Determination of Average Burnup in AGR-2 Compacts 3-3-1, 3-3-2, 2-2-2, and 6-4-2

Technical Report · Sun Sep 01 00:00:00 EDT 2019

DOI:https://doi.org/10.2172/1569364· OSTI ID:1569364

Hunn, John D.  ^[1]; Montgomery, Fred C.  ^[1]; Keever, Tamara {Tammy} J.  ^[1]; Roach, Benjamin D.  ^[1]; Ilgner, Ralph H. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Burnup measurements have been performed on irradiated tristructural-isotropic (TRISO) particle fuel compacts from the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program’s second irradiation experiment (AGR-2). The AGR-2 irradiation experiment used TRISO particles fabricated by BWX Technologies (Barnes and Marshall 2009) and formed into compacts in the Oak Ridge National Laboratory (ORNL) Coated Particle Fuel Development Laboratory. Two compact lots were fabricated that differed in kernel type. The compact lot designated by LEU09-OP2-Z contained kernels made up of uranium carbide and uranium oxide (UCO) that were nominally 425 µm in diameter and 14% enriched (Hunn, Montgomery, and Pappano 2010a). The compact lot designated by LEU11-OP2-Z contained kernels made of only uranium dioxide (UO₂) that were nominally 500 µm in diameter and 9.6% enriched (Hunn, Montgomery, and Pappano 2010b). The addition of carbide to the kernel provides a getter for excess oxygen generated by the fission of UO₂.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1569364
• Report Number(s): ORNL/TM-2019/1315
• Country of Publication: United States
• Language: English