PROPERTIES OF CERAMIC AND CERMET FUELS FOR SODIUM GRAPHITE REACTORS
Nuclear materials of interest as potential reactor fuels for sodium graphite reactors are reviewed to select those which appear most feasible for high-temperature, longburnup application. Fuel propenties such as melting point, thermal neutron absorption cross section, uranium content, chemical and physical propenties, and fabrication details are presented. Other factors such as expected bunnup capabilities, required enrichments, and conversion ratios were compared. A program is currently in progress to evaluate promising nuclear fuels. Fuel materials under consideration include the uranium compounds: uranium dioxide, uranium monocarbide, borides, sulfides, sluminide, nitrides, silicides, and phosphides. Various cermets are under consideration. These include dispersions of uranium compounds in matrices of uranium, uranium alloys, thorium, and thorinm alloys. Included among the uranium alloy matrices are binary and tennary combinations of uranium with niobium, molybdenum, and zirconium. (auth)
- Research Organization:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- DOE Contract Number:
- AT-11-1-GEN-8
- NSA Number:
- NSA-14-018165
- OSTI ID:
- 4175587
- Report Number(s):
- NAA-SR-3880
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ABSORPTION
ALUMINUM ALLOYS
BEARINGS
BURNUP
CERAMICS
CERMETS
CHEMICAL REACTIONS
CONVECTION
CROSS SECTIONS
DISPERSIONS
FABRICATION
FISSIONABLE MATERIALS
FUELS
GRAPHITE
HIGH TEMPERATURE
MELTING POINTS
MOLYBDENUM ALLOYS
NIOBIUM ALLOYS
PHOSPHIDES
REACTORS
SODIUM
THERMAL NEUTRONS
THORIUM
THORIUM ALLOYS
URANIUM
URANIUM ALLOYS
URANIUM BORIDES
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM NITRIDES
URANIUM SILICIDES
URANIUM SULFIDES
USES
ZIRCONIUM ALLOYS