To investigate a means of eliminating quartz mold waste, U-3Zr and U-2
0.5Pu-3Zr fuel was injection cast into Zr tubes, or sheaths, and clad
in 316SS. These elements and U-10Zr and U-19Pu-10Zr fuel elements, cas
t in the standard manner into disposable quartz molds, were irradiated
in EBR-II to 2 at% burnup and removed for interim examination. Measur
ments of fuel column axial growth indicate that the Zr-sheathed fuel e
xhibited significantly less axial elongation than the standard-cast fu
el (1.3 to 1.8% versus 4.9 to 8.1%). Fuel material extruded through th
e ends of the Zr sheaths, contacting the cladding in some cases. Trans
verse metallographic sections reveal cracks in the Zr sheath, indicati
ng that the sheath is not a sufficient barrier between fuel and claddi
ng to reduce fuel-cladding chemical interaction (FCCI). FCCI effects w
ill be monitored as the elements attain higher burnup.