• Proceedings of the KIEE Conference
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• 2004.07d
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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.

• Proceedings of the KIEE Conference
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• 1998.07b
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• pp.772-774
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• 1998

MMIS System of KNGR is composed of systems by using of digital equipment in general, and also interface function among systems is completed by a network. According to this, KNGR PCS also got rid of many kinds of interface cards which have been used for hardwired interface to outside system, and most of function in these cards is to be programmed by PLC. This paper defines the function and method which is to be programmed to PLC. And this paper presents new function which is to be added for operator's interface by using network. It is expected that PCS logic cabinet will be more simplified, satisfy KNGR design concept, and operation convenience will be increased.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.351-356
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• 1997

In the des19n of KNGR (Korea Next Generation Reactor), we believe that economy is one of the most important factors to be considered Thus, we reviewed and evaluated the consequences of designing the head area into an integrated package from an economical point of view. The refueling outage durations of the nuclear power plants currently in operation In Korea, some having and others not having integrated head package, are compared. This paper discusses the characteristics of head area design and the critical design issues of KNGR head area to evaluate the effect of the head area characteristics on the outage duration.

• Proceedings of the Earthquake Engineering Society of Korea Conference
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• 1999.10a
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• pp.137-146
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• 1999

The SSI(Soil-Structure Interaction) analyses are being performed for the KNGR(Korean Next Generation Reactor) design because the KNGR is developed as a standard nuclear power plant concept enveloping various soil conditions. the SASSI program which adopts the flexible volume method is used for the SSI analyses. The soil curves used in the three dimensional SSI analyses of KNGR Nuclear Island(NI) structures are based on the upper bound shear modulus curve and lower bound damping degradation on SSI response the average shear modulus curve with average damping curve was used for two soil cases. This study presents the results of the variances by using different soil nonlinearity parameters based on the paametric SSI analyses. The results include the maximum member forces(shear and axial force) at the base of the NI structures and the 5% damping Floor Response Spectra (FRS) at some representative locations at the top of the NI superstructures. They are also compared together with the enveloped SSI results for eight soil cases and fixed-base analysis for rock case by using two control motions.

• Proceedings of the KIEE Conference
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• 1998.07b
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• pp.807-809
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• 1998

Plant Protection Systems(PPS) are those systems that initiate safety actions to mitigate the consequences of design basis events by sending signals to Reactor Trip Switch Gear System(RTSS) and Engineered Safety Features-Component Control Systems(ESF-CCS). This paper illustrates distinctive features and improved design concepts of Korea Next Generation Reactor(KNGR) based on the experience obtained through prototyping of PPS.

• Proceedings of the KIEE Conference
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• 1998.07b
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• pp.813-815
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• 1998

Engineered Safety Features-Component Control Systems(ESF-CCS) are those I&C systems that control safety equipment used to maintain the integrity of reactor coolant pressure boundary. This paper illustrates distinctive features and improved design concepts of Korea Next Generation Reactor(KNGR) based on the experience obtained through prototyping of ESF-CCS.

• Proceedings of the KIEE Conference
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• 1999.07g
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• pp.3175-3177
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• 1999

In this study, the wireless communication system configuration and major equipments for KNGR will be introduced. Also the reliability and safety impact on the KNGR will be checked by reviewing /testing the EMI/RFI conditions of wireless communication system, The elements of the wireless communication system are radio exchange, base stations, portable telephone handsets.

• Nuclear industry
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• v.20 no.2 s.204
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• pp.62-67
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• 2000

• Nuclear industry
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• v.17 no.10 s.176
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• pp.26-31
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• 1997

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.118.2-118
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• 2001