Published December 1980
| Version v1
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Fabrication of high-uranium-loaded U3O8-Al developmental fuel plates
Description
A common plate-type fuel for research and test reactors is U3O8 dispersed in aluminum and clad with an aluminum alloy. There is an impetus to reduce the 235U enrichment from above 90% to below 20% for these fuels to lessen the risk of diversion of the uranium for nonpeaceful uses. Thus, the uranium content of the fuel plates has to be increased to maintain the performance of the reactors. This paper describes work at ORNL to determine the maximal uranium loading for these fuels that can be fabricated with commercially proven materials and techniques and that can be expected to perform satisfactorily in service
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
12596718.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 19 p.
- Report number
- ORNL/TM--7607
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12596718
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALUMINIUM; DISPERSION NUCLEAR FUELS; FABRICATION; FUEL PLATES; MODERATELY ENRICHED URANIUM; NONDESTRUCTIVE TESTING; RESEARCH AND TEST REACTORS; THERMAL CONDUCTIVITY; U3O8
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CHALCOGENIDES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM; FUEL ELEMENTS; FUELS; ISOTOPE ENRICHED MATERIALS; MATERIALS TESTING; METALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS; TESTING; THERMODYNAMIC PROPERTIES; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES