METHOD OF SEPARATING URANIUM AND ZIRCONIUM

Patent · Mon May 09 00:00:00 EDT 1960

OSTI ID:4824696

A pyrometallurgical method is described for the separation of uranium and zirconium in irradiated uraniumzirconium fuel alloys or mixtures. The material is reduced to a grain size of 3 mm and contacted with 1 to 10 times its weight of molten aluminum at 800 to 900 deg C. After the corroding action of the aluminum has ceased the mixture is cooled from 670 to 760 deg C and the liquid, consisting of uranium and aluminum, is separated from the ZrAl/sub 3/ precipitates. The treatment can be repeated with the precipitate, but the total weight of aluminum consumed should not exceed 10 times the weight of the initial starting material. (NPO)

• Research Organization: Originating Research Org. not identified
• NSA Number: NSA-15-032256
• OSTI ID: 4824696
• Report Number(s): FR 1233910
• Country of Publication: France
• Language: English

Related Subjects

ALLOYS
ALUMINUM
ALUMINUM COMPOUNDS
CHEMISTRY
CORROSION
FUELS
GRAIN SIZE
LIQUID METALS
LIQUIDS
MELTING
METALLURGY
MIXING
PRECIPITATION
SEPARATION PROCESSES
TEMPERATURE
URANIUM
WEIGHT
ZIRCONIUM
ZIRCONIUM COMPOUNDS