• Nuclear Engineering and Technology
• /
• 제47권2호
• /
• pp.148-156
• /
• 2015

Several vendors have recently been actively pursuing the development of integral pressurized water reactors (iPWRs) that range in power levels from small to large reactors. Integral reactors have the features of minimum vessel penetrations, passive heat removal after reactor shutdown, and modular construction that allow fast plant integration and a secure fuel cycle. The features of an integral reactor limit the options for placing control and safety system instruments. The development of instrumentation and control (I&C) strategies for a large 1,000 MWe iPWR is described. Reactor system modeling-which includes reactor core dynamics, primary heat exchanger, and the steam flashing drum-is an important part of I&C development and validation, and thereby consolidates the overall implementation for a large iPWR. The results of simulation models, control development, and instrumentation features illustrate the systematic approach that is applicable to integral light water reactors.

• 드라이브 ㆍ 컨트롤
• /
• 제10권3호
• /
• pp.21-26
• /
• 2013

This paper presents a robust motion tracking control of a cylinder-toggle servomechanism for injection molding machines. Virtual design model has been developed for a five-point type toggle mechanism. A sliding function is defined and combined with PID control to accommodate mismatches between the real plant and the linear model used. From tracking control simulations, it is shown that significant reduction in position tracking error is achieved with clamping force build-up through the use of proposed control scheme.

• 한국가스학회지
• /
• 제20권3호
• /
• pp.22-29
• /
• 2016

조직특성 및 안전문화는 매우 다양한 요인들을 포함하고 있으며, 그러한 안전문화의 향상을 위해서는 다양한 방법으로 접근되어야 한다. 구조방정식모형 분석을 통해 복합화력발전소의 안전문화 요인의 영향관계 검증결과 경영진의 관심도가 증가할수록 교육훈련정도의 향상과, 의사소통 및 안전참여의 향상에 긍정적인 역할을 함을 알 수 있었다. 그리고, 교육훈련 강도가 높을수록 근무향상에 도움이 될 것이 예측되었다.

• Nuclear Engineering and Technology
• /
• 제44권8호
• /
• pp.919-928
• /
• 2012

The applications of computers and communication system and network technologies in nuclear power plants have expanded recently. This application of digital technologies to the instrumentation and control systems of nuclear power plants brings with it the cyber security concerns similar to other critical infrastructures. Cyber security risk assessments for digital instrumentation and control systems have become more crucial in the development of new systems and in the operation of existing systems. Although the instrumentation and control systems of nuclear power plants are similar to industrial control systems, the former have specifications that differ from the latter in terms of architecture and function, in order to satisfy nuclear safety requirements, which need different methods for the application of cyber security risk assessment. In this paper, the characteristics of nuclear power plant instrumentation and control systems are described, and the considerations needed when conducting cyber security risk assessments in accordance with the lifecycle process of instrumentation and control systems are discussed. For cyber security risk assessments of instrumentation and control systems, the activities and considerations necessary for assessments during the system design phase or component design and equipment supply phase are presented in the following 6 steps: 1) System Identification and Cyber Security Modeling, 2) Asset and Impact Analysis, 3) Threat Analysis, 4) Vulnerability Analysis, 5) Security Control Design, and 6) Penetration test. The results from an application of the method to a digital reactor protection system are described.

• 한국건설관리학회:학술대회논문집
• /
• 한국건설관리학회 2002년도 학술대회지
• /
• pp.188-191
• /
• 2002

This paper concerns 3-D graphical modeling and simulation techniques for design and control of automated equipment for construction and facility maintenance. A case study on the use of 3-D graphics techniques for developing a power plant maintenance robot is presented. By simulating equipment operation within the 3-D geometry models of the work environment the environment design was improved. The 3-D graphical models of the equipment and the work environment were further utilized for the control of the robot from a remote distance. By presenting the real-time updated equipment configuration and the work environment to the operator, the graphical model-based equipment control system helped the operator overcome the problems associated with spatial perception. The collision between the robot and the plant structures was also avoided based the real-time analysis of the dynamically updated graphical models.

