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
- 학술저널
- 저자정보
- 발행연도
- 2012.1
- 수록면
- 459 - 470 (12page)
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초록· 키워드
오류제보하기
From the PSA point of view, the Fukushima accident of Japan in 2011 reveals some issues to be re-considered and/or improved in the PSA such as the limited scope of the PSA, site risk, etc. KAERI (Korea Atomic Energy Research Institute)has performed researches on the development of an integrated risk assessment framework related to some issues arisen after the Fukushima accident. This framework can cover the internal PSA model and external PSA models (fire, flooding, and seismic PSA models) in the full power and the low power-shutdown modes. This framework also integrates level 1, 2 and 3PSA to quantify the risk of nuclear facilities more efficiently and consistently. We expect that this framework will be helpful to resolve the issue regarding the limited scope of PSA and to reduce some inconsistencies that might exist between (1) the internal and external PSA, and (2) full power mode PSA and low power-shutdown PSA models. In addition, KAERI is starting researches related to the extreme external events, the risk assessment of spent fuel pool, and the site risk. These emerging issues will be incorporated into the integrated risk assessment framework. In this paper the integrated risk assessment framework and the research activities on the emerging issues are outlined.
목차
등록된 정보가 없습니다.
참고문헌 (26)
참고문헌 신청
/ 2008 / MAAP5-Modular Accident Analysis Program for LWR Power Plants / Fauske & Associates, Inc
American National Standards Institute(ANSI) / 2007 / External Events in PRA Methodology / ANSI/ANS 58.21-2007
American Society of Mechanical Engineers (ASME) / 2009 / Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications / AMSE/A
Committee on the Safety and Security of Commercial Spent Nuclear Fuel Storage, National Research Council / 2006 / Safety and Security of Commercial Spent Nuclear Fuel Storage: Public Re
D. Chanin / 1998 / Code Manual for MACCS2 / NUREG/CR-6613, SAND97-0594, Prepared for U.S. Nuclear Regulatory Commission
American National Standards Institute(ANSI) / 2007 / External Events in PRA Methodology / ANSI/ANS 58.21-2007
American Society of Mechanical Engineers (ASME) / 2009 / Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications / AMSE/A
Committee on the Safety and Security of Commercial Spent Nuclear Fuel Storage, National Research Council / 2006 / Safety and Security of Commercial Spent Nuclear Fuel Storage: Public Re
D. Chanin / 1998 / Code Manual for MACCS2 / NUREG/CR-6613, SAND97-0594, Prepared for U.S. Nuclear Regulatory Commission
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