METHOD FOR EXTRACTIVE RECOVERY OF URANIUM- CONTAINING SOLUTIONS Russian patent published in 2001 - IPC

FIELD: nuclear fuel reprocessing. SUBSTANCE: method designed for reprocessing fissionable fuel of nuclear power plants, enriched uranium, uranium-containing recovered items, wastes, and reusable solutions includes uranium extraction by means of tributyl phosphate solution in carbon hydroxide solvent and uranium re-extraction by means of solutions containing 60-400 g/l of carbamide. Re-extraction process temperature and organic-to-reextraction solution flow ratio is chosen from following conditions: , where t is re-extraction process temperature, C; N is flow ratio of source organic solution to source re-extraction solution; Yu is uranium content of extract, mole/l; Yn is nitric acid content of extract, mole/l; Xc is carbamide content of re-extraction solution, mole/l. EFFECT: eliminated nitric acid carbamide precipitation in uranium re-extracts; enhanced uranium content and volume of re-extract. 4 tbl, 1 ex