Comparison of fracture behavior for low-swelling ferritic and austenitic alloys irradiated in the Fast Flux Test Facility (FFTF) to 180 DPA

Technical Report · Sat Feb 01 04:00:00 EST 1992

DOI:https://doi.org/10.2172/5878662· OSTI ID:5878662

Huang, F H

Fracture toughness testing was conducted to investigate the radiation embrittlement of high-nickel superalloys, modified austenitic steels and ferritic steels. These materials have been experimentally proven to possess excellent resistance to void swelling after high neutron exposures. In addition to swelling resistance, post-irradiation fracture resistance is another important criterion for reactor material selection. By means of fracture mechanics techniques the fracture behavior of those highly irradiated alloys was characterized in terms of irradiation and test conditions. Precipitation-strengthened alloys failed by channel fracture with very low postirradiation ductility. The fracture toughness of titanium-modified austenitic stainless steel D9 deteriorates with increasing fluence to about 100 displacement per atom (dpa), the fluence level at which brittle fracture appears to occur. Ferritic steels such as HT9 are the most promising candidate materials for fast and fusion reactor applications. The upper-shelf fracture toughness of alloy HT9 remained adequate after irradiation to 180 dpa although its ductile- brittle transition temperature (DBTT) shift by low temperature irradiation rendered the material susceptible to brittle fracture at room temperature. Understanding the fracture characteristics under various irradiation and test conditions helps reduce the potential for brittle fracture by permitting appropriate measure to be taken.

• Research Organization: Westinghouse Hanford Co., Richland, WA (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-87RL10930
• OSTI ID: 5878662
• Report Number(s): WHC-SA-1392-Rev.1; ON: DE92008367
• Country of Publication: United States
• Language: English

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ALLOY-D-9
ALLOY-HT-9
ALLOYS
AUSTENITIC STEELS
BARYONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CORROSION RESISTANT ALLOYS
CREEP
ELEMENTARY PARTICLES
EMBRITTLEMENT
FAST NEUTRONS
FERMIONS
FERRITIC STEELS
FRACTOGRAPHY
FRACTURE PROPERTIES
HADRONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MARTENSITIC STEELS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDEN
MOLYBDENUM ADDITIONS
Ma
Materials Studies-- (1992-)
NEUTRONS
NICKEL ALLOYS
NICKEL STEELS
NICKEL-CHROMIUM STEELS
NUCLEONS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR MATERIALS
STAINLESS STEELS
STEEL-CR12MOV
STEELS
SWELLING