• The Transactions of the Korean Institute of Power Electronics
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• v.3 no.1
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• pp.36-45
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• 1998

A simple source voltage clamped resonant link (SVCRL) inverter is proposed to clamp the DC link voltage to the input source voltage and reduce the current rating of resonant inductor. The current control of a permanent magnet synchronous motor (PMSM) using a predictive current control technique (PCCT) employing the SVCRL inverter is also investigated to overcome the disadvantage of the current regulated delta modulation (CRDM) control technique. By using the PCCT based on the discrete model of a PMSM and estimation of back EMF, the minimized current ripple with small number of switchings can be obtained. Finally, the comparative computer simulation and experimental results are given to show the usefulness of the proposed technique.

• Proceedings of the KIEE Conference
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• 2003.07d
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• pp.2215-2217
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• 2003

In this paper we describe a Control Rod Control System(CRCS) with the various functions for the test and operation of Control Rod Drive Mechanism(CRDM). The CRCS controls the motion of the full length rod drive mechanisms in response to signals from the Reactor Operator and the Reactor Regulating System. The mechanisms are grouped and identified as being for either Shutdown Banks or Control Banks. The CRCS also provides information regarding rod motion, rod position, and status of the Rod Control System. Also we have implemented the diverse functions in the developed CRCS. Due to the developed CRCS, we are assured that the commercial operation by this system be made before long.

• 제어로봇시스템학회:학술대회논문집
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• 2002.10a
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• pp.65.5-65
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• 2002

$\textbullet$ Introduction $\textbullet$ Description of Prototype CRDM $\textbullet$ Theoretical Approach for estimating the gap variation between lift pole and lift armature $\textbullet$ Experimental Setup $\textbullet$ Experimental Results $\textbullet$ Conclusions

• Journal of the Korean Magnetics Society
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• v.26 no.5
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• pp.154-158
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• 2016

A CRDM (Control Rod Drive Mechanism) is an electromagnetic device which drives a control rod assembly linearly to regulate the reactivity of a nuclear core. An RPIS (Rod Position Indication System) is used as a position indicator for a control rod assembly of a CRDM of SMART, and an RPIS consists of permanent magnets and reed switches. SMART is designed for the maximum coolant temperature of $350^{\circ}C$, and the permanent magnets are installed inside of the reactor. The reed switches and electrical circuit are installed outside of the reactor on the other hand. Test coil for a reed switch is test equipment for quality verification of a reed switch, and a test coil consists of a coil and core. In this study, magnetic property of test coil and permanent magnet on a reed switch is compared by using finite element electromagnetic simulation.

• Proceedings of the KIEE Conference
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• 1996.07a
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• pp.567-570
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• 1996

A predictive current control technique for an induction motor employing a resonant DC link inverter is proposed to overcome the disadvantage of the current regulated delta modulation(CRDM) which was employed to control the resonant DC link inverter. The discrete model of an induction motor and estimation of back EMF are investigated and a novel predictive current control technique is newly developed based on this discrete model and estimated back EMF. Using the proposed control technique, the minimized current ripple with reduced offset can be obtained. The usefulness of the proposed technique is verified through the computer simulation.

• Journal of the Korean Society for Nondestructive Testing
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• v.16 no.1
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• pp.46-51
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• 1996

원자로는 압력용기 및 내부 구조물로 구분되어 있다. 내부 구조물들의 경련 열화 현상에 따라 결함이 많이 발생하여 이에 대한 초음파검사가 요구되고 있다. 따라서 원자로 내부 구조물에 대한 초음파검사 현황 및 각각 구조물들의 검사 원리를 기술하였다. 특히 원자로 내부 구조물 중 CRDM, core baffle bolt, core barrel bolt, CRGT-support pin 및 fuel alignment pin에 대한 유럽 및 독일을 중심으로 한 검사 현황 및 검사방법을 간략하게 기술하였다. 이 기술에 대한 지침안(guideline)이 독일, 프랑스, 일본을 중심으로 하여 마련되고 있다.

• Proceedings of the KIEE Conference
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• 2005.07d
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• pp.2655-2657
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• 2005

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 taking a control rod assembly. To enhance the reliability of holding control rods, we order two grippers to hold the drive rod. This action is called the double holding. 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.

• Proceedings of the KIEE Conference
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• 2004.07d
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• pp.2301-2303
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• 2004

This paper proposes a detection method for mechanically stuck control rod drive mechanisms (CRDMs) in the nuclear reactor. From an electrical viewpoint, a coil of an electro-mechanical CRDM is modelled as an R-L circuit with time-varying inductance. The inductance of the coil is estimated from the measured voltage and current by using the least square method. Numerical experiments are carried out to illustrate the proposed method.

• Proceedings of the KIEE Conference
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• 2003.11c
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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.

• Proceedings of the KIEE Conference
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• 2003.11c
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• pp.567-570
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• 2003

This paper deals with the design, implementation, and test of a CRCS for nuclear power plants. Although CRCS is still classified into non-safety class, much attention on its reliability issue has been given so far because of its importance for the stable operation of the reactor in the plant. In terms of technical aspects, our system adopts a full-duplex configuration to enhance reliability in contrast to the existing systems that are all simplex.