Evaluation of the advanced mixed oxide fuel test FO-2 irradiated in Fast Flux Test Facility
The advanced mixed-oxide (UO/sub 2/-PuO/sub 2/) test assembly, FO-2, irradiated in the Fast Flux Test Facility (FFTF), is undergoing postirradiation examination (PIE). This is one of the first FFTF tests examined that used the advanced ferrite-martensite alloy, HT9, which is highly resistant to irradiation swelling. The FO-2 includes the first annular fueled pins irradiated in FFTF to undergo destructive examination. The FO-2 is a lead assembly for the ongoing FFTF Core Demonstration Experiment (CDE) (Leggett and Omberg 1987) and was designed to evaluate the effects of fuel design variables, such as pellet density, smeared density, and fuel form (annular or solid fuel), on advanced pin performance. The assembly contains a total of 169 fuel pins of twelve different types. The test was irradiated for 312 equivalent full power days (EFPD) in FFTF. It had a peak pin power of 13.7 kW/ft and reached a peak burnup of 65.2 MWd/kgM with a peak fast fluence of 9.9 /times/ 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV). This document discusses the test and its results. 6 refs., 19 figs., 4 tabs.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 6105418
- Report Number(s):
- WHC-SA-0498; CONF-890604-7; ON: DE89013528
- Resource Relation:
- Conference: Annual meeting of the American Nuclear Society, Atlanta, GA, USA, 4 Jun 1989; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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EVALUATION
FUEL CANS
FUEL PELLETS
FUEL PINS
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PERFORMANCE
PLUTONIUM DIOXIDE
POST-IRRADIATION EXAMINATION
RADIATION EFFECTS
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ACTINIDE COMPOUNDS
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FUEL ELEMENTS
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LIQUID METAL COOLED REACTORS
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PELLETS
PHYSICAL PROPERTIES
PLUTONIUM COMPOUNDS
PLUTONIUM OXIDES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
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