Improving the fracture resistance of irradiated martensitic steels
Conference
·
OSTI ID:10124415
Martensitic steels find application in fast breeder reactors mainly because of their excellent resistance to radiation-induced swelling and creep, but the fracture resistance of the material under neutron irradiation also needs to be assessed. These steels undergo a change in the fracture mode from ductile dimple rupture to brittle cleavage as temperature decreases. Neutron exposure can raise the ductile-brittle transition temperature and produce a condition a low toughness during service. This study examines the effects of cold-work, heat treatment, and chromium content on the postirradiation fracture behavior of selected steels to provide a better understanding of fracture resistance in hopes of improving it. Experimental materials included alloy HT9 containing 12 percent Cr, a vacuum remelt of HT9, modified HT9 containing 10 percent Cr, and 9Cr-1MO. The initiation fracture toughness of irradiated martensitic steels increased with increasing chromium content and tempering temperature. Remelting of HT9 slightly raised the fracture toughness of the irradiated materials. Cold work did not improve the fracture resistance of irradiated ferritic steels as it did for austenitic steels.
- Research Organization:
- Westinghouse Hanford Co., Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-87RL10930
- OSTI ID:
- 10124415
- Report Number(s):
- WHC-SA--1432; CONF-920673--2; ON: DE92008387
- Country of Publication:
- United States
- Language:
- English
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Tue Dec 31 23:00:00 EST 1991
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Sun Jun 01 00:00:00 EDT 1997
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OSTI ID:543208
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500
36 MATERIALS SCIENCE
360103
360106
ALLOY-HT-9
CHROMIUM
CHROMIUM-MOLYBDENUM STEELS
DUCTILE-BRITTLE TRANSITIONS
FAST REACTORS
FRACTURE PROPERTIES
IRRADIATION
MARTENSITIC STEELS
MECHANICAL PROPERTIES
METALLURGICAL EFFECTS
NEUTRON FLUENCE
PHYSICAL RADIATION EFFECTS
POWER REACTORS
BREEDING
RADIATION EFFECTS
REACTOR MATERIALS
210500
36 MATERIALS SCIENCE
360103
360106
ALLOY-HT-9
CHROMIUM
CHROMIUM-MOLYBDENUM STEELS
DUCTILE-BRITTLE TRANSITIONS
FAST REACTORS
FRACTURE PROPERTIES
IRRADIATION
MARTENSITIC STEELS
MECHANICAL PROPERTIES
METALLURGICAL EFFECTS
NEUTRON FLUENCE
PHYSICAL RADIATION EFFECTS
POWER REACTORS
BREEDING
RADIATION EFFECTS
REACTOR MATERIALS