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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.1
- 수록면
- 614 - 620 (7page)
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In a previous study, delayed hydride cracking (DHC) assessment of pressurized water reactor (PWR) spent fuel during dry storage using the threshold stress intensity factor (KIH) was performed. However, there were a few limitations in the analysis of the cladding properties, such as oxide thickness and mechanical properties. In this study, those models were modified to include test data for irradiated materials, and the cladding creep model was introduced to improve the reliability of the DHC assessment. In this study, DHC susceptibility of PWR spent fuel during dry storage depending on the axial elevation was evaluated with the improved assessment methodology. In addition, the sensitivity of affecting parameters such as fuel burnup, hydride thickness, and crack aspect ratio are presented
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참고문헌 (25)
참고문헌 신청
J. D. Hong / 2017 / Delayed hydride cracking assessment of PWR spent fuel during dry storage / Nucl. Eng. Des 322:324~330
U.S. Nuclear Regulatory Commission / 2014 / Identification and Prioritization of the Technical Information Needs Affecting Potential Regulation of Extended Storage and Transportation of Spent Nuclear Fuel
B. Hanson / 2012 / Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analyses
Y. R. Rashid / 2000 / Creep as the Limiting Mechanism for Spent Fuel Dry Storage
C. E. Coleman / 2011 / Delayed Hydride Cracking Considerations Relevant to Spent Nuclear Fuel Storage
U.S. Nuclear Regulatory Commission / 2014 / Identification and Prioritization of the Technical Information Needs Affecting Potential Regulation of Extended Storage and Transportation of Spent Nuclear Fuel
B. Hanson / 2012 / Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analyses
Y. R. Rashid / 2000 / Creep as the Limiting Mechanism for Spent Fuel Dry Storage
C. E. Coleman / 2011 / Delayed Hydride Cracking Considerations Relevant to Spent Nuclear Fuel Storage
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