Fuel pellet fissile content variation in as-sintered fast reactor fuel

Previous studies have shown that a substantial reduction in the manufacturing costs of liquid metal fast breeder reactor fuel can be achived by a relaxation in the mixed uranium/plutonium oxide fuel pellet tolerance specification consistent with demonstrated process capabilities for as-sintered fuel. A number of studies were required to confirm that the proposed relaxations would not be detrimental to reactor core performance. One such study, which compared the expected variability of local fuel pellet fissile content with that allowed based upon reactor performance criteria, is reported herein.