Metal fuel test program in the Fast Flux Test Facility

Conference · Thu Oct 01 00:00:00 EDT 1992

OSTI ID:10116027

Pitner, A L; Baker, R B

This report discusses irradiation testing of metal fuel assemblies in the Fast Flux Test Facility (FFTF) which has demonstrated the viability of this robust fuel design for liquid metal reactor applications. This fuel design provides high burnup capability with reduced fabrication costs relative to standard mixed-oxide FFTF driver fuel assemblies. Development of this fuel design required the establishment of innovative sodium bonding technology as well as special techniques for sodium bond quality verification. Eight metal fuel test assemblies have been irradiated under demanding conditions to burnups as high as 143 MWd/kgM with no indication of pin breach. The unique FFTF instrumentation system has permitted the in situ observation of axial fuel growth in metal fuel assemblies.

• Research Organization: Westinghouse Hanford Co., Richland, WA (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 10116027
• Report Number(s): WHC-SA-1579; CONF-921102-53; ON: DE93004486
• Resource Relation: Conference: Joint American Nuclear Society/European Nuclear Society (ANS/ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future,Chicago, IL (United States),15-20 Nov 1992; Other Information: PBD: Oct 1992
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
FFTF REACTOR
FUEL ELEMENTS
NUCLEAR FUELS
PERFORMANCE TESTING
MIXED OXIDE FUELS
COST
FABRICATION
BURNUP
IRRADIATION
210500
220600
POWER REACTORS
BREEDING
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS