| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Accelerated Discovery and Insertion of Next Generation Structural Materials
|
| Presentation Title |
Novel High-temperature Zirconium Alloys for Fusion Applications |
| Author(s) |
Bradley A. Young, Junliang Liu, Guanze He, Thomas Kwok, Samuel Rogers, Yuanbo Tang, Wenyu Zhang, Megan Carter, Zilin Gao, David Dye, David Armstrong, Chris Grovenor |
| On-Site Speaker (Planned) |
Bradley A. Young |
| Abstract Scope |
Zirconium alloys have been key nuclear fission materials since 1954 due to their low neutron capture cross-section, corrosion resistance, and mechanical properties. Despite this, zirconium has been neglected as a potential structural material in fusion technologies and the data needed to determine the potential of these alloys under fusion conditions remains unknown. Several binary zirconium alloy systems (Zr-Ta,Zr-V,Zr-Mo) have been chosen, cast, and thermo-mechanically processed because of their potential for use at temperatures above 700K.
The alloys’ microstructural stability has been analysed using electron microscopy and atom probe tomography to avoid catastrophic failures in-service due to unexpected microstructural changes. Novel, high-throughput mechanical testing techniques have been chosen and validated to assess an array of alloys efficiently; and these have shown improved strength compared with those available commercially. This work will enable understanding of the microstructure-property relationships in selected systems which may facilitate machine learning optimisation approaches in the future. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, High-Temperature Materials, Mechanical Properties |