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.
| Original language | English |
|---|---|
| Pages (from-to) | 331-340 |
| Number of pages | 10 |
| Journal | Journal of Nuclear Materials |
| Volume | 392 |
| Issue number | 2 |
| DOIs | |
| State | Published - Jul 15 2009 |
Funding
This work was sponsored by the US Department of Energy, Office of Nuclear Energy Science and Technology under contract DE-AC05-00OR22725 with Oak Ridge National Laboratory, managed by UT-Battelle, LLC.
| Funders | Funder number |
|---|---|
| Office of Nuclear Energy Science and Technology | DE-AC05-00OR22725 |
| U.S. Department of Energy | |
| Oak Ridge National Laboratory | |
| UT-Battelle |