Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels
- Oak Ridge National Lab., TN (United States)
Ferritic/martensitic steels such as the conventional 9Cr-1MoVNb (Fe-9Cr-1Mo-0.25V-0.06Nb-0.1C) and 12Cr-1MoVW (Fe-12Cr-1Mo-0.25V-0.5W-0.5Ni-0.2C) steels have been considered potential structural materials for future fusion power plants. The major obstacle to their use is embrittlement caused by neutron irradiation. Observations on this irradiation embrittlement is reviewed. Below 425-450{degrees}C, neutron irradiation hardens the steels. Hardening reduces ductility, but the major effect is an increase in the ductile-brittle transition temperature (DBTT) and a decrease in the upper-shelf energy, as measured by a Charpy impact test. After irradiation, DBTT values can increase to well above room temperature, thus increasing the chances of brittle rather than ductile fracture.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- OSTI ID:
- 543208
- Report Number(s):
- DOE/ER--0313/22; ON: DE97008797
- Country of Publication:
- United States
- Language:
- English
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