Journal of Nuclear Materials
Journal of Nuclear Materials
4 years ago

Characterization of U-Zr fuel with alloying additive Sb for immobilizing fission product lanthanides

Characterization of U-Zr fuel with alloying additive Sb for immobilizing fission product lanthanides
Fission product lanthanides can migrate to the fuel periphery and enhance fuel-cladding chemical interaction (FCCI). Adding Sb into the fuel alloy to bind lanthanides and thus to prevent lanthanides from migration has been proposed. The U-Zr fuel alloys were fabricated with compositions of U-10Zr-4.1Sb, U-10Zr-4.1Sb-4Ce, U-10Zr-2.07Sb, and U-10Zr-2.07Sb-2Ce wt.% by arc melting, and analyzed under scanning electron microscope (SEM) for the microstructure and elemental compositions. In the Ce-free alloy, Sb was found in Sb-Zr precipitates; while in the Ce-contained alloy, Sb was found in the form of intermetallic compounds Ce4Sb3 and Ce2Sb without any Sb-Zr precipitates. Antimony has the preference to bind Ce over Zr, indicating Sb can effectively prevent Ce interaction with Fe to the extent. Cerium is bound to Sb and no ternary intermetallic Ce-Sb-Zr compound was found.

Publisher URL: www.sciencedirect.com/science

DOI: S0022311517311455

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