2018 | AFC ACCOMPLISHMENTS 77 and rupture criteria for both cladding materials.These simulations use previously-implemented properties for the Zircaloy cladding, and newly- implemented properties for the FeCrAl cladding, as available. Data used to develop the high-temperature plastic behavior and rupture models for FeCrAl are derived from experiments performed at Oak Ridge National Laboratory (ORNL). Accomplishments: The fuel rod geometries used in these simulations are representative of a Boiling Water Reactor (BWR)/4. Because of the parasitic thermal neutron absorption from the FeCrAl alloy cladding, the cladding is thinned while the fuel radius is enlarged to partially offset the neutronic penalty. The 2D-axisymmetric simulation Figure 1. The maximum cladding temperature for both cladding types as a function of time after the accident initiation. The results from the TRACE simulation are (black line) included in to provide a comparison.