Performance of HT9 clad metallic fuel at high temperature
Steady-state testing of HT9 clad metallic fuel at high temperatures was initiated in EBR-II in November of 1987. At that time U-10 wt. % Zr fuel clad with the low-swelling ferritic/martensitic alloy HT9 was being considered as driver fuel options for both EBR-II and FFTF. The objective of the X447 test described here was to determine the lifetime of HT9 cladding when operated with metallic fuel at beginning of life inside wall temperatures approaching [approximately]660[degree]C. Though stress-temperature design limits for HT9 preclude its use for high burnup applications under these conditions due to excessive thermal creep, the X447 test was carried out to obtain data on high temperature breach phenomena involving metallic fuel since little data existed in that area.
- Research Organization:
- Argonne National Lab., Idaho Falls, ID (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6983330
- Report Number(s):
- ANL/FE/CP-76393; CONF-921102--50; ON: DE93004852
- Country of Publication:
- United States
- Language:
- English
Similar Records
Performance of HT9 clad metallic fuel at high temperature
Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins
Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins
Conference
·
Mon Nov 30 23:00:00 EST 1992
·
OSTI ID:10117065
Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins
Journal Article
·
Sun May 01 00:00:00 EDT 2016
· Journal of Nuclear Materials
·
OSTI ID:1344053
Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins
Journal Article
·
Fri Feb 26 19:00:00 EST 2016
· Journal of Nuclear Materials
·
OSTI ID:1357497
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ALLOY-HT-9
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CLADDING
CORROSION RESISTANT ALLOYS
DEPOSITION
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL ELEMENTS
FUELS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MARTENSITIC STEELS
MATERIALS
MIXED OXIDE FUELS
MOLYBDEN
MOLYBDENUM ADDITIONS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
STAINLESS STEELS
STEEL-CR12MOV
STEELS
SURFACE COATING
TEMPERATURE RANGE
TEMPERATURE RANGE 0400-1000 K
TEST REACTORS
TESTING
ZIRCONIUM ALLOYS
210500* -- Power Reactors
Breeding
ALLOY-HT-9
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CLADDING
CORROSION RESISTANT ALLOYS
DEPOSITION
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL ELEMENTS
FUELS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MARTENSITIC STEELS
MATERIALS
MIXED OXIDE FUELS
MOLYBDEN
MOLYBDENUM ADDITIONS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
STAINLESS STEELS
STEEL-CR12MOV
STEELS
SURFACE COATING
TEMPERATURE RANGE
TEMPERATURE RANGE 0400-1000 K
TEST REACTORS
TESTING
ZIRCONIUM ALLOYS