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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 764 - 775 (12page)
이용수
초록· 키워드
오류제보하기
Periodic safety reviews (PSRs) are conducted on operating nuclear power plants (NPPs) and have been mandated also for research reactors in Korea, in response to the Fukushima accident. One safety review tool,the probabilistic safetyassessment(PSA),aims toidentify weaknesses in the designand operation of the research reactor, and to evaluate and compare possible safety improvements. However, the PSA for research reactors is difficult due to scarce data availability. An important element in the analysis of research reactors is the reactor protection system (RPS), with its functionality and importance. In this view, we consider that of the AGN-201K, a zero-power reactor without forced decay heat removal systems, to demonstrate a risk-informed safety improvement study. By incorporating risk- and safetysignificance importance measures, and sensitivity and uncertainty analyses, the proposed method identifies critical components in the RPS reliability model, systematically proposes potential safety improvements and ranks them to assist in the decision-making process.
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등록된 정보가 없습니다.
참고문헌 (38)
참고문헌 신청
International Atomic Energy Agency / 2013 / Periodic Safety Review for Nuclear Power Plants, IAEA Safety Standards / Specific Safety Guide No. SSG-25
US Nuclear Regulatory Commision / 1983 / PRA Procedures Guide: A Guide to the Performance of Probabilistic Risk Assessments for Nuclear, Power Plants
T.L. Chu / 2008 / Traditional Probabilistic Risk Assessment Methods for Digital Systems
T. D. Le Duy / 2018 / A practical methodology for modeling and estimation of common cause failure parameters in multi-unit nuclear PSA model / Reliab. Eng. Syst. Saf 170:159~174
T. Hakata / 2007 / Seismic PSA method for multiple nuclear power plants in a site / Reliab. Eng. Syst. Saf 92:883~894
US Nuclear Regulatory Commision / 1983 / PRA Procedures Guide: A Guide to the Performance of Probabilistic Risk Assessments for Nuclear, Power Plants
T.L. Chu / 2008 / Traditional Probabilistic Risk Assessment Methods for Digital Systems
T. D. Le Duy / 2018 / A practical methodology for modeling and estimation of common cause failure parameters in multi-unit nuclear PSA model / Reliab. Eng. Syst. Saf 170:159~174
T. Hakata / 2007 / Seismic PSA method for multiple nuclear power plants in a site / Reliab. Eng. Syst. Saf 92:883~894
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