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- W2369651569 abstract "According to RCC-M rule and NRC 10CFR50.61,the PTS analysis was performed for the reactor pressure vessel beltline with assumed defect.The end of life reference temperature TR of nuclear power plant was calculated and assessed with PTS screening criteria.The stress intensity factors were calcu-lated under PTS transients and assessed with RCC-M Rule." @default.
- W2369651569 created "2016-06-24" @default.
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- W2369651569 date "2012-01-01" @default.
- W2369651569 modified "2023-09-23" @default.
- W2369651569 title "Pressurized Thermal Shock Analysis for Reactor Pressure Vessels" @default.
- W2369651569 hasPublicationYear "2012" @default.
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