• Journal of Electrical Engineering and Technology
• /
• 제7권3호
• /
• pp.297-303
• /
• 2012

This paper presents the simulation results for the analysis of a lightning surge, switching transients and very fast transients within a thermal plant. The modeling of gas insulated substations (GIS) makes use of electrical equivalent circuits that are composed of lumped elements and distributed parameter lines. The system model also includes some generators, transformers, and low voltage circuits such as 24V DC rectifiers and control circuits. This paper shows the simulation results, via EMTP (Electro-Magnetic Transients Program), for three overvoltage types, such as transient overvoltages, switching transients, very fast transients and a lightning surge.

• 대한전기학회논문지
• /
• 제45권4호
• /
• pp.501-510
• /
• 1996

The gas-turbine generator of Seo-Incheon combined-cycle plant was tested for derivation of a model for dynamic analysis. Load rejection and AVR step test was performed to get the dynamic response of generator. The parameters of generator/control system model were determined by these measured data. No-load saturation test was performed for the saturation characteristics of the generator under steady state. V-curve test was also performed so as to find exact generator parameters. Q-axis parameters of generator was derived by measuring power angle. AVR and governor constants have been tuned by their oscillatory period and setting time characteristics. The derived parameters of generator control system is verified by one-machine infinite bus system simulation. (author). 7 refs., 20 figs., 5 tabs.

• 드라이브 ㆍ 컨트롤
• /
• 제11권2호
• /
• pp.9-15
• /
• 2014

This paper deals with the issue of force synchronizing control for the clamping servomechanism of injection molding machines. Prior to the controller design, a virtual design model has been developed for the clamping mechanism with hydraulic systems. Then, a synchronizing controller is designed and combined with an adaptive feedforward control in order to accommodate the mismatches between the real plant and the linear model plant used. As a disturbance, the leakage due to the ring gap with relative motion in the cylinder has been introduced. From the robust force tracking simulations, it is shown that a significant reduction in the force synchronizing error is achieved through the use of a proposed control scheme.

• 드라이브 ㆍ 컨트롤
• /
• 제18권3호
• /
• pp.16-22
• /
• 2021

The variable structure controller has the characteristic that while in sliding mode, the system moves along the switching plane in the vicinity of the switching plane, so it is robust to the parameter fluctuations of the plant. However, a controller based on a variable structure may not meet the desired performance when it is commanded to track any input or exposed to disturbances. To solve this problem, a sliding mode controller based on the IVSC approach excluding an integrator is proposed in this study. The proposed sliding mode control was applied to the position control of a hydraulic cylinder piston. The sliding plane was determined by the pole placement and the control input was designed to ensure the existence of the sliding mode. The feasibility of the modeling and controller was reviewed by comparing it with a conventional proportional control through computer simulation using MATLAB software and experiment in the presence of significant plant parameter fluctuations and disturbances.

• 한국화재소방학회논문지
• /
• 제27권2호
• /
• pp.80-88
• /
• 2013

원자력발전소의 밀폐된 다중 구획에서 환기부족화재에 대한 FDS 검증이 수행되었다. 수치결과는 OECD/NEA PRISME 프로젝트를 통해 얻어진 실험결과와 비교되었다. 환기시스템의 수치 경계조건 및 FDS에 적용된 소화모델이 구획 내부의 열적 및 화학적특성에 미치는 영향이 상세히 논의되었다. 점화 및 소화 단계에서 구획 내부의 급격한 압력변동에 의해 변화될 수 있는 환기 유량의 수치 경계조건은 다중 구획 내부의 온도, 열유속에는 큰 영향을 주지 않지만, 농도의 정확한 예측을 위하여 주위 깊게 고려되어야 한다. FDS에 적용된 소화모델의 기본값은 인위적인 소화 및 재점화 현상을 동반하며, 해당 연료에 대한 수정된 소화모델의 정보가 적용되었을 때 환기부족화재에 대한 FDS의 결과는 실험결과를 매우 잘 예측하고 있음을 확인하였다.