A robust and reliable code to model the irradiation behavior of metal and oxide fuels in sodium cooled fast reactors is developed. Modeling capability was enhanced by adopting a non-empirical mechanistic approach to the extent possible, so that to increase the ability to extrapolate the existing database with a reasonable accuracy. Computational models to analyze in-reactor behavior of U-Zr and U-Pu-Zr metallic alloy fuel pins and U0 2-PuO 2 mixed oxide fuel pins have been developed and implemented into a new code, the Fuel Engineering and Structural analysis Tool (FEAST). FEAST has several modules working in coupled form with an explicit numerical algorithm. These modules describe (1) Fission Gas Release and Swelling, (2) Fuel Chemistry and Restructuring, (3) Temperature Distribution, (4) Fuel Clad Chemical Interaction, (5) Fuel and Clad Mechanical Analysis and (6) Transient Creep- Fracture Model for the clad. Given the fuel pin geometry, composition and irradiation history, FEAST can analyze fuel and cladding thermo-mechanical behavior at both steady state and design-basis accident scenarios. FEAST was written in FORTRAN-90 program language. The FEAST-METAL code mechanical analysis module implements the old Argonne National Laboratory (ANL)'s LIFE code algorithm.
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