METHOD OF RECEIVING OF URANIUM OXIDE AT PROCESSING OF URANIC FUEL ELEMENTS Russian patent published in 2009 - IPC G21C19/44 C01G43/01 C22B35/00 C22B26/22 

FIELD: metallurgy.

SUBSTANCE: invention relates to method of receiving of uranium oxide at processing of uranic fuel elements, coated by alloy magnesium-beryllium consisting in mechanical removal of non-reproducing structural component of fuel elements, fragmentation of fuel elements, removing of fuel elements' protective envelope made of alloy magnesium-beryllium at heating of fuel elements fragment up to the temperature 500-700°C in vacuum not lower 10^-4 anchor rings during 2-5 hours, vapor condensation of magnesium and oxidation of metallic uranium in medium of oxygen-containing agent at temperature 500-900°C in reactor pot, forming closed space with inner volume which is 2-4 of volume of charged metallic uranium and allowing openings, total area of which is from 5 up to 25% of surface area of reactor pot, herewith after achieving of temperature 500-900°C external source of heating is excluded.

EFFECT: new method of uranium oxide receiving.

7 ex, 1 tbl