FIELD: extraction processing of uranium-containing solutions.
SUBSTANCE: invention can be used in the technology of processing irradiated nuclear fuel of nuclear power plants, as well as various uranium-containing solutions, including recycled materials. The processing method includes extraction of uranium from uranium-containing solutions with an organic solution of tributyl phosphate in an inert diluent, washing the extract with a nitric acid solution. Re-extraction of uranium is carried out with an aqueous solution of 1.0-2.5 mol/l of glycine and 0.03-0.07 mol/l of nitric acid.
EFFECT: invention allows to reduce losses of uranium with the circulating extraction solvent, to increase the technological stability of the process and the possibility of recycling mother liquors after precipitation of uranium from re-extracts.
2 cl, 4 tbl
| Title | Year | Author | Number |
|---|---|---|---|
| IRRADIATED NUCLEAR FUEL EXTRACTION PROCESSING METHOD | 2020 |
|
RU2727140C1 |
| METHOD FOR EXTRACTIVE RECOVERY OF URANIUM- CONTAINING SOLUTIONS | 1999 |
|
RU2170964C1 |
| METHOD OF EXTRACTION PROCESSING OF URANIUM-CONTAINING SOLUTIONS | 1997 |
|
RU2114469C1 |
| METHOD OF CONTINUOUSLY EXTRACTION COUNTERFLOW CONCENTRATING OF ELEMENTS | 0 |
|
SU1588428A1 |
| METHOD TO SEPARATE URANIUM AND PLUTONIUM IN EXTRACTION TECHNOLOGY OF SPENT NUCLEAR FUEL RECYCLING | 2010 |
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RU2449393C2 |
| METHOD OF PLUTONIUM EXTRACTION AND PURIFICATION | 2018 |
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| EXTRACTION SEPARATION OF ZIRCONIUM AND HAFNIUM | 2012 |
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RU2521561C2 |
| METHOD FOR RECOVERY OF IRRADIATED THORIUM MATERIALS | 2001 |
|
RU2200993C2 |
| METHOD OF PROCESSING HIGH-ACTIVITY WASTE WITH FRACTIONATION OF RADIONUCLIDES | 2019 |
|
RU2709826C1 |
| METHOD OF EXTRACTION PROCESSING OF NPP SPENT NUCLEAR FUEL | 2014 |
|
RU2574036C1 |
