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Title: DISSOLUTION OF URANIUM FUELS BY MONOOR DIFLUOROPHOSPHORIC ACID

Abstract

A method of dissolving and separating uranium from a uranium matrix fuel element by dissolving the uraniumcontaining matrix in monofluorophosphoric acid and/or difluorophosphoric acid at temperatures ranging from 150 to 275 un. Concent 85% C, thereafter neutralizing the solution to precipitate uranium solids, and converting the solids to uranium hexafluoride by treatment with a halogen trifluoride is presented. (AEC)

Inventors:
; ;
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4714553
Patent Number(s):
3088800
Assignee:
U.S. Atomic Energy Commission
Patent Classifications (CPCs):
C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01G - COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
NSA Number:
NSA-17-021804
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-63
Country of Publication:
United States
Language:
English
Subject:
CHEMISTRY; ACIDITY; BURNUP; CHEMICAL REACTIONS; FLUORINE COMPOUNDS; FUEL ELEMENTS; PHOSPHORIC ACID; PRECIPITATION; REPROCESSING; SEPARATION PROCESSES; SOLUTIONS; TEMPERATURE; URANIUM HEXAFLUORIDE

Citation Formats

Johnson, R, Horn, F L, and Strickland, G. DISSOLUTION OF URANIUM FUELS BY MONOOR DIFLUOROPHOSPHORIC ACID. United States: N. p., 1963. Web.
Johnson, R, Horn, F L, & Strickland, G. DISSOLUTION OF URANIUM FUELS BY MONOOR DIFLUOROPHOSPHORIC ACID. United States.
Johnson, R, Horn, F L, and Strickland, G. Wed . "DISSOLUTION OF URANIUM FUELS BY MONOOR DIFLUOROPHOSPHORIC ACID". United States.
@article{osti_4714553,
title = {DISSOLUTION OF URANIUM FUELS BY MONOOR DIFLUOROPHOSPHORIC ACID},
author = {Johnson, R and Horn, F L and Strickland, G},
abstractNote = {A method of dissolving and separating uranium from a uranium matrix fuel element by dissolving the uraniumcontaining matrix in monofluorophosphoric acid and/or difluorophosphoric acid at temperatures ranging from 150 to 275 un. Concent 85% C, thereafter neutralizing the solution to precipitate uranium solids, and converting the solids to uranium hexafluoride by treatment with a halogen trifluoride is presented. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1963},
month = {5}
}

Patent:
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