Properties of U sub 3 O sub 8 -aluminum cermet fuel

Technical Report · Thu Mar 01 00:00:00 EST 1990

OSTI ID:6927935

Peacock, H B

Nuclear fuel elements containing U{sub 3}O{sub 8} dispersed in an aluminum matrix have been used in research and test reactors for about 30 years. These elements, sometimes called cermet fuel, are made by powder metallurgical methods (PM) and can accommodate up to approximately 65 wt % uranium in the core. Cermet fuel elements have been fabricated and irradiated at the Savannah River Site (SRS). Irradiation behavior is excellent. Extruded tubes with up to 52 wt % uranium have been successfully irradiated to fission densities of about 1.6 {times} 10{sup 21} fissions per cc of core. Physical, mechanical, and chemical properties of cermet fuels are assembled into a reference document. Results will be used by Argonne National Laboratory to design cermet fuel elements for possible use in the New Production Reactor at SRS. 66 refs., 35 figs., 12 tabs.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (USA)
• Sponsoring Organization: DOE/DP
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 6927935
• Report Number(s): WSRC-RP-89-981-Rev.1; ON: DE90012044
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
URANIUM OXIDES U3O8
CHEMICAL PROPERTIES
MECHANICAL PROPERTIES
PHYSICAL PROPERTIES
ALUMINIUM ALLOYS
CERMETS
IRRADIATION
PROCESSING
SPECIFIC HEAT
THERMAL CONDUCTIVITY
THERMAL EXPANSION
THERMODYNAMIC PROPERTIES
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
COMPOSITE MATERIALS
EXPANSION
MATERIALS
OXIDES
OXYGEN COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
050700* - Nuclear Fuels- Fuels Production & Properties