FIELD: power engineering.
SUBSTANCE: method for processing of irradiated nuclear fuel consists in grinding of uranium oxides by means of their multiple oxidation and recovery at the temperature of 700-900°C. At the same time oxidation and recovery are carried out by means of DC voltage supply to electrodes. Solid electrolyte with oxygen-ion conductivity is applied onto one of electrodes to separate this electrode from uranium oxides and pressed to the oxide, and the second one is partially applied onto the solid electrolyte at the side of the oxide, and is partially submerged into the oxide, this voltage is maintained for a period of time required for current flow in amount of 480-500 coulombs per one gramme of uranium oxide, de-energising electrodes, supplying voltage of opposite polarity, maintenance for the same period of time, de-energising and repeating cyclic supply of voltage and de-energising until the oxide is ground down to nanoparticles.
EFFECT: invention makes it possible to carry out controlled oxidation and recovery of uranium oxides, to simplify technological process.
1 cl, 1 tbl, 1 ex
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Authors
Dates
2012-01-27—Published
2010-12-15—Filed