Performance of titanium stabilized D9 cladding and ducts
Conference
·
OSTI ID:6555724
A series of mixed oxide UO/sub 2/-PuO/sub 2/ Liquid Metal Reactor (LMR) Fuel assemblies using D9 alloy cladding and/or ducts have been irradiated to high exposure in the Fast Flux Test Facility (FFTF) with very encouraging results. D9 is a titanium modified variant of 316 stainless steel. The highest burnup attained for 316 stainless steel clad driver fuel pins in FFTF has been achieved in an assembly with a cold worked D9 duct while assemblies which simultaneously utilize both D9 ducts and D9 clad pins have achieved burnups as high as 155 MWd/kgM with a corresponding fast fluence of 25 x 10/sup 22/ n/cm/sup 2/. The cold worked D9 ducts demonstrated less length increase and less dilation than their Cold Worked 316 SS counterparts. The D9 pins also showed less length and diameter increase than comparable 316 SS pins with less evidence of deformation due to interference between the pin bundle and the duct. Corrosion behavior at the inner and outer surface of the D9 cladding has proved to be very similar to that of 316 stainless steel.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6555724
- Report Number(s):
- HEDL-SA-3452-FP; CONF-860931-17; ON: DE87007439
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE COMPOUNDS
ALLOY-D-9
ALLOYS
BURNUP
CHALCOGENIDES
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION
CORROSION RESISTANT ALLOYS
DATA
DEFORMATION
DUCTS
ELEMENTS
EPITHERMAL REACTORS
EXPERIMENTAL DATA
FAST REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENTS
FUELS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LIQUID METAL COOLED REACTORS
MATERIALS
METALS
MIXED OXIDE FUELS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NICKEL STEELS
NICKEL-CHROMIUM STEELS
NUMERICAL DATA
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TEST REACTORS
TITANIUM
TRANSITION ELEMENTS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDE COMPOUNDS
ALLOY-D-9
ALLOYS
BURNUP
CHALCOGENIDES
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION
CORROSION RESISTANT ALLOYS
DATA
DEFORMATION
DUCTS
ELEMENTS
EPITHERMAL REACTORS
EXPERIMENTAL DATA
FAST REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL CANS
FUEL ELEMENTS
FUELS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
LIQUID METAL COOLED REACTORS
MATERIALS
METALS
MIXED OXIDE FUELS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NICKEL STEELS
NICKEL-CHROMIUM STEELS
NUMERICAL DATA
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TEST REACTORS
TITANIUM
TRANSITION ELEMENTS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES