Structural Engineering and Mechanics

  • 제37권3호
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  • Pages.257-265
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  • 2011
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  • 1225-4568(pISSN)
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  • 1598-6217(eISSN)
테크노프레스 (Techno-Press)
권호 표지
DOI QR코드

DOI QR Code

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)
  • 투고 : 2009.09.25
  • 심사 : 2010.10.12
  • 발행 : 2011.02.10
⟨ 이전 논문 다음 논문 ⟩

초록

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.

키워드

참고문헌

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피인용 문헌

  1. Evaluation of RPV according to alternative fracture toughness requirements vol.53, pp.6, 2015, https://doi.org/10.12989/sem.2015.53.6.1271
  2. A new design concept for ocean nuclear power plants using tension leg platform vol.76, pp.3, 2011, https://doi.org/10.12989/sem.2020.76.3.367