Actions for AN INVESTIGATION OF DISPERSION HARDENING IN THE URANIUM-URANIUM DIOXIDE SYSTEM-RESEARCH IN PROGRESS

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AN INVESTIGATION OF DISPERSION HARDENING IN THE URANIUM-URANIUM DIOXIDE SYSTEM-RESEARCH IN PROGRESS

Author
Arbiter, W.
Published
United States : [publisher not identified], 1960.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1960.
Physical Description
microopaque : positive ; 8 x 13 cm

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Summary
Metallic U is a desirable fuel material for both fast and thermal reactors. However, at low temperatures its anisotropy can result in growth under irradiation with little or no decrease in density, while at temperatures where this effect diminishes (900 to 1000 deg F) other destructive mechanisms are enccuntered. The U increases in volume due to fission gas bubble formation and an inability of the metal to resist the stresses thus imposed. In a study to aileviate these limitations without detriment to neutron economy, a study of dispersion hardening in the U-- U0/sub 2/ system was undertsken. The results of an initial study showed that substantial improvement in both thermal cycling stability and transverse bend strength at elevated temperature are achieved in dispersion-hardened unalloyed U. Further work is in progress in which oxide content and spacing will be controlled, and fabrication procedures studied, in order that optimum structures for the thermal and radiation stability can be achieved ultimately. (auth)
Report Numbers
TID-13339
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: AT(30-1)-2303
NSA number: NSA-15-026521
OSTI Identifier 4003741
Research organization: Nuclear Development Corp. of America, White Plains, N.Y.
View MARC record | catkey: 42249339