Improving the fracture resistance of irradiated martensitic steels
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
- Resource Relation:
- Conference: 16. annual symposium of American Society of Testing and Materials (ASTM) on effects of radiation on materials,Denver, CO (United States),21-25 Jun 1992; Other Information: PBD: Jan 1992
- Country of Publication:
- United States
- Language:
- English
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Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels
Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
MARTENSITIC STEELS
FRACTURE PROPERTIES
PHYSICAL RADIATION EFFECTS
CHROMIUM
METALLURGICAL EFFECTS
FAST REACTORS
REACTOR MATERIALS
NEUTRON FLUENCE
IRRADIATION
DUCTILE-BRITTLE TRANSITIONS
CHROMIUM-MOLYBDENUM STEELS
ALLOY-HT-9
360106
360103
210500
RADIATION EFFECTS
MECHANICAL PROPERTIES
POWER REACTORS
BREEDING