b'3 ADVANCED REACTOR FUELS 1483.1Fuel Fabrication and Properties .Chemical Interaction and Compatibility of Uranium Nitride Fuelswith Liquid Pb and Alumina-forming Austenitic Alloys .1483.2AR Core Materials .152Advanced Reactor Core Materials 152HT9 Modeling 154Linear and Nonlinear Guided Ultrasonic Wavesto Characterize Cladding of Accident Tolerant Fuel 1563.3AR Irradiation Testing and PIE Techniques160Examination of FAST-1 Accelerated Fission Rate Metallic Fuel Test .160Microstructure and Micromechanical Characterizationof Cr Diffusion Barrier in ATR Irradiated U-10Zr Metallic Fuel.164Femtosecond Laser Ablation Machining & Examination -Center for Active Materials Processing (FLAME-CAMP) .1703.4AR Fuel Safety Testing .174Post-Transient Characterization of the Metal FuelTHOR-C-2 Experiment .174First Irradiated-Fuel Fast Reactor Experiments in TREAT:Assembly and Performance 176NEUP 20-19374: Maintaining and Building upon theHalden Legacy of In-situ Diagnostics .1823.5AR Performance Assessment 186Pre-Test Fuel Performance Evaluation of THOR-C Experiments .186FAST to EBR-II Comparison and HT9 Applicability .1902023|AFC ACCOMPLISHMENTS 7'