A common plate-type fuel for research and test reactors is U3O8 dispersed in aluminum and clad with an aluminum alloy. There is an impetus to reduce the 235U enrichment from above 90% to below 20%) for these fuels to lessen the risk of diversion of the uranium for nonpeaceful uses. Thus, the uranium content of the fuel plates has to be increased to maintain the performance of the reactors. Work at Oak Ridge National Laboratory has determined the maximal uranium loading for these fuels that can be fabricated with commercially proven materials and techniques and that can be expected to perform satisfactorily in service. Assuming satisfactory performance in irradiation tests to the required burnup, we anticipate being able to increase the uranium loading in U3O8-Al dispersions to the 3.1 Mg U/m3 level (75 wt% U3O8). This loading level will allow many research reactors to be fueled by uranium of <20% enrichment.