FIELD: power industry.
SUBSTANCE: invention refers to methods for obtaining mixed uranium-plutonium nuclear fuel based on UO2 and PuO2 dioxides, which has the following name: MOX (Mixed-Oxide) fuel. Nitric-acid solution of nitrates of actinides is mixed with formic acid solution; the obtained solution is dried in air flow or inert atmosphere at the temperature of up to 140°C till solid mixture of formiates of the above elements, and then, the obtained mixture is annealed in inert atmosphere at temperatures of 400-450°C for decomposition of formiates.
EFFECT: invention allows decreasing heat treatment temperatures and excluding hydrogen use, which will lead to safety improvement and simplification of a method for obtaining mixed oxides of actinides.
4 cl
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RU2554626C2 |
| ACTINIDE NITRATES PREPARATION METHOD (VARIATIONS) | 2005 |
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| METHOD OF PRODUCING SOLID PLUTONIUM DIOXIDE SOLUTION IN URANIUM DIOXIDE MATRIX | 2015 |
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