METHOD FOR DRY TREATMENT OF NUCLEAR FUEL SCRAP OF MIXED URANIUM AND PLUTONIUM DIOXIDES Russian patent published in 2004 - IPC

FIELD: nuclear fuel production and treatment. SUBSTANCE: method for dry treatment of nuclear fuel scrap of mixed (U, Pu)O₂, formed during fuel manufacture or conveying it to wastes in case its use is not needed or ceased includes dosing and first mixing of powdered scrap and in some cases PuO₂ and/or UO₂ powders. Then primary mixture obtained is pulverized and forced through screen, screened mixture is dosed once more and mixed up with PuO₂ powders and in some cases with powder wastes. Second mixture is pelletized and pellets obtained are sintered. Pre-treatment waste processing includes pelletizing and sintering of powdered scrap to produce pellets from wastes and fine pulverization of pellets from wastes to introduce them as powdered wastes in first mixture and/or in second mixture. EFFECT: ability of in-situ treatment of nuclear fuel scrap. 12 cl, 2 dwg, 1 tbl