Structural Engineering and Mechanics

Techno-Press (테크노프레스)
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Comparison of vessel failure probabilities during PTS for Korean nuclear power plants

  • Jhung, M.J. (Korea Institute of Nuclear Safety) ;
  • Choi, Y.H. (Korea Institute of Nuclear Safety) ;
  • Chang, Y.S. (Kyung Hee University)
  • Received : 2009.09.25
  • Accepted : 2010.10.12
  • Published : 2011.02.10
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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 $8{\times}10^{19}\;n/cm^2$, generating sufficient margin beyond the design life.

Keywords

References

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