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Microstructural characterization of U‐Zr alloy fuel slugs for sodium‐cooled fast reactor
Author(s) -
Kim KiHwan,
Oh SeokJin,
Kim SunKi,
Lee ChongTak,
Lee ChanBock
Publication year - 2012
Publication title -
surface and interface analysis
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.52
H-Index - 90
eISSN - 1096-9918
pISSN - 0142-2421
DOI - 10.1002/sia.4989
Subject(s) - materials science , microstructure , alloy , metallurgy , spent nuclear fuel , casting , scanning electron microscope , sodium cooled fast reactor , dispersion (optics) , metal , composite material , nuclear chemistry , chemistry , physics , optics
In order to investigate a fabrication process of metallic fuel for sodium‐cooled fast reactor, U‐Zr fuel slugs were fabricated with gravity casting and injection casting. In order to reduce the formation of radioactive wastes, and to have a fine microstructure, spherical powder of U‐Zr alloy was also fabricated by centrifugal atomization. The microstructural characteristics were investigated by using electron microscopes and energy‐dispersive electron X‐ray spectroscope. U‐10wt.%Zr fuel slugs had some dispersion phases of Zr precipitates and Zr compounds of about 5 µm in size. The matrix was composed of fine laminar structure of about 0.15 µm in thickness. U grains became finer from about 30 µm in conventionally cast fuel slug to about 2 µm in atomized powder. Laminar structure became so fine from 0.2 µm in conventionally cast fuel slug to 0.1 µm in atomized powder. It is possible for atomized metallic fuel to have a fine microstructure, resulting in a higher fission gas release rate during irradiation. Copyright © 2012 John Wiley & Sons, Ltd.