A high-resolution neutron radiographic system has been developed at the University of Washington Nuclear Reactor to radiograph mixed oxide particle fuels. The method was tested without fuel using TiO2, Eu2O3, and RhO2 mixtures as analogs for the oxides of U, 239Pu, and 240Pu, respectively. These analogs have microscopic cross sections similar to the fuel isotopes. Two weight percent PuO2-UO2 fuel rod radiographic analogs were built containing PuO2 analog particle diameter distributions from 0 to 800 μm. These radiographic analogs were radiographed with resonant energy neutrons using the activation transfer neutron detection technique to examine both the homogeneity of the mixed oxide and the imaging of the various diameter PuO2 analog particles. A divergent neutron collimator was designed to successfully complete this study. Also, an experiment was performed to determine the contrast sensitivity of neutron radiography for the radiographic discrimination between the analog for 239PuO2 and the analog for 240PuO2.