SiC and FeCrAl as Potential Cladding Materials for APR-1400 Neutronic Analysis

The aim of this study is to investigate the potential improvement accident-tolerant fuels in pressurized water reactors for replacing existing reference zircaloy (Zr) fuel-cladding systems. Three main strategies improving are investigated: enhancement present state-of-the-art zirconium system improve oxidation resistance, replacement current referenced material with an alternative high-performance oxidation-resistant cladding, and fuel forms. This focuses on a preliminary analysis neutronic behavior properties silicon carbide (SiC)-fuel FeCrAl cladding systems, which provide better safety margin as systems reactors. typical physical both investigated determine their general performance. multiplication factor, thermal neutron flux spectrum, 239Pu inventory, pin power distribution, radial analyzed compared those Zr system. Furthermore, effects burnable poison rod (Gd2O3) different assemblies investigated. SiC softer spectrum lower linear distribution conventional Zr-fuel-cladding Additionally, exhibits behaviors that consistent thereby affording greater economic improvements.