Using the BISON fuel performance code, simulations were conducted of an automated process to read initial and operating conditions from the Pacific Northwest National Laboratory (PNNL) database and reports, which contained metallic fuel data from the Fast Flux Test Facility (FFTF) Mechanistic Fuel Failure (MFF). This work builds off previous modeling efforts involving 1,977 EBR-II metallic fuel pins. Coupling the PNNL database and reports to BISON allowed for all 338 pins from MFF-3 and MFF-5 to be simulated. Each BISON simulation contained a unique power history, flux history, axial power and flux profiles, and coolant channel flow rates. Fission gas release (FGR), fuel axial swelling, cladding profilometry, and burnup were all simulated in BISON and compared to available Post Irradiation Examination (PIE) data. Cladding profilometry, FGR, and fuel axial swelling simulation results for full length MFF metallic pins were found to be in agreement with PIE measurements using physics and models from EBR-II simulations. The main two peaks observed within the cladding profilometry were able to be simulated, with Fuel Cladding Mechanical Interaction (FCMI), Fuel Cladding Chemical Interaction (FCCI), and thermal creep being the cause. A U-Pu-Zr hot-pressing model was included in this work to allow pore collapse within the fuel matrix. This allowed better agreement between BISON simulated cladding profilometry and PIE measurements for the peak caused by FCMI. This work shows that metallic fuel models used to accurately represent fuel performance for smaller EBR-II pins may be used for full length metallic fuel, such as FFTF MFF assemblies and the Versatile Test Reactor (VTR).
