대한전기학회:학술대회논문집 (Proceedings of the KIEE Conference)
- 대한전기학회 1998년도 하계학술대회 논문집 B
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- Pages.813-815
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- 1998
차세대 원자력 발전소에서의 공학적안전설비작동계통 Prototype 기능의 구현
Prototype Development for KNGR Engineered Safety Features-Component Control Systems
- Park, Jong-Beom (Korea Electric Power Research Institute) ;
- Park, Hyun-Shin (Korea Electric Power Research Institute) ;
- Chang, Ik-Ho (Korea Power Engineering Company., INC)
- 발행 : 1998.07.20
초록
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.
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