Metal fuel test program in the Fast Flux Test Facility
Conference
·
OSTI ID:10116027
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
- Country of Publication:
- United States
- Language:
- English
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· Transactions of the American Nuclear Society; (United States)
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
BURNUP
COST
FABRICATION
FFTF REACTOR
FUEL ELEMENTS
IRRADIATION
MIXED OXIDE FUELS
NUCLEAR FUELS
PERFORMANCE TESTING
POWER REACTORS
BREEDING
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
210500
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
BURNUP
COST
FABRICATION
FFTF REACTOR
FUEL ELEMENTS
IRRADIATION
MIXED OXIDE FUELS
NUCLEAR FUELS
PERFORMANCE TESTING
POWER REACTORS
BREEDING
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS