Probabilistic analysis of PWR Reactor Pressure Vessel under Pressurized Thermal Shock
Probabilistic analysis of PWR Reactor Pressure Vessel under Pressurized Thermal Shock
This paper describes the benchmark study for deterministic and probabilistic fracture mechanics analyzing the beltline region under PTS by using FAVOR code developed by Oak Ridge National Laboratory. The Monte Carlo method was employed in FAVOR code to calculate the conditional probability of crack initiation.