PROCESS OF DISSOLVING ZIRCONIUM ALLOYS
Abstract
A process is described for dissolving binary zirconium-uranium alloys where the uranium content is about 2%. In prior dissolution procedures for these alloys, an oxidizing agent was added to prevent the precipitation of uranium tetrafluoride. In the present method complete dissolution is accomplished without the use of the oxidizing agent by using only the stoichiometric amount or slight excess of HF required by the zirconium. The concentration of the acid may range from 2M to 10M and the dissolution is advatageously carried out at a temperature of 80 deg C.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4304923
- Patent Number(s):
- 2820692
- Assignee:
- U.S. Atomic Energy Commission
- Patent Classifications (CPCs):
-
C - CHEMISTRY C22 - METALLURGY C22B - PRODUCTION AND REFINING OF METALS
- NSA Number:
- NSA-12-007004
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-58
- Country of Publication:
- United States
- Language:
- English
- Subject:
- PATENTS; ENRICHMENT; OXIDATION; PATENT; PRECIPITATION; SOLVENTS; URANIUM; URANIUM TETRAFLUORIDE; ZIRCONIUM ALLOYS
Citation Formats
Shor, R S, and Vogler, S. PROCESS OF DISSOLVING ZIRCONIUM ALLOYS. United States: N. p., 1958.
Web.
Shor, R S, & Vogler, S. PROCESS OF DISSOLVING ZIRCONIUM ALLOYS. United States.
Shor, R S, and Vogler, S. Tue .
"PROCESS OF DISSOLVING ZIRCONIUM ALLOYS". United States.
@article{osti_4304923,
title = {PROCESS OF DISSOLVING ZIRCONIUM ALLOYS},
author = {Shor, R S and Vogler, S},
abstractNote = {A process is described for dissolving binary zirconium-uranium alloys where the uranium content is about 2%. In prior dissolution procedures for these alloys, an oxidizing agent was added to prevent the precipitation of uranium tetrafluoride. In the present method complete dissolution is accomplished without the use of the oxidizing agent by using only the stoichiometric amount or slight excess of HF required by the zirconium. The concentration of the acid may range from 2M to 10M and the dissolution is advatageously carried out at a temperature of 80 deg C.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1958},
month = {1}
}
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