High burnup performance of an advanced oxide fuel assembly in FFTF (Fast Flux Test Facility) with ferritic/martensitic materials
An advanced oxide fuel assembly with ferritic/martensitic materials has successfully completed its sixth cycle of irradiation in the FFTF, reaching a peak pellet burnup greater than 100 MWd/KgM and a peak fast fluence greater than 15 x 10SS n/cmS. The cladding, wire-wrap, and duct material for the ACO-1 test assembly is the ferritic/martensitic alloy, HT9, which was chosen for use in long-lifetime fuel assemblies because of its good nominal temperature creep strength and low swelling rate. Valuable experience on the performance of HT9 materials has been gained from this test, advancing our quest for long-lifetime fuel. Pertinent data, obtained from the ACO-1 test assembly, will support the irradiation of the Core Demonstration Experiment in FFTF.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6434230
- Report Number(s):
- HEDL-SA-3497; CONF-860931-24; ON: DE87010719
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ALLOYS
BURNUP
CARBON ADDITIONS
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FERRITE
FFTF REACTOR
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL PINS
FUEL-CLADDING INTERACTIONS
IRON ALLOYS
IRRADIATION
LIQUID METAL COOLED REACTORS
MARTENSITE
PERFORMANCE
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STRESS ANALYSIS
TEST REACTORS