FIELD: separation.
SUBSTANCE: invention relates to methods for extraction purification of reprocessed uranium from technetium and can be used in technological processes for recycling irradiated nuclear fuel, wherein tributyl phosphate (TBP) in a hydrocarbon diluent is used as an extractant and wherein purification of uranium from beta-active technetium-99 is needed. The method for extraction purification of uranium extract from technetium includes counter-current washing of the uranium extract containing tributyl phosphate in a hydrocarbon diluent, uranium and technetium, with an aqueous nitric acid solution. The uranium extract is therein washed with a nitric acid solution of uranyl nitrate containing 300 to 500 g/l of uranium and 0.1 to 0.3 mol/l of nitric acid. The uranium extract is washed at the ratio of the flows of the organic and aqueous phases O:A no more than 5.1:1.
EFFECT: method provides an increase in the degree of purification of uranium extract from technetium and a reduction in the transfer of nitric acid with the extract.
2 cl, 2 tbl
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RU2354728C2 |
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RU2517651C1 |
Authors
Dates
2022-03-22—Published
2021-04-12—Filed