U-Si and U-Si-Al dispersion, fuel alloy development for research and test reactors
As part of the National Reduced Enrichment Research and Test Reactor Program, Argonne National Laboratory (ANL) is engaged in a fuel alloy development project. The reduction of the /sup 235/U enrichment from above 90% to below 20% for such fuels would lessen the risk of diversion of the fuel for nonpeaceful uses. Fuel alloy powder prepared with low-enrichment uranium (<20%/sup 235/U) is dispersed in an aluminum matrix, and metallurgically roll bonded within a cladding of 6061 aluminum alloy. Miniplates with up to 55 vol% fuel alloy (up to 7.0 g total U/cm/sup 3/) have been successfully fabricated. Fifty-five of these plates have been or are being irradiated in the Oak Ridge Research Reactor. Three fuel alloys have been used in the ANL miniplates: U/sub 3/Si(U + 4 wt% Si), U/sub 3/Si/sub 2/(U + 7.5 wt% Si), and ''U/sub 3/SiAl'' (U + 3.5 wt% Si + 1.5 wt% Al). All are candidates for permitting higher fuel loadings and thus lower enrichments of /sup 235/U than would be possible with either UAl/SUB x/ or U/sub 3/O/sub 8/, the current fuels for plate-type elements. A target loading of up to 7.0 g U/cm/sub 3/ in the fuel zone was selected. To date the fabrication and irradiation results with the silicide fuels have been encouraging, and as an adjunct to the development effort, ANL is engaged in the early stages of technology transfer with commercial fabricators of fuel elements for research reactors. Continuing effort also involves the development of a technology for full-sized plate fabrication and the irradiation of miniplates to a burnup of about 90% /sup 235/U depletion.
- Research Organization:
- Argonne National Laboratory, Materials Science and Technology Division, 9700 South Cass Avenue, Argonne, Illinois 60439
- OSTI ID:
- 5492328
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 62:3; 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
ACTINIDE ALLOYS
ACTINIDES
ALLOY NUCLEAR FUELS
ALLOYS
ALUMINIUM ALLOYS
ANL
DESIGN
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
FABRICATION
FUEL ELEMENTS
FUEL PLATES
FUELS
HIGHLY ENRICHED URANIUM
ISOTOPE ENRICHED MATERIALS
MATERIALS
METALS
NATIONAL ORGANIZATIONS
NUCLEAR FUELS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH PROGRAMS
SILICON ALLOYS
SLIGHTLY ENRICHED URANIUM
SOLID FUELS
TECHNOLOGY TRANSFER
TESTING
URANIUM
URANIUM ALLOYS
US AEC
US DOE
US ERDA
US ORGANIZATIONS