Fragility Analysis of the Reactor Steel Shaft Door Due to Accidental Extreme Overpressure
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Juraj Kralik
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| Transactions of the VSB - Technical University of Ostrava, Civil Engineering Series |
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2023, Volume 23, Issue 2, Pages 5-12
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Doi: 10.35181/tces-2023-0008
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This paper describes the probabilistic nonlinear analysis of the hermetic steel door of the reactor shaft failure due to extreme pressure and temperature. The probabilistic assessment of NPP structures for Probabilistic Safety Analysis (PSA2) level 2 of VVER 440/213 in the case of the technology accidents is presented. The scenario of the hard accident in nuclear power plant (NPP) and the methodology of the calculation of the fragility curve of the failure overpressure using the probabilistic safety assessment PSA 2 level is presented. The nonlinear deterministic and probabilistic analysis based on the response surface method (RSM) were considered.
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