• Proceedings of the KIEE Conference
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• 2004.11c
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• pp.559-561
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• 2004

In this paper, we design two types of Main Control Unit for Control Rod Control System and Control Element Drive Mechanism Control System, respectively, using a domestic Distributed Control System(DCS) developed to localize the instrumentation and control(I&C) system for nuclear power plant(NPP). There are many parts developed by domestic skills and being operated successfully in NPP, but the development of I&C system as an essential part has been slow in progress. We will show the great possibility of developing peculiar Korean I&C system by applying this domestic DCS to nuclear I&C system and confirming its successful operation.

• Proceedings of the KIEE Conference
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• 2004.11c
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• pp.741-743
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• 2004

In this paper, we describe a Control Element Drive Mechanism(CEDM) operation test using a Power Controller. By testing, we can catch the mechanical and electrical characteristics of CEDM and obtain the information about the improvement of CEDM and the design of CEDM power cabinet. The power controller for CEDM introduced in this paper can input firing angles directly into gate drive circuits of thyristors so that this method can be used to derive the maximum and minimum values of firing angles within available limits for a 3-phase half-wave rectifier. Angle inputs help us understand each coil's response characteristics. Since this power controller generates a serial sequence for CEDM insertion and withdrawal operations, we may judge whether CEDM works correctly as expected or not in each phase of a step movement.

• 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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• 1999.07f
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• pp.2754-2757
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• 1999

This paper describes the development of the linear pulse motor (herea-fter, LPM) and the driver system to control the quantity of fuel in the nuclear furnace. The LPM developed in this study is a kind of the linear motor with the properties of moving up and down, and both the stator and the mover of the LPM are designed as the salient type. Especially, the stator has windings but there is no windings or magnet on the mover. To Maximize the characteristics of the LPM, we chose the asymmetric bridge converter as the driving system for LPM.

• Proceedings of the KIEE Conference
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• 2004.07d
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• pp.2370-2373
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• 2004

In this paper we describe the design of a Dual-Redundant Power Controller(DRPC) for Control Rod Control System(CRCS). The CRCS also provides information regarding rod motion, rod position, and status of the Rod Control System. It has Hot/Stand-by type, and also has the function of fault detection for controller itself and power modules. We have implemented the various functions with the dual-redundant Power Controller. Due to the developed DRPC, we are assured that the commmecial use by this controller be made before long.

• Proceedings of the KIEE Conference
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• 2004.07d
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• pp.2298-2300
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• 2004

This paper does 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.

• 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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• 1999.11b
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• pp.98-100
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• 1999

A thermal analysis was performed for the electromagnet which is installed in the control element drive mechanism(CEDM) of the integral reactor SMART. A model for the thermal analysis of the electromagnet was developed and theoretical bases for the model were established. It is important that the temperature of the electromagnet windings be maintained within the allowable limit of the insulation, since the electromagnet of CEDM is always supplied with current during the reactor operation. So the thermal analysis of the winding insulation which is composed of polyimide and air were performed by finite element method. The thermal properties obtained here will be used as input for the optimization analysis of the electromagnet.

• Proceedings of the KIEE Conference
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• 2002.07d
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• pp.2646-2648
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• 2002

This paper deals with a comparative evaluation of the reliability of control rod drive mechanisms including their driving methods for nuclear power plants. Basically there exist two types of electromagnetic-jack-type drive mechanisms in commercial use that are called as Control Rod Drive Mechanism and Control Element Drive Mechanism. Each type has corresponding drive sequence to make the movements of insertion and withdrawal. A state-space model is derived for each model graphically. Then the evaluation of the reliability is carried out on the programming tool called SHARPE. The evaluation does not give any meaningful numerical values for the reliability but just shows a relative degree to each other in view of reliability.

• Proceedings of the KIEE Conference
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• 2002.07d
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• pp.2295-2297
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• 2002

In this paper, we describe a set of test facilities for the development of CRCS (Control Rod Control System). The test facilities consist of a code simulator CRDM (Control Rod Drive Mechanism) mockup, an input/output simulator for validation work and R-L load to simulate CRDM mockup.