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Thermal compatibility studies of unirradiated uranium silicide dispersed in aluminum

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:5967359

Powder metallurgy dispersions of uranium silicides in an aluminum matrix have been developed by the international Reduced Enrichment for Research and Test Reactors program as a new generation of proliferation-resistant fuels. A major issue of concern is the compatibility of the fuel with the matrix material and the dimensional stability of this fuel type. A total of 45 miniplate-type fuel plates were annealed at 400/sup 0/C for up to 1981 h. A data base for the thermal compatibility of unirradiated uranium silicide dispersed in aluminum was established. No tested modification of a standard fuel plate showed any significant reduction in plate swelling. The cause of thermal growth of silicide fuel plates was determined to be a two-step process: (a) the reaction of the uranium silicide with aluminum to form U(AlSi)/sub 3/ and (b) the release of hydrogen and subsequent creep and pillowing of the fuel plate.

Research Organization:
Argonne National Laboratory, Materials Science and Technology Division, Argonne, IL
OSTI ID:
5967359
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 71:3; ISSN NUTYB
Country of Publication:
United States
Language:
English