• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2001년도 추계학술대회논문집 II
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• pp.1032-1039
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• 2001

In this paper, modal analysis of wind-power generator rotor system was performed by using finite element method. Experimental modal analysis of generator rotor system was performed and the result were compared with analytical ones. Sensitivity method and localized modification method were used to update finite element model. As a result of updating finite element model, errors of natural freguency were reduced within 0.5％ and MAC value was improved near by l. Stability characteristics of wind-power generator rotor-bearing system through harmonic analysis about several external force will be analyzed using finite element model.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2003년도 추계학술대회 논문집 전력기술부문
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• pp.488-490
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• 2003

This paprer presents the evlauation method for transmission marginal loss factors(MLFs) considering the electrical distance. Generally, MLFs are represented as the sensitivity of transmission losses, which is computed from the change of generation by the change of the load. MLFs are classified as load-focused MLFs and generator-focused MLFs. The existing evaluation method for generator focused MLFs has the limit not reflecting the characteristic of power systems since the method has been introduced the assumption which the output of a generator is supplied to all of the load buses on the power system. Therefore, to overcome the limit of evaluation method for generator-focused MLFs, we have applied the process, which it approximately can find the load buses that supplied a generator to the method. We have applied the proposed method to the simple 5-bus system because the proposed method is not analytic but the hybrid method incorporated the Kirschen and Bialek's algorithm to the existing analytic method to find the load buses supplied by a generator.

• 한국안전학회지
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• 제20권2호
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• pp.32-37
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• 2005

The purpose of this study is for the sensitivity study f9r a Steam Generator Tube Rupture (SGTR) of the System-integrated Modular Advanced ReacTor for a Pilot (SMART-P) plant. The thermal hydraulic analysis of a SGIR for the Limiting Conditions for Operation (LCO) is performed using TASS/SMR code. The TASS/SMR code can calculate the core power, pressure, flow, temperature and other values of the primary and secondary system for the various initiating conditions. The major concern of this sensitivity study is not the minimum Critical Heat Flux Ratio(CHFR) but the maximum leakage amount from the primary to secondary sides at the steam generator. Therefore the break area causing the maximum accumulated break flow is researched for this reason. In the case of a SGIR for the SMART-p, the total integrated break flow is 11,740kg in the worst case scenario, the minimum CHFR is maintained at Over 1.3 and the hottest fuel rod temperature is below 606"I during the transient. It means that the integrity of the fuel rod is guaranteed. The reactor coolant system and the secondary system pressures are maintained below 18.7MPa, which is system design pressure.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2013년도 추계학술대회
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• pp.375-378
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• 2013

본 논문에서는 EEPROM이나 MTP 등의 NVM 메모리 IP 설계에 필요로 하는 PVT(Process-Voltage-Temperature) 변동에 둔감한 기준전압(Reference Voltage) 회로를 설계하였다. 매그나칩반도체 $0.18{\mu}m$ EEPROM 공정을 이용하여 설계된 BGR(Bandgap Reference Voltage) 회로는 wide swing을 갖는 캐스코드 전류거울 (cascode current-mirror) 형태의 저전압 밴드갭 기준전압발생기 회로를 사용하였으며, PVT 변동에 둔감한 기준전압 특성을 보이고 있다. 최소 동작 전압은 1.43V이고 VDD 변동에 대한 VREF 민감도(sensitivity)는 0.064mV/V이다. 그리고 온도 변동에 대한 VREF 민감도는 $20.5ppm/^{\circ}C$이다. 측정된 VREF 전압은 평균 전압이 1.181V이고 $3{\sigma}$는 71.7mV이다.

• 비파괴검사학회지
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• 제21권5호
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• pp.518-525
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• 2001

증기발생기 전열관이 노후화 됨에 따라 새롭고 판단이 애매한 결함이 발생되기 시작하고 있다. 대부분의 결함은 전열관 외부에서 발생되어 진전된다. 일반 와전류탐상에서는 외부결함으로부터의 신호가 표피효과로 인해 내부결함으로부터의 신호보다 매우 약하기 때문에, 본 논문에서는 자성체 관 검사에서 내부 및 외부결함에 거의 같은 민감도를 보인 바 있는 원격장와전류 탐상을 비자성체인 전열관의 검사에 적용하기 위한 연구를 수행하였다. 유한요소 모델링을 통한 연구결과는 비자성체인 전열관에서 원격장와전류 효과가 나타나려면 탐상주파수가 수백 kHz가 되어야 하며, 여자코일과 센서코일간의 간격은 자성 관 검사시의 절반인 관 외경의 1.5배 정도가 되어야 함을 보였다. 이렇게 설계된 탐촉자를 사용하여 예측한 결함신호들은 이 검사방법이 내부 및 외부결함에 동일하게 민감하며, 위상신호의 세기와 결함깊이간에는 선형적인 비례관계가 존재함을 보여 주었다. 이러한 결과들은 비자성 증기발생기 전열관이라 할지라도 원격장와전류 탐상이 가능함을 말해 주고 있다.

• 한국전자통신학회논문지
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• 제15권1호
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• pp.179-184
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• 2020

랜덤성이 우수한 의사난수열 생성기로 알려진 셀룰라 오토마타(Cellular automata, CA)는 그 응용분야가 매우 다양하다. Cho 등은 긴 주기의 비선형 수열을 생성하기 위하여 CA기반의 수축수열 생성기를 설계하였다. 또한, 카오스 캣맵은 초기 조건에 대한 민감성과 예측 불가능한 특성을 가지는 복잡한 비선형 동역학계로 많은 연구자들에 의하여 연구되어 왔다. 본 논문에서는 높은 보안성을 위하여 최대 주기를 갖는 CA기반의 수축 생성기로 생성한 비선형 수열과 3차원 카오스 캣맵을 이용한 새로운 영상 암호화 방법을 제안한다.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2009년도 춘계학술대회 논문집
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• pp.504-508
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• 2009

To obtain high power, diesel engines continuously increase combustion pressure and mean effective pressure each cylinder, and the excitation sources and noisy sources are increased, too. Moreover, to reduce the costs, shipyards make hull structures weaker than before. As above reasons, it is more difficult to control the vibration phenomenon nowadays. In this study, it was investigated why diesel generator sets reached the vibration allowable limits during the FAT and heavy vibration phenomenon of diesel generator sets using ODS test during onboard tests. Also, it is found out the stiffness of deck and common bed using the test result of their structural impedance. To find out the vibratory characteristics of diesel generator sets, MODAL tests were carried out. From the sensitivity analysis after above tests, it was selected points to be reinforced and studied troubleshooting to solve heavy vibration phenomenon of diesel generator sets.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2000년도 추계학술대회논문집A
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• pp.837-842
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• 2000

In the coiling process of helical steam generator tubes of integral reactor SMART, a considerable amount of spring back, which induces dimensional inaccuracy and difficulty in fabrication, has been arised. In this research, an analytical model was derived to evaluate the amount of the spring back for steam generator tubes. The model was developed on the basis of beam theory and elastic-perfectly plastic material property. This model was extended to consider the effect of plastic hardening and the effect of the tensile force on the spring back phenomena. Parametric studies were performed for various design variables of steam generator tubes in order to minimize the spring back in the design stage. A sensitivity analysis has shown that the low yield strength, the high elastic modulus, the small helix diameter, and the large tube diameter result in a small amount of the spring back. The amount of the spring back can be controlled by the selection of adequate design values in the basic design stage and reduced to an allowable limit by the application of the tensile force to the tube during the coiling process.

• 한국정밀공학회지
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• 제22권10호
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• pp.137-143
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• 2005

The integrity of steam generator tubes in nuclear power plant should be maintained sufficiently during operation. For sake of this, complicated assessment procedures are required such as fracture mechanics analysis, etc. The integrity assessment of tubes has been performed by using conventional deterministic approaches while there are many uncertainties to carry out a rational evaluation. In this respect, probabilistic integrity assessment is considered as an alternative method for integrity assessment. The objectives of this study are to develop an integrity assessment system based on probabilistic fracture mechanics and to predict the failure probability of steam generator tubes containing an axial through-wall crack. The developed integrity assessment system consists of three evaluation modules, which apply first order reliability method, second order reliability method and Monte Carlo simulation method, respectively. The system has been applied to predict failure probability of steam generator tubes and the estimation results showed a promising applicability of the probabilistic integrity assessment system.

• Nuclear Engineering and Technology
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• 제35권3호
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• pp.179-190
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• 2003

The multiple steam generator tube rupture (SGTR) event scenario with available safety systems was experimentally and analytically evaluated. The experiment was conducted on the large scaled test facility to simulate the multiple SGTR event and investigate the effectiveness of operator actions. As a result, it indicated that the opening of pressurizer power operated relief valve was significantly effective in quickly terminating the primary-to-secondary break flow even for the 6.5 tubes rupture. In the analysis, the recent version of RELAP5 code was assessed with the test data. It indicated that the calculations agreed well with the measured data and that the plant responses such as the water level and relief valve cycling in the damaged steam generator were reasonably predicted. Finally, sensitivity study on the number of ruptured tubes up to 10 tubes was performed to investigate the coolant release into atmosphere. It indicated that the integrated steam mass released was not significantly varied with the number of ruptured tubes although the damaged steam generator was overfilled for more than 3 tubes rupture. These findings are expected to provide useful information in understanding and evaluating the plant ability to mitigate the consequence of multiple SGTR event.