Cadet Reniel Dela Cruz presented his work on "Monte Carlo Criticality and Burn-up Analysis of Accident-Tolerant Fuel Cladding Designs for Pressurized Water Reactors". The research aimed to determine the best Accident-Tolerant Fuel Cladding design for Pressurized Water Reactors. It focused on the neutronic aspect of the various cladding designs. Dela Cruz used Monte Carlo N-Particle transport code to simulate an infinite reactor with various cladding compositions designed to reduce hydrogen productions during a loss-of-coolant accident like the Fukushima Daiichi Nuclear Power Plant disaster. His work analyzed various proposed innovative designs and objectively determined the best composition based upon accident resistance, cost of enrichment and lifetime of the reactor core. Dela Cruz will present the results of his research at the annual American Nuclear Society Student Conference at the University of Florida in March 2018 and is working within the Department of Physics and Nuclear Engineering for a related Academic Individual Advanced Development (AIAD) through the Korea Advanced Institute of Science and Technology.
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