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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 185 - 191 (7page)
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초록· 키워드
오류제보하기
Plant-specific analyses of an advanced reactor have been performed to assure the structural integrity of the reactor pressure vessel during transient conditions, which are expected to initiate pressurized thermal shock (PTS) events. The vessel failure probabilities from the probabilistic fracture mechanics analyses are combined with the transient frequencies to generate the through-wall cracking frequencies, which are compared to the acceptance criterion. Several sensitivity analyses are performed, focusing on the orientations and sizes of cracks, the copper content, and a flaw distribution model. The results show that the integrity of the reactor vessel is expected to be maintained for long-term operation beyond the design lifetime from the PTS perspective using the design data of the advanced reactor. Moreover, a fluence level exceeding 9✕1019 n/cm2 is found to be acceptable, generating a sufficient margin beyond the design lifetime.
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참고문헌 (12)
참고문헌 신청
H.G. Kim / 2009 / Design characteristics of the advanced power reactor 1400, in: International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21 Century :96~98
OECD / 2008 / Proceedings of the CSNI Workshop on Structural Reliability Evaluation and Mechanical Probabilistic Approaches of NPP Components
IAEA / 2010 / Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment
KINS / 2016 / A-Pro2: Phase 2 ASINCO Project for Probabilistic Fracture Mechanics Analysis e Korea Results
UKAEA / 1982 / An Assessment of the Integrity of the PWR Pressure Vessels, Second Report by a Study Group under the Chairmanship of Dr. W. Marshall
OECD / 2008 / Proceedings of the CSNI Workshop on Structural Reliability Evaluation and Mechanical Probabilistic Approaches of NPP Components
IAEA / 2010 / Pressurized Thermal Shock in Nuclear Power Plants: Good Practices for Assessment
KINS / 2016 / A-Pro2: Phase 2 ASINCO Project for Probabilistic Fracture Mechanics Analysis e Korea Results
UKAEA / 1982 / An Assessment of the Integrity of the PWR Pressure Vessels, Second Report by a Study Group under the Chairmanship of Dr. W. Marshall
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