b'TALENT PIPELINE: The original database contained post-irradiation data obtained from nearly 2,000 Travis Wright, student test fuel pins from the Experimental Breeder Reactor-II (EBR-II) and covered a wide at Texas Tech University variety of fuel and cladding compositions, operating temperatures, and lifetimes. Abhilasha Lokannavar, student Using the new database template, researchers also gathered information for at North Carolina State University experiments performed in the Fast Flux Test Facility as part of qualification efforts Patrick Eblen, student to include metal fuel driver in the Fast Flux Test Facility. The Fast Flux Test Reactor at Idaho State University experiment used fuel pins with a core height nearly three times that of EBR-II, Ammon Black, student a height that more closely matches that of recently proposed reactors. With the at Utah State University help of the documentation of analyses performed at Pacific Northwest National Kyle Paaren, INL postdoc Laboratory for the physics and other operational information and the post-irradiation examination collected at INL, the required information was put into a structured query language database that could later be added to the Fuels Irradiation & Physics Database. BISON modeling analysis demonstrated the success of these efforts, which are relevant to many new startup reactor types. For example, DOE and Arc Clean Energy have expressed interest for the Versatile Test Reactor and the ARC-100 advanced small modular reactor, respectively.PUBLICATIONS:Paaren, K. M., M. Gale, M. J. Kerr, P. G. Medvedev, and D. L. Porter, Initial demonstration of automated fuel performance modeling with 1,977 EBR-II metallic fuel pins using BISON code with FIPD and IMIS databases, Nuclear Engineering and Design 382 (2021) 111393.Paaren, K. M., N. Lybeck, K. Mo, P.G. Medvedev, and D. L. Porter, Cladding profilometry analysis of EBR-II metallic fuel pins with HT9, D9, and SS316 cladding, Energies 14(2) (2021) 515.Gribok, A. V., D. L. Porter, K. M. Paaren, M. D. Gale, S. C. Middlemas, and N. J. Lybeck, Automatic information extraction from neutron radiography imaging to estimate axial fuel expansion in EBR-II, Journal of Nuclear Materials 557 (2021) 153250.PRESENTATION:Wright, T. R., and D. L. Porter, Utilization of several post-irradiation measurement techniques to determine axial growth in EBR-II fuel, American Nuclear Society Winter Meeting 2019, Washington D.C., USA, Nov. 1721, 2019.33'