About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Mechanical and Thermal Characterization of Combinatorial Tungsten Alloy Thin Films Fabricated Using PVD |
| Author(s) |
Aidan Earll, Sriram Vijayan |
| On-Site Speaker (Planned) |
Aidan Earll |
| Abstract Scope |
Divertors in nuclear fusion reactors absorb heat, channel plasma instabilities, and remove contaminant particles. Pure tungsten is one of the primary candidate plasma-facing materials (PFMs) used for divertors. Tungsten is selected for its robust mechanical, thermal, and radiation properties. However, fusion reactor conditions are extreme, and PFMs remain a key limitation for reactor longevity. In this study, multiple combinatorial tungsten alloy thin films are produced using physical vapor deposition (PVD) for high-throughput testing, with nano-hardness, reduced modulus, electrical conductivity (as a surrogate for thermal conductivity), and plasma sputtering rate as evaluation methods. Microstructural characterization is performed using SEM/EDS and XRD, while a custom in situ SEM microheater device enables thermo-mechanical cycling under fusion-relevant conditions. In situ SEM heating experiments performed on a subset of alloys revealed damage accumulation from thermal cycling. This systematic methodology aims to identify alloy compositions that enhance performance beyond pure tungsten for divertor material development. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
High-Temperature Materials, Thin Films and Interfaces, Nuclear Materials |