지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술대회자료
- 저자정보
- 발행연도
- 2014.11
- 수록면
- 35 - 38 (4page)
이용수
초록· 키워드
오류제보하기
Nuclear power plant has been designed to be safe when there is an accident in the plant. There are many design features that mitigate the effect of accident and keep the plant in safe state. In instrumentation and control system, there are automatic systems which trip reactor or actuate safety features such as plant protection system and engineered safety features component control system. However, in some case of the accident, manual operator action is need for the plant safety. These manual operator actions are defined as important human actions (IHAs) and considered in plant design such as human system interfaces. IHAs are defined from probabilistic safety analysis and deterministic safety analysis. IHAs from deterministic safety analysis can be categorized by two, one is critical operator action and the other is non-critical operator action. Critical operator action is credited operator manual actions in transient and accident analyses and required for safety system to perform their safety-related functions. Non-critical operator action is also operator action in transient and accident analyses, but the manual action is not critical to plant safety. For example, there are operator actions for plant cool down after the accident is mitigated and the plant is in safe state. However, there are no clear criteria for the categorization. In this paper, the categorization criteria have been proposed and IHAs in transient and accident analyses have been categorized according to the criteria.
목차
ABSTRACT
1. Introduction
2. Scope of important human actions
3. Criteria for variable selection of accident monitoring
4. Critical operator action
4. Discussion
References
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UCI(KEPA) : I410-ECN-0101-2016-530-002499407