Metal fuel test program in the FFTF

Conference · Wed Jan 01 04:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6982445

Pitner, A L; Baker, R B ^[1]

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1. Westinghouse Hanford Co., Richland, WA (United States)

Aggressive irradiation testing of metal-fuel assemblies containing long fuel pins has been successfully conducted in the Fast Flux Test Facility (FFTF), and no cladding breaches have been observed up to burnups approaching 150 MWd/kg M. In-reactor measurements of performance indicate good behavior. Postirradiation examinations (under way and future) will characterize fuel and sodium bond performance, cladding strain behavior, fuel/cladding mechanical interaction, and other irradiation performance attributes. With continued FFTF operation, ultimate burnup capabilities and the breach mode in long metal-fuel pins will be determined. These results support the design development of the IFR fuel system, the design of the ALMR, and provide a potential advanced driver fuel design for the FFTF.

• OSTI ID: 6982445
• Report Number(s): CONF-921102--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
BURNUP
DESIGN
ENERGY SOURCES
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENTS
FUEL PINS
FUELS
IFR REACTOR
IRRADIATION
LIQUID FUELS
LIQUID METAL COOLED REACTORS
LIQUID METAL FUELS
MATERIALS
MECHANICAL PROPERTIES
NUCLEAR FUELS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TESTING
ZERO POWER REACTORS