| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
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| Symposium
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Advances in Bcc-Superalloys
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| Presentation Title |
Tungsten-Based BCC Superalloys for Nuclear Fusion |
| Author(s) |
Matthew James Lloyd, Jóhan Magnuessen, Neal Parkes, Alexander Knowles |
| On-Site Speaker (Planned) |
Matthew James Lloyd |
| Abstract Scope |
The high temperatures and neutron irradiation anticipated in nuclear fusion reactors requires the use of novel, high-performance materials. W is brittle and suffers from irradiation induced embrittlement and precipitation of transmutation products [1]. Novel solutions include tungsten-based BCC-superalloys [2,3] and refractory high-entropy alloys (RHEAs), but there is limited data on their irradiation response. Tungsten-based BCC-superalloys use B2 intermetallic phases to offer strengthening and a high density of point defect sinks to suppress radiation induced clustering/precipitation.
This study explores the mechanical properties and irradiation response of W-(Ti,Fe), WTaV alloys and RHEAs using sub-scale tensile/3-point bend testing and nanoindentation. Radiation damage is produced using irradiation with heavy-ions and intermediate energy protons and is characterised using APT and TEM.
[1] M.J.Lloyd, et al., Materialia (2023) 101991.
[2] A.J.Knowles, et al., Appl Mater Today 23 (2021) 101014.
[3] N.Parkes, et al., Int J Refract Metals Hard Mater 113 (2023) 106209.
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| Proceedings Inclusion? |
Planned: |
| Keywords |
High-Temperature Materials, Characterization, Mechanical Properties |