Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
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Sensitivity Analyses for Failure Probabilities of the OPR1000 Reactor Vessel Under Pressurized Thermal Shock

가압열충격에 의한 OPR1000 원자로용기의 파손확률 민감도 해석

  • Received : 2019.10.30
  • Accepted : 2019.12.11
  • Published : 2019.12.30
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Abstract

In this paper, failure probabilities of the OPR1000 reactor vessel under pressurized thermal shock (PTS) were estimated using the probabilistic fracture mechanics code, R-PIE. Input variables of initial crack distribution, crack size, copper contents, and upper shelf toughness were selected for the sensitivity analyses. A wide range of the input data were considered. Through-wall cracking frequencies determined by the product of the vessel failure probability and the corresponding occurrence frequency of the transient were also compared to the acceptance criterion. The results showed that transient history had the most significant impact on the vessel failure probability. Moreover, conservative assumptions resulted in extremely high through-wall cracking frequencies.

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References

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