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Title: DISSOLUTION OF LANTHANUM FLUORIDE PRECIPITATES

Abstract

A plutonium separatory ore concentration procedure involving the use of a fluoride type of carrier is presented. An improvement is given in the derivation step in the process for plutonium recovery by carrier precipitation of plutonium values from solution with a lanthanum fluoride carrier precipitate and subsequent derivation from the resulting plutonium bearing carrier precipitate of an aqueous acidic plutonium-containing solution. The carrier precipitate is contacted with a concentrated aqueous solution of potassium carbonate to effect dissolution therein of at least a part of the precipitate, including the plutonium values. Any remaining precipitate is separated from the resulting solution and dissolves in an aqueous solution containing at least 20% by weight of potassium carbonate. The reacting solutions are combined, and an alkali metal hydroxide added to a concentration of at least 2N to precipitate lanthanum hydroxide concomitantly carrying plutonium values.

Inventors:
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4187134
Patent Number(s):
US 2912303
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-14-007472
NSA Number:
NSA-14-007472
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; ALKALI METALS; HYDROXIDES; LANTHANUM FLUORIDES; ORE PROCESSING; PLUTONIUM; POTASSIUM CARBONATES; PRECIPITATION; RECOVERY; SOLUBILITY; SOLUTIONS; WATER

Citation Formats

Fries, B.A. DISSOLUTION OF LANTHANUM FLUORIDE PRECIPITATES. United States: N. p., 1959. Web.
Fries, B.A. DISSOLUTION OF LANTHANUM FLUORIDE PRECIPITATES. United States.
Fries, B.A. Tue . "DISSOLUTION OF LANTHANUM FLUORIDE PRECIPITATES". United States.
@article{osti_4187134,
title = {DISSOLUTION OF LANTHANUM FLUORIDE PRECIPITATES},
author = {Fries, B.A.},
abstractNote = {A plutonium separatory ore concentration procedure involving the use of a fluoride type of carrier is presented. An improvement is given in the derivation step in the process for plutonium recovery by carrier precipitation of plutonium values from solution with a lanthanum fluoride carrier precipitate and subsequent derivation from the resulting plutonium bearing carrier precipitate of an aqueous acidic plutonium-containing solution. The carrier precipitate is contacted with a concentrated aqueous solution of potassium carbonate to effect dissolution therein of at least a part of the precipitate, including the plutonium values. Any remaining precipitate is separated from the resulting solution and dissolves in an aqueous solution containing at least 20% by weight of potassium carbonate. The reacting solutions are combined, and an alkali metal hydroxide added to a concentration of at least 2N to precipitate lanthanum hydroxide concomitantly carrying plutonium values.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {11}
}