Development of production processes for mixed (U-Pu) oxides suitable for fast and thermal reactor fuel

Results are described of investigations on developing production processes for mixed uranium-plutonium fuel for fast and thermal reactors: sol-gel-spheres; granulated oxides through the ammonia precipitation, process oxides through carbonate precipitation. Advantages and shortcomings of the methods are considered. Specific features of corresponding apparatus are discussed. The developments are at the level of performance testing, during of whids were produced large quantities of the mixed fuel. The test fuel assemblies for the BN-600 were fabricated on the base of the produced fuel