METHOD FOR DECONTAMINATION OF REACTOR SOLUTIONS

Patent · Fri May 01 00:00:00 EDT 1959

OSTI ID:4221149

Maraman, W J; Baxman, H R; Baker, R D

A process for U recovery from phosphate fuel solutions is described. To fuel solution drawn from the reactor is added Fe(NO/sub 3/)/sub 3/ which destroys the U complex and forms ferric phosphate complex. The UO/sub 2/(NO/sub 3/)/sub 2/ formed is extracted into TBP-kerosene in a countercurrent column. The TBP contalning UO/sub 2/(NO/sub 3/)/sub 2/ is further purified by an aqueous Al(NO/ sub 3/)/sub 3/ scrub solution. The pregnant solution then goes to an H/sub 3/PO/ sub 4/ stripping and kerosene washing column. The H/sub 3/PO/sub 4/--uranyl phosphate solution is separated at the bottom and boiled to remove HNO/sub 3/ then diluted to fuel solution make-up strength. (T.R.H.)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-13-020999
• Assignee: U.S. Atomic Energy Commission
• Patent Number(s): US 2885260
• OSTI ID: 4221149
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-59
• Country of Publication: United States
• Language: English

Related Subjects

CHEMISTRY
ACIDITY
ALUMINUM NITRATES
BOILING
BUTYL PHOSPHATES
COUNTER CURRENT
DECOMPOSITION
DECONTAMINATION
EXTRACTION COLUMNS
FUELS
HYDROCARBONS
IRON NITRATES
KEROSENE
MIXING
NITRIC ACID
PETROLEUM
QUANTITY RATIO
RECOVERY
SEPARATION PROCESSES
SOLUTIONS
SOLVENT EXTRACTION
URANIUM
URANIUM COMPLEXES
URANIUM PHOSPHATES
URANYL NITRATES