FIELD: metallurgy.
SUBSTANCE: proposed process comprises leaching of uranium by nitric acid and separation of water phase from undissolved precipitate. Then, undissolved precipitate is mixed with fluorine-bearing agent, dissolution of produced charge and/or charge as a suspension in nitric acid solution. Produced solution is returned to production process for extraction of uranium. Nitric acid concentration in solution makes at least 2 mol/l. Dilution is carried out at fluorine-ion concentration at, at least, 15 g/l. Dilution is performed at 60-100°C.
EFFECT: decreased losses of uranium, minimised wastes.
4 cl, 1 dwg, 1 tbl
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Authors
Dates
2014-04-27—Published
2012-12-03—Filed