IMPROVED PROCESS OF PLUTONIUM CARRIER PRECIPITATION

Patent · Tue Jun 30 04:00:00 EDT 1959

OSTI ID:4232376

Faris, B F

This patent relates to an improvement in the bismuth phosphate process for separating and recovering plutonium from neutron irradiated uranium, resulting in improved decontamination even without the use of scavenging precipitates in the by-product precipitation step and subsequently more complete recovery of the plutonium in the product precipitation step. This improvement is achieved by addition of fluomolybdic acid, or a water soluble fluomolybdate, such as the ammonium, sodium, or potassium salt thereof, to the aqueous nitric acid solution containing tetravalent plutonium ions and contaminating fission products, so as to establish a fluomolybdate ion concentration of about 0.05 M. The solution is then treated to form the bismuth phosphate plutonium carrying precipitate.

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-13-022167
• Assignee: U.S. Atomic Energy Commission
• Patent Number(s): US 2892676
• OSTI ID: 4232376
• Country of Publication: United States
• Language: English

Related Subjects

AMMONIUM COMPOUNDS
BISMUTH PHOSPHATES
CARRIERS
CHEMICAL REACTIONS
CHEMISTRY
COMPOUNDS
DECONTAMINATION
FISSION PRODUCTS
FUELS
IONS
IRRADIATION
MINERAL ACIDS
MOLYBDENUM FLUORIDES
NEUTRON BEAMS
NITRIC ACID
PATENT
PERFORMANCE
PLUTONIUM
PLUTONIUM COMPOUNDS
POTASSIUM COMPOUNDS
PRECIPITATION
QUANTITY RATIO
RECOVERY
REPROCESSING
SALTS
SEPARATION PROCESSES
SODIUM COMPOUNDS
SOLUBILITY
SOLUTIONS
URANIUM
WATER