Dimensional changes in FFTF (Fast Flux Test Facility) austenitic cladding and ducts
Conference
·
OSTI ID:6345334
As the standard cladding and duct material for the Fast Flux Test Facility driver fuel, 20% cold-worked 316 stainless steel has provided good service up to a fast fluence of 16 {times} 10{sup 22} n/cm{sup 2} in extreme cases. The titanium-stabilized variant of 316 SS, called D9, has extended the useful life of the austenitic alloys by increasing the incubation fluence necessary for the onset of volumetric swelling. Duct flat-to-flat, length and bow, pin bundle distortion, fuel pin diameter and length, as well as cladding volumetric swelling have been examined for high fluence components representing both alloys. These data emphasize the importance of the swelling process, the superiority of D9, and the interrelation between deformations in the duct, bundle, and individual pins. 8 refs., 10 figs.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 6345334
- Report Number(s):
- WHC-SA-0933; CONF-901101--63; ON: DE91004556
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOY-D-9
ALLOYS
AUSTENITIC STEELS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
DEFORMATION
DUCTS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL CANS
FUEL ELEMENTS
FUEL PINS
HEAT RESIS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NICKEL STEELS
NICKEL-CHROMIUM STEELS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SERVICE LIFE
SODIUM COOLED REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEEL-CR17NI12MO3
STEELS
SWELLING
TEST REACTORS
210500* -- Power Reactors
Breeding
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOY-D-9
ALLOYS
AUSTENITIC STEELS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CORROSION RESISTANT ALLOYS
DEFORMATION
DUCTS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL CANS
FUEL ELEMENTS
FUEL PINS
HEAT RESIS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NICKEL STEELS
NICKEL-CHROMIUM STEELS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SERVICE LIFE
SODIUM COOLED REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEEL-CR17NI12MO3
STEELS
SWELLING
TEST REACTORS