FIELD: uranium extraction from spent nuclear fuel and production wastes of metal uranium, its alloys and parts.
SUBSTANCE: proposed method includes uranium oxidation in solvent. Dissolved gases such as chlorine, nitrogen oxides, or sulfur dioxide are used as oxidants. Dipolar aprotic solvent or that mixed up with chlorine-containing compound is used as solvent. Trialkyl phosphates, dialkyl phosphates, trialkyl phosphine oxides, organic acid amines, dialkyl sulfoxides, nitriles, and esters can be used as dipolar aprotic solvents. Tetrachloroethylene of 0 - 90% concentration is used as chlorine-containing compound. Dissolution is conducted at temperature of 10 - 90 °C.
EFFECT: enhanced water-free dissolution speed of metal uranium and uranium-containing materials using cheap oxidants under fire-proof conditions.
6 cl, 1 ex, 1 tbl
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Authors
Dates
2004-10-20—Published
2002-08-19—Filed