Abstract
The deployment of a suitable, Pu-bearing inert matrix fuel (IMF) could offer an attractive option as a oncethrough
LWR strategy aimed at reducing the currently growing plutonium stockpiles. A development programme focusing on
yttria stabilized zirconia (YSZ)-based IMF is conducted at PSI. YSZ-based IMF has so far been irradiated in two test
reactors. The material characterization of the irradiated material by ceramography, electron probe micro analysis, and x-ray
diffraction are presented. IMF fabrication by attrition milling of the oxide constituents is possible, but high sintering
temperatures are required to achieve homogeneity. X-ray diffraction is a suitable tool to monitor the homogeneity.
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