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 (United States)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6434230
- Report Number(s):
- HEDL-SA-3497; CONF-860931-24; ON: DE87010719
- Resource Relation:
- Conference: International conference on reliable fuels for liquid metal reactors, Tucson, AZ, USA, 7 Sep 1986; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
BURNUP
FABRICATION
FERRITE
FUEL PINS
FUEL-CLADDING INTERACTIONS
IRRADIATION
MARTENSITE
PERFORMANCE
PHYSICAL RADIATION EFFECTS
STRESS ANALYSIS
ALLOYS
CARBON ADDITIONS
EPITHERMAL REACTORS
FAST REACTORS
FUEL ELEMENTS
IRON ALLOYS
LIQUID METAL COOLED REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
220300 - Nuclear Reactor Technology- Fuel Elements