Irradiation hardening in F82H irradiated at 573 K in the HFIR
- ORNL
- Japan Atomic Energy Agency (JAEA)
- University of California, Santa Barbara
Post-irradiation tensile tests were conducted on alloy F82H and variants of this steels irradiated at 573 K up to 19 dpa in the High Flux Isotope Reactor (HFIR) in Oak Ridge National Laboratory. Post-irradiation tensile and hardness tests revealed that the strength of F82H steeply increased below 5 dpa, and the total elongation decreased. The ductility of the variants, which showed more ductility in the unirradiated condition was the same as irradiated F82H, even though the magnitude of irradiation hardening is smaller than F82H. This suggests that the softened parts of the blanket, such as heat affected zones, could show more ductility loss at this temperature. The hardening behavior of F82H with 0.09% additional tantalum (mod3), which demonstrated microstructural stability under high temperature processing, was very similar to that of F82H. Therefore mod3 can be an attractive alternate structural material for a blanket when processed above 1373 K.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Science (SC)
- DOE Contract Number:
- DE-AC05-00OR22725
- OSTI ID:
- 1031011
- Journal Information:
- Journal of Nuclear Materials, Vol. 417, Issue 1-3; ISSN 0022-3115
- Country of Publication:
- United States
- Language:
- English
Similar Records
Strain evaluation using a non-contact deformation measurement system in tensile tests of irradiated F82H and 9cr ODS steels
Heat Treatment Effect on Fracture Toughness of F82H Irradiated in HFIR