Title of article
High temperature irradiation effects in selected Generation IV structural alloys
Author/Authors
Nanstad، نويسنده , , R.K. and McClintock، نويسنده , , D.A. and Hoelzer، نويسنده , , D.T. and Tan، نويسنده , , L. and Allen، نويسنده , , T.R.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2009
Pages
10
From page
331
To page
340
Abstract
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 1.2–1.6 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.
Journal title
Journal of Nuclear Materials
Serial Year
2009
Journal title
Journal of Nuclear Materials
Record number
1365032
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