期刊
JOURNAL OF NUCLEAR MATERIALS
卷 481, 期 -, 页码 33-45出版社
ELSEVIER
DOI: 10.1016/j.jnucmat.2016.08.033
关键词
Oxide dispersion strengthened; Nanoindentation; Plasticity; Ion irradiation
资金
- U.S. Nuclear Regulatory Commission [NRC-HQ-84-14-G-0056, NRC-38-08-955]
- US DOE Office of Nuclear Energy under DOE Idaho Operations Office, Nuclear Science User Facilities experiments [DE-AC07-05ID14517, 14-485, 14-486, 15-540]
- Micron Foundation
- Brazilian Scientific Mobility Program
The objective of this study is to determine irradiation effects on the nanoindentation plastic zone morphology in a model Fe-9%Cr ODS alloy. Specimens are irradiated to 50 displacements per atom at 400 degrees C with Fe++ self-ions or to 3 dpa at 500 degrees C with neutrons. The as-received specimen is also studied as a control. The nanoindentation plastic zone size is calculated using two approaches: (1) an analytical model based on the expanding spherical cavity analogy, and (2) finite element modeling (FEM). Plastic zones in all specimen conditions extend radially outward from the indenter, similar to 4-5 times the tip radius, indicative of fully plastic contact. Non-negligible plastic flow in the radial direction requires the experimentalist to consider the plastic zone morphology when nanoindenting ion-irradiated specimens; a single nanoindent may sample non-uniform irradiation damage, regardless of whether the indent is made top-down or in cross-section. Finally, true stress-strain curves are generated. (C) 2016 Elsevier B.V. All rights reserved.
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