PROCESS USING BISMUTH PHOSPHATE AS A CARRIER PRECIPITATE FOR FISSION PRODUCTS AND PLUTONIUM VALUES

Patent · Mon Mar 09 23:00:00 EST 1959

OSTI ID:4241793

Finzel, T G

A process is described for separating plutonium from fission products carried therewith when plutonium in the reduced oxidation state is removed from a nitric acid solution of irradiated uranium by means of bismuth phosphate as a carrier precipitate. The bismuth phosphate carrier precipitate is dissolved by treatment with nitric acid and the plutonium therein is oxidized to the hexavalent oxidation state by means of potassium dichromate. Separation of the plutonium from the fission products is accomplished by again precipitating bismuth phosphate and removing the precipitate which now carries the fission products and a small percentage of the plutonium present. The amount of plutonium carried in this last step may be minimized by addition of sodium fluoride, so as to make the solution 0.03N in NaF, prior to the oxidation and prccipitation step.

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-13-015189
• Assignee: U.S. Atomic Energy commission
• Patent Number(s): US 2877090
• OSTI ID: 4241793
• Country of Publication: United States
• Language: English

Related Subjects

BISMUTH PHOSPHATES
BORON
CARRIERS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM OXIDES
DIFFUSION
EFFICIENCY
EVAPORATION
EVAPORATION HEAT
FUEL ELEMENTS
IRRADIATION
KNUDSEN EFFUSION
LOSSES
MASS SPECTROMETERS
MIXING
NITRIC ACID
OPERATION
OXIDATION
PATENT
PHASE DIAGRAMS
PLUTONIUM
PLUTONIUM COMPOUNDS
PLUTONIUM NITRATES
POTASSIUM COMPOUNDS
PRECIPITATION
PRESSURE
QUANTITY RATIO
RECOVERY
REDUCTION
REFINING
REPROCESSING
SEPARATION PROCESSES
SODIUM FLUORIDES
SOLUTIONS
THERMODYNAMICS
TITANIUM
TITANIUM BORIDES
URANIUM
URANIUM NITRATES
URANYL NITRATES
WATER