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

Abstract

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.

Inventors:
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4241793
Patent Number(s):
2877090
Assignee:
U.S. Atomic Energy commission DTIE; NSA-13-015189
NSA Number:
NSA-13-015189
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; BISMUTH PHOSPHATES; BORON; CARRIERS; CHEMICAL REACTIONS; 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

Citation Formats

Finzel, T.G. PROCESS USING BISMUTH PHOSPHATE AS A CARRIER PRECIPITATE FOR FISSION PRODUCTS AND PLUTONIUM VALUES. United States: N. p., 1959. Web.
Finzel, T.G. PROCESS USING BISMUTH PHOSPHATE AS A CARRIER PRECIPITATE FOR FISSION PRODUCTS AND PLUTONIUM VALUES. United States.
Finzel, T.G. Tue . "PROCESS USING BISMUTH PHOSPHATE AS A CARRIER PRECIPITATE FOR FISSION PRODUCTS AND PLUTONIUM VALUES". United States.
@article{osti_4241793,
title = {PROCESS USING BISMUTH PHOSPHATE AS A CARRIER PRECIPITATE FOR FISSION PRODUCTS AND PLUTONIUM VALUES},
author = {Finzel, T.G.},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {3}
}