Actions for OXIDATION OF ZIRCONIUM-CONTAINING FUELS TO FACILITATE URANIUM RECOVERY

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OXIDATION OF ZIRCONIUM-CONTAINING FUELS TO FACILITATE URANIUM RECOVERY

Author
Wymer, R. G.
Published
United States : [publisher not identified], 1956.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1956.
Physical Description
microopaque : positive ; 8 x 13 cm

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Summary
ABS>Results of this investigation indicated that an oxidation-leaching process for uranium recovery from zirconium-uranium is not practicable. Oxidation of zirconium-uranium alloy specimens was sufficiently rapid that the elements would be completely converted to the oxides in about 6 hr at 1000 deg C. However, uranium recovery in leaching was of the order of 80% in the best cases. Tolerable losses are of the order of 0.05%. Oxidative processing of this type of fuel was therefore abandoned. (auth)
Report Numbers
ORNL-2182(Del.)
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: W-7405-ENG-26
NSA number: NSA-13-007595
OSTI Identifier 4253414
Research organization: Oak Ridge National Lab., Tenn.
View MARC record | catkey: 42231928