DOE OSTI · 3031149
Legacy Metallic Fuel U(Pu)Zr Data Qualification
Abstract
The Metallic Fuels Irradiation and Physics Database (FIPD) is an organized collection of legacy metallic fuel U(Pu)Zr data, measurements, and reactor conditions from the Experimental Breeder Reactor II (EBR-II) and the Fast Flux Test Facility (FFTF). The database provides a wealth of information and is easily accessed and utilized by the U.S. nuclear industry and the Nuclear Regulatory Commission (NRC). The database contains three categories of data. The first category covers fuel pin fabrication specifications, including fuel slug diameter and length, cladding diameter, smeared density, etc. The second consists of operational conditions, which include axial distributions of power, temperature, fluence, burnup, isotopic density, etc. The third category contains post-irradiation examination (PIE) results, largely collected at facilities now part of the Idaho National Laboratory (INL), formerly part of Argonne National Laboratory -West (ANL-W) and at the Alpha-Gamma Hot Cell Facility (AGHCF) at Argonne National Laboratory, comprising fission gas release and chemistry analysis, profilometry measurements, neutron radiography data, etc. All these data have been organized and preserved in FIPD.
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Mo, Kun [Argonne National Laboratory (ANL), Argonne, IL (United States)], Oaks, Aaron [Argonne National Laboratory (ANL), Argonne, IL (United States)], Tomchik, Carolyn [Argonne National Laboratory (ANL), Argonne, IL (United States)], Schulthess, Jason L. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000242897528), Porter, Douglas L. [Idaho National Laboratory (INL), Idaho Falls, ID (United States)] (ORCID:0000000305456771), Yacout, Abdellatif [Argonne National Laboratory (ANL), Argonne, IL (United States)]. 2025-07-04. Legacy Metallic Fuel U(Pu)Zr Data Qualification. https://doi.org/10.2172/3031149
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