About this Abstract |
Meeting |
2020 TMS Annual Meeting & Exhibition
|
Symposium
|
Radiation Effects in Metals and Ceramics
|
Presentation Title |
H-63: Small Scale Tensile Testing of Grain Boundary Strength of Pristine and Neutron Irradiated Ni Based X-750 Alloy |
Author(s) |
Yachun Wang, Xiang Liu, Daniel Murray, Fei Teng, Mukesh Bachhav, Wen Jiang, Lingfeng He, Cheng Sun, Ziqi Xiao, Xian-Ming Bai, John Jackson, Robert Carter |
On-Site Speaker (Planned) |
Yachun Wang |
Abstract Scope |
The degradation of grain boundary (GB) strength under irradiation conditions can cause intergranular cracks inside reactor structural materials and pose a safety threat. Understanding the relationship between GB character and its strength in neutron irradiated Ni based X-750 alloy can shed insight into the impact of irradiation on the grain boundary strength. This work aims, by combining advanced characterizations, small-scale tensile test, and modeling, to quantitatively study effects of element segregation/depletion and precipitates on GB strength in neutron-irradiated and non-irradiated X-750 alloys. The GB microstructure was characterized by utilizing Electron Backscatter Diffraction (EBSD), Transmission Electron Microscope (TEM) equipped with Energy Dispersive x-ray Spectroscopy (EDS) and Atom Probe Tomography (APT). Evaluation on the strength of single GB of different types has been performed through small-scale tensile testing and modeling. |
Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |