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A Safety Assessment Methodology for a Digital Reactor Protection System
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  • A Safety Assessment Methodology for a Digital Reactor Protection System
  • A Safety Assessment Methodology for a Digital Reactor Protection System
저자명
Lee. Dong-Young,Choi. Jong-Gyun,Lyou. Joon
간행물명
International Journal of Control, Automation and Systems
권/호정보
2006년|4권 1호|pp.105-112 (8 pages)
발행정보
제어로봇시스템학회
파일정보
정기간행물|ENG|
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기타
이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

The main function of a reactor protection system is to maintain the reactor core integrity and the reactor coolant system pressure boundary. Generally, the reactor protection system adopts the 2-out-of-m redundant architecture to assure a reliable operation. This paper describes the safety assessment of a digital reactor protection system using the fault tree analysis technique. The fault tree technique can be expressed in terms of combinations of the basic event failures such as the random hardware failures, common cause failures, operator errors, and the fault tolerance mechanisms implemented in the reactor protection system. In this paper, a prediction method of the hardware failure rate is suggested for a digital reactor protection system, and applied to the reactor protection system being developed in Korea to identify design weak points from a safety point of view.