Thermal compatibility studies of unirradiated uranium silicide dispersed in aluminum
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
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
36 MATERIALS SCIENCE
360603 -- Materials-- Properties
ACTINIDE COMPOUNDS
ANNEALING
COMPATIBILITY
CREEP
DEFORMATION
ELEMENTS
EXPANSION
FUEL ELEMENTS
FUEL PLATES
GAS PRODUCTION RATES
HEAT TREATMENTS
HYDROGEN
MATERIALS
MATERIALS TESTING
MATRIX MATERIALS
MECHANICAL PROPERTIES
METALLURGY
NONMETALS
POWDER METALLURGY
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SILICIDES
SILICON COMPOUNDS
SWELLING
TEMPERATURE EFFECTS
TESTING
THERMAL EXPANSION
URANIUM COMPOUNDS
URANIUM SILICIDES