Transactions of the Korean Society of Mechanical Engineers A (대한기계학회논문집A)

The Korean Society of Mechanical Engineers (대한기계학회)
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Probabilistic Fracture Mechanics Analysis of Reactor Vessel for Pressurized Thermal Shock - The Effect of Residual Stress and Fracture Toughness -

가압열충격에 대한 원자로 용기의 확률론적 파괴역학해석 - 잔류응력 및 파괴인성곡선의 영향 -

  • 정성규 (한국전력기술(주) 전력기술개발연구소) ;
  • 진태은 (한국전력기술(주) 전력기술개발연구소) ;
  • 정명조 (한국원자력안전기술원 원자력안전연구실) ;
  • 최영환 (한국원자력안전기술원 원자력안전연구실)
  • Published : 2003.06.01
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Abstract

The structural integrity of the reactor vessel with the approaching end of life must be assured for pressurized thermal shock. The regulation specifies the screening criteria for this and requires that specific analysis be performed for the reactor vessel which is anticipated to exceed the screening criteria at the end of plant life. In case the screening criteria is exceeded by the deterministic analysis, probabilistic analysis must be performed to show that failure probability Is within the limit. In this study, probabilistic fracture mechanics analysis of the reactor vessel for pressurized thermal shock is performed and the effects of residual stress and master curve on the failure probability are investigated.

Keywords

References

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  1. Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock vol.19, pp.2, 2005, https://doi.org/10.1007/BF02916185