 nm during the period that high soot concentration is observed. One can also conclude that the optical length longer than 1 m in the dynamic range regarding this method is preferable for measuring soot concentration at the level of $1\;mg/m^3$.

• 전기학회논문지
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• 제65권8호
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• pp.1340-1346
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• 2016

Utilization of Distributed Generations (DGs) using Renewable Energy Sources (RESs) has been constantly increasing as they provide a lot of environmental, economic merits. In spite of these merits, some problems with respect to voltage profile, protection and its coordination system due to reverse power flow could happen. In order to analyze and solve the problems, accurate modeling of DG systems should be preceded as a fundamental research task. In this paper, we present a PhotoVoltaic (PV) generation system which consists of practical PV cells with series and parallel resistor and an inverter for interconnection with a main distribution system. The inverter is based on controllable current source which is capable of controlling power factors, active and reactive powers within a certain limit related to amount of PV generation. To verify performance of the model, a distribution system based on actual data is modeled by using ElectroMagnetic Transient Program (EMTP) software. Computer simulations according to various conditions are also performed and it is shown from simulation results that the model presented is very effective to study DG-related researches.

• Nuclear Engineering and Technology
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• 제31권5호
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• pp.476-485
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• 1999

In order to evaluate the gravity-injection capability to maintain core cooling after a loss-of-shutdown-cooling event during shutdown operation, the plant conditions of the Yong Gwang Units 3&4 were reviewed. The six cases of possible gravity-injection paths from the refueling water tank (RWT) were identified and the thermal-hydraulic analyses were performed using the RELAP5/MOD3.2 code. The core cooling capability was significantly dependent on the gravity-injection path, the RCS opening, and the injection rate. In the cases with the pressurizer manway opening higher than the RWT water level, the coolant was held up in the pressurizer and the system pressure continued increasing after gravity-injection. The gravity injection eventually stopped due to the high system pressure and the core was uncovered. In the cases with the injection path and opening on the same leg side, the core cooling was dependent on whether the water injected from the RWT passed the core region or not. However, in the cases with the injection path and opening on the different leg side, the system was well depressurized after gravity-injection and the core boiling was successfully prevented for a long-term transient. In addition, from the sensitivity study on the gravity-injection flow rate, it was found that about 54 kg/s of injection rate was required to maintain the core cooling and the core cooling could be provided for about 10.6 hours after event with that injection rate from the RWT. Those analysis results would provide useful information to operators coping with the event.

• 대한기계학회논문집A
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• 제36권9호
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• pp.1103-1108
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• 2012

주증기관은 보일러와 터빈을 연결하는 주요계통이다. 운전조건으로 인한 배관시스템에 손상을 제한 할 수 있기 때문에 수격현상 해석은 중요하다. 배관시스템의 불안정한 유동에 의해 생성되는 수격현상은 압력의 과도한 변화, 진동 및 소음을 일으킬 수 있다. 주증기관 구조는 운전환경아래 압력맥동 및 여러 진동 등을 안전하게 견딜 수 있도록 설계되어야 한다. 본 논문에서는 정지 및 정상 운전기간 동안 배관에 유입되는 수격현상을 과도조건에 적용하여 ASME 피로수명 방법론과 유한요소해석에 따라 주증기관의 구조건전성을 평가하였다. 계산된 교번응력 및 피로응력 평가 결과, ASME 피로수명의 허용요건을 만족하였다.

• 한국해양학회지:바다
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• 제8권2호
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• pp.203-209
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• 2003

본 연구에서는 해양탐사장비를 예인하는 예인케이블에 관한 3차원 동적해석을 수행하였다. 해양케이블에 관한 지배방정식 중에서 굽힘강성 성분도 포함되는 보다 일반적인 지배방정식을 사용하였으며, 지배방정식은 3차원 비선형, 연성방정식이다. 예인선박의 예인속도와 측면주사음탐기의 중량에 따라서 예인단에서 발생하는 장력을 추정하였으며, 임의의 시간에 대한 케이블의 전체형상을 추정하였다. 정적해석결과를 통하여 특정한 수심에서 해양탐사장비를 예인할 때 예인속도를 잘못 조절한다면 관측장비가 해저면 바닥에 닿아서 탐사장비를 손실할 수 있다는 것을 알 수 있었다. 다양한 예인속도에 따른 예인단에서 장력의 변화를 살펴보았는데, 이를 통하여 예인단 장력은 예인속도가 임계속도보다 클 때는 접선하중성분이 지배적이고 작을 때는 자중효과가 지배적으로 나타난다는 것을 알 수 있었다. 또한 속도가 변하는 천이영역에서는 장력의 피크가 나타났으며 이것은 케이블에 충격력 효과로 작용할 수 있으므로 예인선박 운용에 이를 잘 고려해야 할 것이다. 본 연구결과는 다양한 해양탐사장비의 예인문제에 적용할 수 있을 것이다.

• 한국수자원학회:학술대회논문집
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• 한국수자원학회 2018년도 학술발표회
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• pp.145-145
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• 2018

Small islands rely heavily on groundwater resources in addition to rainwater as the source of freshwater since surface water bodies are often absent. The groundwater resources are vulnerable to sea level rise, coastal flooding, saltwater intrusion, irregular pattern of precipitation resulting in long droughts and flash floods. Increase in population increases the demand for the limited groundwater resources, thus aggravating the problem. In this study, the effects of climate change on Tongatapu Island, Kingdom of Tonga, a small island in Pacific Ocean, are investigated using a sharp interface transient groundwater flow model. Twenty nine downscaled General Circulation Model(GCM) predictions are input to a water balance model to estimate the groundwater recharge. The temporal variation in recharge is predicted over the period of 2010 to 2099. A set of GCM models are selected to represent the ensemble of 29 models based on cumulative recharge at the end of the century. This set of GCM model predictions are then used to simulate a total of six climate scenarios, three each (2010-2039, 2040-2069, and 2070-2099) under RCP 4.5 and RCP 8.5. The impacts of predicted climate change on groundwater resources is evaluated in terms of freshwater volume changes and saltwater ratios in pumping wells compared to present conditions. Though the cumulative recharge at the end of the century indicates a wetter climate compared to the present conditions the large variability in rainfall pattern results in frequent periods of groundwater drought leading to saltwater intrusion in pumping wells. Thus for sustaining the limited groundwater resources in small islands, implementation of timely assessment and management practices are of utmost importance.