Synthesis and characterization of zirconia-magnesia inert matrix fuel: Uranium homolog studies

Journal Article · Wed Oct 21 00:00:00 EDT 2009 · J. Nucl. Mater.

DOI:https://doi.org/10.1016/j.jnucmat.2009.06.007· OSTI ID:1005910

Holliday, Kiel; Hartmann, Thomas; Poineau, Frederic; Kennedy, J Rory; Czerwinski, Ken

X-ray powder diffraction, X-ray fluorescence, microscopy, X-ray absorption fine structure, and electron probe microanalysis were used to characterize ZrO₂–MgO inert matrix fuel containing UO₂ (as a fissile element and a Pu homolog) and Er₂O₃ as a burnable poison. A large composition range of MgO and ZrO₂ was evaluated to determine total concentrations, local environment, phases present, phase mixing, and phase composition. It was found that most compositions of the material consist of two phases: MgO (periclase) and ZrO₂ (cubic zirconia). The zirconia phase incorporates up to 5% (wt/wt) MgO and up to 20% and 10% (wt/wt) UO₂ and Er₂O₃ respectively. This allows the fissile material and burnable poison to be incorporated into the zirconia crystal structure and defines the limits of this isomorphic substitution. The bond deformation due to the isomorphic substitution of uranium was determined by X-ray absorption fine structure. The MgO phase remains pure, which will enable design optimization of the overall thermophysical properties of the inert matrix fuel in regard to thermal diffusivity and thermal conductivity. This characterization data will be used in future studies to correlate the dissolution behavior of inert matrix material containing plutonium.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE
• OSTI ID: 1005910
• Journal Information: J. Nucl. Mater., Vol. 393, Issue (2) ; 09, 2009
• Country of Publication: United States
• Language: ENGLISH