(U,Zr)C-graphite fuel for TREAT converter studies
Journal Article
·
· Nucl. Technol., v. 28, no. 1, pp. 23-30
OSTI ID:4097157
Improved test facilities are required for safety studies of liquid-metal fast breeder reactor (LMFBR) fuel bundles. The objectives for such a test facility can be obtained by installing a converter section in the central region of the Transient Reactor Test Facility (TREAT) core to provide a hardened neutron spectrum around the test section containing the large cluster of LMFBR fuel pins. The expertise gained at Los Alamos Scientific Laboratory in the Rover fuel element development program was extended to fabricate (U,Zr)C-graphite composite fuel rods for scoping studies of candidate fuels. Selected properties determined for the carbide-graphite composite fuel rods provided for the first scoping test indicate that they are definitely a candidate fuel for a TREAT converter. (auth)
- Research Organization:
- Los Alamos Scientific Lab., NM
- NSA Number:
- NSA-33-019508
- OSTI ID:
- 4097157
- Journal Information:
- Nucl. Technol., v. 28, no. 1, pp. 23-30, Journal Name: Nucl. Technol., v. 28, no. 1, pp. 23-30; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
*LMFBR TYPE REACTORS-- TEST FACILITIES
*TREAT REACTOR-- FUEL ELEMENTS
220600* --Nuclear Reactor Technology--Research
Test & Experimental Reactors
FUEL ELEMENT CLUSTERS
GRAPHITE
N77600* --Reactors--Research
Test
Experimental
Zero-power & Training Reactors
& Subcritical Assemblies
REACTOR SAFETY
TRANSIENTS
URANIUM CARBIDES
ZIRCONIUM CARBIDES
*TREAT REACTOR-- FUEL ELEMENTS
220600* --Nuclear Reactor Technology--Research
Test & Experimental Reactors
FUEL ELEMENT CLUSTERS
GRAPHITE
N77600* --Reactors--Research
Test
Experimental
Zero-power & Training Reactors
& Subcritical Assemblies
REACTOR SAFETY
TRANSIENTS
URANIUM CARBIDES
ZIRCONIUM CARBIDES