Development and Preliminary Verification of Oxide Fuel Performance Analysis Code FUTURE for Lead-based Fast Reactor

To simulate and analyze the performance and behaviors evolution of oxide fuel for lead-based fast reactor under steady operating condition, the fuel performance analysis code FUTURE was developed based on the semi-implicit coupling solution method. This code adopted a two-step analysis method to achieve the coupling calculation of the global thermomechanical analysis and the local behavior models of the oxide fuel element on the lead-based fast reactor. Through the comparison of each calculation module with the related model examples, the benchmark formula and the existing similar codes, FUTURE code was preliminarily verified and tested all separate effects. The comparison result indicates that FUTURE code can accurately simulate the temperature evolution, structural deformation and stress distribution inside the fuel element, and achieve the computational simulation of fuel restructuring, oxygen and plutonium migration, fission gas release and liquid lead-bismuth corrosion during steady-state operating.