Assessment of the Probability of Failure of Reactor Vessels After Warm Pre-stressing Using Monte Carlo Similations
Source abstract
Abstract
The probability of failure of reactor vessel with semi–elliptic crack after warm pre-stressing was assessed taken into account the scatter of mechanical properties and loading parameters by Monte–Carlo with importance sampling and first–order reliability method based on limit–state functions from FITNET procedure. The failure assessment diagrams were obtained by means of Monte–Carlo simulations for different crack depth and variable internal pressure.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Probabilistic and Robust Engineering Design · Fatigue and fracture mechanics · Nuclear reactor physics and engineering
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References (9)
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