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High Temperature Irradiation Effects in Selected Generation IV Structural Alloys...

by Randy K Nanstad, David A Mcclintock, David T Hoelzer, Lizhen Tan, Todd Allen
Publication Type
Journal
Journal Name
Journal of Nuclear Materials
Publication Date
Page Numbers
331 to 340
Volume
392
Issue
2

In the Generation IV Materials Program cross-cutting task, irradiation and testing were carried out to address the issue of high temperature irradiation effects with selected current and potential candidate metallic alloys. The materials tested were (1) a high-nickel iron-base alloy (Alloy 800H); (2) a nickel-base alloy (Alloy 617); (3) two advanced nano-structured ferritic alloys (designated 14YWT and 14WT); and (4) a commercial ferritic-martensitic steel (annealed 9Cr-1MoV). Small tensile specimens were irradiated in rabbit capsules in the High-Flux Isotope Reactor at temperatures from about 550 to 700�C and to irradiation doses in the range 1.2 to 1.6 dpa. The Alloy 800H and Alloy 617 exhibited significant hardening after irradiation at 580�C; some hardening occurred at 660�C as well, but the 800H showed extremely low tensile elongations when tested at 700�C. Notably, the grain boundary engineered 800H exhibited even greater hardening at 580�C and retained a high amount of ductility. Irradiation effects on the two nano-structured ferritic alloys and the annealed 9Cr-1MoV were relatively slight at this low dose.