The neutronics characteristics of four possible driver fuels for the Fast Test Reactor (FTR) are compared. The fuels investigated are PuO2-SS and UO2-SS cermets and PuO2-238UO2 and UO2-238UO2 ceramics. Since a high flux is of paramount importance in a test reactor, low-inventory plutonium-fueled cores are found to be quite attractive for use in the FTR. For core volumes of approximately 600 liters, cermet fuels offer a higher neutron flux and a larger shutdown coefficient than oxide ceramic fuels. If the latter fuels are used, BeO could be added to enhance the Doppler coefficient.