Experience on fuel and structural materials development in the USA
The United States has conducted extensive LMFBR fuel and structural materials development programs since the mid-1960's. Fuels and materials irradiation tests conducted in EBR-II formed the basis for evaluating the expected performance of FFTF fuel and identified candidate fuels and materials for further full-scale testing in FFTF. The performance of FFTF fuel through the first three years of reactor operation (700 EFPD) has been outstanding. Peak fuel burnup has been limited by swelling of the cold worked AISI 316 austenitic stainless steel ducts rather than by fuel pin behavior. Standard FFTF driver fuel is currently being irradiated routinely to a peak burnup of approximately 100,000 MWd/MTM. Fuel assemblies fabricated with Alloy D9 (titanium modified austenitic stainless steel) cladding and ducts will complete irradiation to an exposure of 155,000 MWd/MTM by the end of 1985, and a large-scale FFTF test program to demonstrate the extended performance capability of fuel assemblies fabricated with the ferritic/martensitic stainless steel alloy HT9 is in progress. Current information indicates that mixed oxide fuel clad with alloy HT9, a modified D9 alloy or dispersion strengthened ferritic stainless steel, enclosed in an HT9 alloy duct, can be expected to achieve the extended burnup goals set for the US program. 3 refs., 3 figs.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76FF02170
- OSTI ID:
- 6496517
- Report Number(s):
- HEDL-SA-3344-FP; CONF-850722-3; IAEA-SM-284/15; ON: DE85018212
- Country of Publication:
- United States
- Language:
- English
Similar Records
High burnup performance of an advanced oxide fuel assembly in FFTF (Fast Flux Test Facility) with ferritic/martensitic materials
Irradiation performance of Fast Flux Test Facility drivers using D9 alloy
Related Subjects
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOY-D-9
ALLOY-HT-9
ALLOYS
BURNUP
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL PINS
FUELS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
MIXED OXIDE FUELS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NICKEL STEELS
NICKEL-CHROMIUM STEELS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
SOLID FUELS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
SWELLING
TEST REACTORS