| About this Abstract |
| Meeting |
2023 TMS Annual Meeting & Exhibition
|
| Symposium
|
Refractory Metals 2023
|
| Presentation Title |
A New Tungsten Alloy for Fusion Reactors |
| Author(s) |
Neal Parkes, Alexander Knowles, Chris Hardie |
| On-Site Speaker (Planned) |
Neal Parkes |
| Abstract Scope |
Nuclear Fusion offers us the possibility of an abundant supply of energy without the carbon footprint of other technologies. Due to the extreme environment of fusion reactors, tungsten has been identified as one of the leading candidate materials. However, there are major concerns with tungsten’s high DBTT, potential irradiation embrittlement at low temperature, as well as poor oxidation resistance - during loss-of-coolant or air ingress into the reactor.
To address these challenges, W-Cr nanostructured alloys are being developed. Controlled thermal heat treatments are used to produce a nanostructured tungsten alloys to improve (1) ductility (2) irradiation damage resistance and (3) accident tolerance. Alloys were produced by powder processing, characterised using electron microscopy and subjected to various physical/mechanical measurements. |
| Proceedings Inclusion? |
Undecided |
| Keywords |
High-Temperature Materials, Nuclear Materials, Additive Manufacturing |