Both deterministic and probabilistic methods are used to assess the integrity of a reactor pressure vessel (RPV) subjected to pressurized thermal shocks (PTSs). The FAVOR code is applied to calculate the probabilities for crack initiation and failure of the RPV subjected to two transients, by considering crack distributions based on cracks observed in the Shoreham and pressure vessel research user facility (PVRUF) RPVs. The crack parameters, i.e., crack density, depth, aspect ratio, orientation, and location are assumed as random variables following different distributions. KI of the cracks with the same depth increases with its aspect ratio. Both KI and KIc at the crack tip increase with crack depth, which is the reason why a deeper crack does not necessarily lead to a higher failure probability. The underclad crack is the most critical crack and the deeper crack is the least critical one in this study. Considering uncertainties of the transients results in higher failure probabilities.
Probabilistic Pressurized Thermal Shocks Analyses for a Reactor Pressure Vessel
Nuclear Energy and Safety Research Department,
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received August 6, 2014; final manuscript received March 31, 2015; published online May 20, 2015. Assoc. Editor: Kunio Hasegawa.
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Qian, G., and Niffenegger, M. (December 1, 2015). "Probabilistic Pressurized Thermal Shocks Analyses for a Reactor Pressure Vessel." ASME. J. Pressure Vessel Technol. December 2015; 137(6): 061206. https://doi.org/10.1115/1.4030299
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