Abstract
In situ nano-indentation techniques are attractive for studying the effects of neutron irradiation on the mechanical properties of materials. This study demonstrated high-speed, high-resolution modulus mapping of an irradiated SiC composite and micro-pillar compression testing of an irradiated FeCrAl alloy. Various irradiated specimens and specimen preparation capabilities are available at the LAMDA laboratory for conducting advanced nanoindentation tests through the NSUF program.
| Original language | English |
|---|---|
| Pages (from-to) | 317-319 |
| Number of pages | 3 |
| Journal | Transactions of the American Nuclear Society |
| Volume | 124 |
| Issue number | 1 |
| DOIs | |
| State | Published - 2021 |
| Event | 2021 Transactions of the American Nuclear Society Annual Meeting, ANS 2021 - Virtual, Online, United States Duration: Jun 14 2021 → Jun 16 2021 |
Funding
This study was supported by the US Department of Energy, Office of Nuclear Energy, for the Advanced Fuels Campaign of the Nuclear Technology R&D program under contact DE-AC05-00OR22725 with Oak Ridge National Laboratory, managed by UT Battelle, LLC. PIE was supported by the Office of Nuclear Energy under DOE Idaho Operations Office Contract DE-AC07-051D14517 as part of an NSUF experiment. A portion of this research used resources at the High Flux Isotope Reactor, a DOE Office of Science User Facility operated by ORNL. The authors wish to thank Weicheng Zhong, Omer Karakoc, and Deborah Counce at ORNL for reviewing and editing this manuscript. Campaign of the Nuclear Technology R&D program under contact DE-AC05-00OR22725 with Oak Ridge National Laboratory, managed by UT aB ttelle, LLC. PIE was supported by the Office of Nuclear Energy under DOE Idaho Operations Office Contract DE-AC07 -051D14517 as part of an NSUF experiment. A portion of this research used resources at the High Flux Isotope Reactor , a DOE Office of Science User Facility operated by ORNL. The authors wish to thank Weicheng honZ g, Omer Karakoc, and Deborah Counce at ORNL for reviewing and editing this manuscript. This study was supported by the US Department of Energy, Office of Nuclear Energy, for the Advanced Fuels Notice: This manus cript has been authored by UT-aB ttelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http:e//nergy.gov/downloadsdoe/ -public-access-plan).