Fabrication of high-uranium-loaded U/sub 3/O/sub 8/-Al developmental fuel plates

Technical Report · Sun Nov 30 23:00:00 EST 1980

DOI:https://doi.org/10.2172/7014128· OSTI ID:7014128

Copeland, G L; Martin, M M

A common plate-type fuel for research and test reactors is U/sub 3/O/sub 8/ dispersed in aluminum and clad with an aluminum alloy. There is an impetus to reduce the /sup 235/U 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.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 7014128
• Report Number(s): ORNL/TM-7607
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE COMPOUNDS
ACTINIDES
ALUMINIUM
CHALCOGENIDES
DISPERSION NUCLEAR FUELS
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
FABRICATION
FUEL ELEMENTS
FUEL PLATES
FUELS
ISOTOPE ENRICHED MATERIALS
MATERIALS
MATERIALS TESTING
METALS
MODERATELY ENRICHED URANIUM
NONDESTRUCTIVE TESTING
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
PHYSICAL PROPERTIES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
SOLID FUELS
TESTING
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
URANIUM
URANIUM COMPOUNDS
URANIUM OXIDES
URANIUM OXIDES U3O8