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Title: PLUTONIUM PURIFICATION PROCESS EMPLOYING THORIUM PYROPHOSPHATE CARRIER

Abstract

The separation and purification of plutonium from the radioactive elements of lower atomic weight is described. The process of this invention comprises forming a 0.5 to 2 M aqueous acidffc solution containing plutonium fons in the tetravalent state and elements with which it is normally contaminated in neutron irradiated uranium, treating the solution with a double thorium compound and a soluble pyrophosphate compound (Na/sub 4/P/sub 2/O/sub 7/) whereby a carrier precipitate of thorium A method is presented of reducing neptunium and - trite is advantageous since it destroys any hydrazine f so that they can be removed from solutions in which they are contained is described. In the carrier precipitation process for the separation of plutonium from uranium and fission products including zirconium and columbium, the precipitated blsmuth phosphate carries some zirconium, columbium, and uranium impurities. According to the invention such impurities can be complexed and removed by dissolving the contaminated carrier precipitate in 10M nitric acid, followed by addition of fluosilicic acid to about 1M, diluting the solution to about 1M in nitric acid, and then adding phosphoric acid to re-precipitate bismuth phosphate carrying plutonium.

Inventors:
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4228906
Patent Number(s):
US 2884305
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-13-022162
NSA Number:
NSA-13-022162
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; ACIDITY; ACIDS; AMINES; ATOMS; CARRIERS; CHEMICAL REACTIONS; CHEMICALS; HYDROXIDES; HYDROXYLAMINE; IMPURITIES; IONS; PATENT; PHOSPHATES; PLUTONIUM; PLUTONIUM COMPOUNDS; PYROPHOSPHATES; QUANTITY RATIO; RADIOISOTOPES; RECOVERY; REDUCTION; REFINING; SEPARATION PROCESSES; SODIUM PHOSPHATES; SOLUTIONS; THORIUM COMPOUNDS; THORIUM PHOSPHATES; WATER; WEIGHT

Citation Formats

King, E.L. PLUTONIUM PURIFICATION PROCESS EMPLOYING THORIUM PYROPHOSPHATE CARRIER. United States: N. p., 1959. Web.
King, E.L. PLUTONIUM PURIFICATION PROCESS EMPLOYING THORIUM PYROPHOSPHATE CARRIER. United States.
King, E.L. Tue . "PLUTONIUM PURIFICATION PROCESS EMPLOYING THORIUM PYROPHOSPHATE CARRIER". United States. doi:.
@article{osti_4228906,
title = {PLUTONIUM PURIFICATION PROCESS EMPLOYING THORIUM PYROPHOSPHATE CARRIER},
author = {King, E.L.},
abstractNote = {The separation and purification of plutonium from the radioactive elements of lower atomic weight is described. The process of this invention comprises forming a 0.5 to 2 M aqueous acidffc solution containing plutonium fons in the tetravalent state and elements with which it is normally contaminated in neutron irradiated uranium, treating the solution with a double thorium compound and a soluble pyrophosphate compound (Na/sub 4/P/sub 2/O/sub 7/) whereby a carrier precipitate of thorium A method is presented of reducing neptunium and - trite is advantageous since it destroys any hydrazine f so that they can be removed from solutions in which they are contained is described. In the carrier precipitation process for the separation of plutonium from uranium and fission products including zirconium and columbium, the precipitated blsmuth phosphate carries some zirconium, columbium, and uranium impurities. According to the invention such impurities can be complexed and removed by dissolving the contaminated carrier precipitate in 10M nitric acid, followed by addition of fluosilicic acid to about 1M, diluting the solution to about 1M in nitric acid, and then adding phosphoric acid to re-precipitate bismuth phosphate carrying plutonium.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Apr 28 00:00:00 EDT 1959},
month = {Tue Apr 28 00:00:00 EDT 1959}
}