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Structural Engineering and Mechanics Volume 37, Number 3, February10 2011 , pages 257-265 DOI: https://doi.org/10.12989/sem.2011.37.3.257 |
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Comparison of vessel failure probabilities during PTS for Korean nuclear power plants |
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M.J. Jhung,Y.H. Choi and Y.S. Chang
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| Abstract | ||
| Plant-specific analyses of 5 types of domestic reactors in Korea are performed to assure the structural integrity of the reactor pressure vessel (RPV) during transients which are expected to initiate pressurized thermal shock (PTS) events. The failure probability of the RPV due to PTS is obtained by performing probabilistic fracture mechanics analysis. The through-wall cracking frequency is calculated and compared to the acceptance criterion. Considering the fluence at the end of life expected by surveillance test, the sufficient safety margin is expected for the structural integrity of all reactor pressure vessels except for the oldest one during the pressurized thermal shock events. If the flaw with aspect ratio of 1/12 is considered to eliminate the conservatism, the acceptance criteria is not exceeded for all plants until the fluence level of 8 x 1019 n/cm2, generating sufficient margin beyond the design life. | ||
| Key Words | ||
| pressurized thermal shock; reactor pressure vessel; structural integrity; stress intensity factor; failure probability; through-wall cracking. | ||
| Address | ||
| M.J. Jhung: Korea Institute of Nuclear Safety, 19 Guseong-dong, Yuseong-gu, Daejeon 305-338, Korea Y.H. Choi: Korea Institute of Nuclear Safety, 19 Guseong-dong, Yuseong-gu, Daejeon 305-338, Korea Y.S. Chang: Kyung Hee University, Seocheon-dong, Giheung-gu, Yongin 446-701, Korea | ||