• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 1997년도 봄 학술발표회 논문집
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• pp.147-151
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• 1997

The dynamic characteristics of Control Element Drive Mechanism (CEDM) in Korea standard Nuclear Power Plant was reviewed as a secondary mass in a simplified two degree of freedom system, while the reactor vessel as a primary mass. The design improvement stratege to minimize each displacement amplitude of these primary and secondary masses was proposed. According to this stratege the designs of CEDM components, the shroud and the pressure housing, respectively, were changed using optimization technique.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1996년도 한국자동제어학술회의논문집(국내학술편); 포항공과대학교, 포항; 24-26 Oct. 1996
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• pp.609-611
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• 1996

Zero-Cross Detector makes pilot signal to control the power to CEDM(Control Element Drive Mechanism). Existing Zero-Cross Detectors has had a problem which can cause unexpected reactor trip resulted from fluctuating frequency of input signal coming from M/G Set. The existing Zero-Cross Detector can't work properly when power frequency is varying because it was designed to work under stable M/G Set operation, and produces wrong pilot signal and output voltage. In this report the Zero-Cross Detector is improved to resolve voltage fluctuating problem by using new devices such as digital noise filtering circuit, variable cycle compensator and alarm circuit. And through the performance verification it shows that new circuit is better than old one. If suggested detector is applied to plant, it is possible to use it under House Load Operation because stable voltage can be generated by new Zero-Cross Detector.

• 전력전자학회:학술대회논문집
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• 전력전자학회 2002년도 전력전자학술대회 논문집
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• pp.249-252
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• 2002

최근 수년동안 의료 X-선 장비의 고전압 발생용 전원장치는 고주파 인버터 형태로의 개발이 가속화되어 단시간 촬영의 고성능화와 장치의 소형화 그리고 고전압 리플의 저감에 따른 피폭량 감소가 실현되고 있다. 본 논문은 이에 따른 의료 진단용 X-선 발생 시스템에서 40kW(125kV, 800mA)급 고주파 전원 발생장치 개발에 관한 것으로 고주파 고전압 인버터, 고주파 고전압 변압기를 포함한 고전압 발생 회로, X-선 관전압, 관전류 제어부, 시스템 구동부의 설계 개발에 대하여 기술하였고, 전체 구성된 시스템의 실험 파형에 따른 동작 특성을 제시하였다.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2003년도 학술회의 논문집 정보 및 제어부문 B
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• pp.555-558
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• 2003

When a fault relating to the urgent alarm occurs, we must prevent control rods from dropping and make one of two grippers in Control Rod Drive Mechanism (CRDM) grip the drive rod laking a control rod assembly. If a gripper with any problem is ordered to grip the drive rod, the gripper which cannot latch the rod stably will fail to take the rod. On the purpose of escaping this bad case, we order two grippers to hold the drive rod and enhance the reliability of holding control rods. This action is called the double hold. In the middle of the movement of the drive rod, the latching of the drive rod can cause friction between a gripper and the drive rod. This state may give damage to both the gripper and the drive rod. In this paper, we have devised the method which can have two grippers hold the drive rod more stably, without damaging the equipment.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 제36회 하계학술대회 논문집 D
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• pp.2606-2608
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• 2005

In this paper we describe the fault detection methods in a Dual-Redundant Power Controller(DRPC) for Control Rod Control System(CRCS). The DRPC has the function of fault detection for controller itself and power modules. And in this paper we have described the some complex items out of fault detection methods for CRCS. By utilizing the suggested methods, we are convinced that these methods are applied to commercial use before long.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2005년도 제36회 하계학술대회 논문집 D
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• pp.2609-2612
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• 2005

In this paper we proposed the real time monitoring system for power controller in CRCS. The proposed real time monitoring system can be utilized to adapt CRCS to real plant at initial step for commercial use. Through the this system, we are assured that CRCS is more easily fitted to real plant.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2004년도 하계학술대회 논문집 D
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• pp.2275-2277
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• 2004

Korea Next Generation Reactor(KNGR) is in the midst of being developed and will exceed Korea Standard Nuclear Power Plant(KSNP) economically. Domestic Instrumentation and Control(I&C) systems shall be applied to KNGR and the development of Control Element Drive Mechanism Control System(CEDMCS) considered as an essential part in nuclear I&C system will be dealt with in this paper. The newly developed CEDMCS has the control cabinet using the nuclear Distributed Control System(DCS) made in Korea and the power cabinet produced by our research institute and interfaced with the DCS control cabinet.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2003년도 학술회의 논문집 정보 및 제어부문 B
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• pp.552-554
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• 2003

This paper is about the method by which Power Control Unit(PCU) of Control Rod Control System(CRCS) logs events in the system and the real-time monitoring display. This method enables the functions like the event logging of Control Rod Drive Mechanism(CRDM)/power Cabinet, the off-line show of the event data logged and the on-line show by communication between the PCU and the monitoring display. Operators in a nuclear power plant must be able to grasp any possible abnormal states correctly. Because our newly designed system has a good ability to log and display the kinds, tine, and the prior and posterior states of urgent or non-urgent events, the operators can judge, maintain and repair the abnormal event more easily.

• 대한전기학회:학술대회논문집
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• 대한전기학회 2003년도 학술회의 논문집 정보 및 제어부문 B
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• pp.575-579
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• 2003

In this paper, we describe a Duplex Power Controller for Control Rod Control System(CRCS). A Duplex Power Controller has the various functions for the reliable operations of Control Rod Drive Mechanism(CRDM). Also we have implemented the diverse functions by utilizing the developed Duplex Power Controller. Due to the developed Duplex Power Controller, we are assured that the commercial operation by this system be made before long.

• Nuclear Engineering and Technology
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• 제26권2호
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• pp.197-204
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• 1994

원자로운전정지시 사용되는 제어봉집합체는 제어봉구동장치에서 분리되어 핵연료집합체의 안내관으로 자유낙하한다. 이 제어봉집합체의 주요변수로는 낙하시간과 충격속도가 있는데, 낙하시간은 원자로 안전정지와 관계가 있으며, 충격속도는 핵연료집합체의 건전성과 관계가 있다. 따라서, 제어봉 낙하시간과 충격속도의 적절한 결정은 제어봉집합체와 핵연료집합체의 설계에 매우 중요하다. 제어봉집합체는 낙하도중 유체저항이나 마찰력 및 부력과 같은 여러 힘들에 의해 낙하시간이 감소하게 되는데, 이러한 여러가지 힘의 복잡한 결합으로 인해 낙하시간과 충격속도를 해석적으로 유추하는 것은 매우 어렵다. 본 논문에서는 국산핵연료집합체에 적용되는 해석적인 방정식을 포함하고 있는 프로그램을 개발하였고, 이 프로그램을 단일제어봉 낙하시험과 비교하였다. 비교결과 시험 및 해석결과가 잘일치하고 있음으로써 개발된 프로그램의 검증을 확인할 수 있었고, 따라서 이 프로그램이 제어봉및 안내관의 설계변경시 매우 유용하게 사용할 수 있게 되었다.