| About this Abstract |
| Meeting |
2022 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior and Degradation of Advanced Nuclear Fuel and Structural Materials
|
| Presentation Title |
Microstructure Characterization and Micro-mechanical Properties of 14YWT Tubing after Proton Irradiation |
| Author(s) |
Cayla Harvey, Osman El-Atwani, Stuart Maloy, Siddhartha Pathak |
| On-Site Speaker (Planned) |
Cayla Harvey |
| Abstract Scope |
14YWT nanostructured ferritic alloy (NFA) is a leading structural material candidate for fast nuclear reactors due to its exceptional irradiation tolerance and high strength. We examined This work examines alloys after different processing paths of hydrostatic extrusion and pilger processing with varying annealing temperatures. It is targeted for application as fuel cladding. We conducted electron backscatter diffraction (EBSD) and transmission electron microscopy (TEM) based micro-structural characterization along with corresponding micro-mechanical testing on 14YWT alloys before and after proton irradiation. This work examines alloys after different processing paths of hydrostatic extrusion and pilger processing with varying annealing temperatures. Electron backscatter diffraction was used to identify the principle texture and microstructure components. Transmission electron microscopy was used to characterize the morphology, dislocation density, and oxide particles. Spherical indentation shows the compressive stress-strain response, while micro-tensile tests reveal the change in ductility and tensile strength after proton irradiation. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Powder Materials, Characterization, |