A Probabilistic Methodology For Estimating Fuel Rod Fracture During Loss-Of-Coolant Accidents: Enhancing Reactor Safety Analysis

Dr. James A. Richards; Prof. Linda M. Turner

Authors

Dr. James A. Richards Department of Nuclear Engineering, Massachusetts Institute of Technology, Cambridge, MA, USA
Prof. Linda M. Turner Department of Mechanical and Aerospace Engineering, University of California, Berkeley, CA, USA

Keywords:

Probabilistic modeling, Loss-of-Coolant Accident (LOCA), fuel rod fracture, Monte Carlo simulation

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

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