Process for recovering uranium
Abstract
A process useful in recovering uranium from deposits on stainless steel liner surfaces of calutrons is presented. The deposit is removed from the stainless steel surface by washing with aqueous nitric acid. The solution obtained containing uranium, chromium, nickel, copper, and iron is treated with an excess of ammonium hydroxide to precipitnte the uranium, iron, and chromium and convert the nickel and copper to soluble ammonio complexions. The precipitated material is removed, dried and treated with carbon tetrachloride at an elevated temperature of about 500 to 600 deg C to form a vapor mixture of UCl/ sub 4/, UCl/sub 5/, FeCl/sub 3/, and CrCl/sub 4/. The UCl/sub 4/ is separated from this vapor mixture by selective fractional condensation at a temperature of about 500 to 400 deg C.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4206040
- Patent Number(s):
- 2879130
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01G - COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
- NSA Number:
- NSA-13-022160
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
- Subject:
- CHEMISTRY; AMMONIA; BERYLLIUM OXIDES; CALUTRON; CARBON TETRACHLORIDE; CHEMICAL REACTIONS; CHEMICALS; CHROMIUM; CHROMIUM CHLORIDES; CHROMIUM COMPOUNDS; CHROMIUM NITRATES; COMPLEXES; CONDENSERS; CONTROL; COPPER; COPPER COMPOUNDS; COPPER NITRATES; CRACKS; CYLINDERS; DECONTAMINATION; DISTILLATION; FAILURES; FILMS; FILTERS; HEAT TREATMENTS; HIGH TEMPERATURE; IMPURITIES; INSTRUMENTS; IRON CHLORIDES; IRON; IRON COMPOUNDS; IRON NITRATES; ISOTOPE SEPARATION; LEACHING; LIQUEFYING; MASS SPECTROMETERS; MATERIALS TESTING; MIXING; NICKEL; NICKEL COMPOUNDS; NICKEL NITRATES; NITRIC ACID; NUMERICALS; OPERATION; PATENT; PRECIPITATION; QUENCHING; REACTORS; RECOVERY; SEPARATION PROCESSES; SOLIDIFICATION; SOLIDS; SOLUBILITY; SOLUTIONS; STAINLESS STEELS; SURFACES; TEMPERATURE; TENSILE PROPERTIES; THERMAL; URANIUM; URANIUM CHLORIDES; URANIUM COMPOUNDS; VAPORS; WATER
Citation Formats
MacWood, G. E., Wilder, C. D., and Altman, D. Process for recovering uranium. United States: N. p., 1959.
Web.
MacWood, G. E., Wilder, C. D., & Altman, D. Process for recovering uranium. United States.
MacWood, G. E., Wilder, C. D., and Altman, D. Tue .
"Process for recovering uranium". United States. https://www.osti.gov/servlets/purl/4206040.
@article{osti_4206040,
title = {Process for recovering uranium},
author = {MacWood, G. E. and Wilder, C. D. and Altman, D.},
abstractNote = {A process useful in recovering uranium from deposits on stainless steel liner surfaces of calutrons is presented. The deposit is removed from the stainless steel surface by washing with aqueous nitric acid. The solution obtained containing uranium, chromium, nickel, copper, and iron is treated with an excess of ammonium hydroxide to precipitnte the uranium, iron, and chromium and convert the nickel and copper to soluble ammonio complexions. The precipitated material is removed, dried and treated with carbon tetrachloride at an elevated temperature of about 500 to 600 deg C to form a vapor mixture of UCl/ sub 4/, UCl/sub 5/, FeCl/sub 3/, and CrCl/sub 4/. The UCl/sub 4/ is separated from this vapor mixture by selective fractional condensation at a temperature of about 500 to 400 deg C.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {3}
}