Measurement of grain boundary strength of Inconel X-750 superalloy using in-situ micro-tensile testing techniques in FIB/SEM system
Grain boundaries (GBs), known as two-dimensional defects, are omnipresent in polycrystalline metallic alloys and thus influence a wide range of mechanical properties under different environmental conditions like irradiation and corrosion. Therefore, quantifying the strength of individual GBs is crit...
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Published in | Materials science & engineering. A, Structural materials : properties, microstructure and processing Vol. 849; p. 143475 |
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Main Authors | , , , , , , , , , , , , , , |
Format | Journal Article |
Language | English |
Published |
Lausanne
Elsevier B.V
01.08.2022
Elsevier BV Elsevier |
Subjects | |
Online Access | Get full text |
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Summary: | Grain boundaries (GBs), known as two-dimensional defects, are omnipresent in polycrystalline metallic alloys and thus influence a wide range of mechanical properties under different environmental conditions like irradiation and corrosion. Therefore, quantifying the strength of individual GBs is critical for understanding the degradation of mechanical properties of materials under different conditions. In this study we developed an efficient approach for the fabrication of micro-tensile specimens with a GB almost perpendicular to the tensile direction, which is expected to advance the development of individual GB tensile testing at micro or nanoscale in a wide scope of materials. An in-situ cantilever micro-tensile testing method was developed and used to quantify the strength of a ∑3 GB in Inconel X-750 with the combination of finite element modeling. The average ultimate tensile strength (UTS) of a non-irradiated ∑3 GB is estimated at around 1.4 GPa, comparable to that of a neutron-irradiated ∑3 GB with a dose of ∼1.5 dpa (1.3 GPa). Moreover, the in-situ push-to-pull micro-tensile testing technique developed in this work provides valuable insights into the high-angle GB deformation and fracture behavior. This method generates qualitatively similar ductility behavior before and after neutron irradiation as the bulk material testing. However, the ductility and UTS values obtained from this method are different from bulk measurements due to vastly different specimen dimensions.
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Bibliography: | USDOE Office of Nuclear Energy (NE) USDOE Laboratory Directed Research and Development (LDRD) Program INL/JOU-22-65715-Rev000 AC07-05ID14517 |
ISSN: | 0921-5093 1873-4936 |
DOI: | 10.1016/j.msea.2022.143475 |