b'Metallic Alloy Fuels for TransmutationPrincipal Investigator: Randall Fielding & Luca CapriottiTeam Members/ Collaborators: Brian Newbold, and Hot Fuel Examination Facility and Fuel Manufacturing Facility OperatorsFigure 1. Neutron radiography of IRT1 rodlets, (a) thermal neutron radiography (Dy foil) and (b) epithermal (In foil). Each panel shows R1, R2, and R5 from left to right. Highlighted in the red square is the sodium plug on top of IRT1-R1.I n collaboration with the JointIRT-1 test was fabricated using U-TRU Fuel Cycle Studies project post- material recovered from used mixed irradiation examination (PIE) wasoxide (MOX) fuels. An addition of performed on three rodlets from thevarious lanthanide elements was added irradiation test (IRT)-1 fuel irradiationto the fuel to simulate fission prod-test. The follow-on irradiation test,ucts that may be carried over during IRT-2, was fabricated using U-TRUrecycling high burnup fuel. Three test material recovered through recyclingrodlets underwent PIE showing accept-of used light water reactor fuel.able irradiation behavior. Following Project Description: irradiation of the IRT-1 test, a follow-on This work was one of the main goalstest, IRT-2 was fabricated. The IRT-2 test of the Joint Fuel Cycle Studies (JFCS)used U-TRU feed material recovered project; to fabricate, irradiate andfrom used light water reactor fuel. The perform PIE on metallic, transuranicfuel alloys did not include the addition (TRU) bearing fuels, using feedstockof surrogate fission products, as was recycled from used oxide fuels. Thedone for the IRT-1 test, to determine the irradiation behavior of recycled used 132 2021|AFC ACCOMPLISHMENTS'