Fabrication of high-uranium-loaded U3O8-Al developmental fuel plates
Conference
·
OSTI ID:7065341
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)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7065341
- Report Number(s):
- CONF-801144--2
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE ALLOYS
ALLOYS
ALUMINIUM ALLOYS
CHEMICAL COMPOSITION
FABRICATION
FUEL ELEMENTS
FUEL PLATES
MECHANICAL PROPERTIES
OPTIMIZATION
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SPECIFICATIONS
URANIUM ALLOYS
URANIUM BASE ALLOYS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE ALLOYS
ALLOYS
ALUMINIUM ALLOYS
CHEMICAL COMPOSITION
FABRICATION
FUEL ELEMENTS
FUEL PLATES
MECHANICAL PROPERTIES
OPTIMIZATION
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SPECIFICATIONS
URANIUM ALLOYS
URANIUM BASE ALLOYS