U-Si and U-Si-Al dispersion fuel alloy development for research and test reactors

Journal Article · Thu Sep 01 04:00:00 EDT 1983 · Nucl. Technol.; (United States)

OSTI ID:6362724

Domagala, R F; Thresh, H R; Wiencek, T C

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/sup 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, Argonne, IL
• OSTI ID: 6362724
• 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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BURNUP
CHALCOGENIDES
DISPERSION NUCLEAR FUELS
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FUEL ELEMENTS
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ISOTOPE ENRICHED MATERIALS
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MINUTES LIVING RADIOISOTOPES
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NUCLEAR MATERIALS DIVERSION
NUCLEI
ORR REACTOR
OXIDES
OXYGEN COMPOUNDS
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REACTORS
SILICIDES
SILICON ALLOYS
SILICON COMPOUNDS
SLIGHTLY ENRICHED URANIUM
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URANIUM
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US AEC
US DOE
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