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Recovery of uranium from solutions

Patent ·
OSTI ID:6240875
; ;

A process is described of separating uranium from a dilute waste solution derived from the ammonium diuranate process of converting UF/sub 6/ to UO/sub 2/ and containing U(VI), fluoride ion, and ammonium ion, which comprises adding sodium hydrosulfite to the solution and recovering a precipitate containing fluorine, sodium, ammonium, and U(IV).

Assignee:
Advanced Nuclear Fuels Corp., Richland, WA
Patent Number(s):
US 4668482
OSTI ID:
6240875
Country of Publication:
United States
Language:
English

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Related Subjects

052001* -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACTINIDE COMPLEXES
ACTINIDE COMPOUNDS
ACTINIDES
ALKALI METAL COMPOUNDS
AMMONIUM COMPOUNDS
AMMONIUM URANATES
CHALCOGENIDES
COMPLEXES
DILUTION
ELEMENTS
FLUORIDES
FLUORINE COMPOUNDS
HALIDES
HALOGEN COMPOUNDS
HIGH-LEVEL RADIOACTIVE WASTES
LIQUID WASTES
MANAGEMENT
MATERIALS
METALS
OXIDES
OXYGEN COMPOUNDS
PRECIPITATION
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
REMOVAL
SEPARATION PROCESSES
SODIUM COMPOUNDS
SULFITES
SULFUR COMPOUNDS
URANATES
URANIUM
URANIUM COMPLEXES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM FLUORIDES
URANIUM HEXAFLUORIDE
URANIUM OXIDES
WASTE MANAGEMENT
WASTE PROCESSING
WASTES