A PROBABILISTIC METHODOLOGY FOR ESTIMATING FUEL ROD FRACTURE DURING LOSS-OF-COOLANT ACCIDENTS: ENHANCING REACTOR SAFETY ANALYSIS

Abstract

The structural integrity of nuclear fuel rods during a Loss-of-Coolant Accident (LOCA) is critical for reactor safety. This paper proposes a probabilistic approach to estimate the fracture behavior of nuclear fuel rods under LOCA conditions. Through a combination of numerical simulations, material testing, and probabilistic modeling, we aim to provide a best estimate of fuel rod fracture during LOCA. The study incorporates various uncertainties in input parameters such as temperature, pressure, mechanical properties, and material degradation. The results offer a more robust prediction for reactor safety analysis, improving our understanding of fuel rod behavior under accident conditions and enhancing the reliability of safety margin evaluations in nuclear reactors.