Sixth IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis

The saga of nonferrous metallurgy in the quest of new radiation-resistant fusion materials beyond pure tungsten

Not scheduled

20m

Auditorium Hall HGX 102 (Guanghua Twin Tower) (Fudan University, Shanghai, China)

Oral

Speaker

Matheus A. Tunes (Montanuniversität Leoben)

Description

Innovative materials development is essential for advancing nuclear fusion energy technologies, which require high-performance materials capable of withstanding extreme conditions such as intense heat and radiation exposure. Tungsten (W) has historically been a preferred material due to its high melting point, availability, and cost-effectiveness [1]; however, it remains highly susceptible to radiation damage. This limitation highlights the need for alternative materials that can meet the demanding requirements of fusion reactors, posing a problem for contemporary non-ferrous metallurgy. In this work, we will review the scientific data accumulated all over the decades in the radiation damage of W and its binary alloys [2–8]. Although recent high-entropy materials, such as multicomponent equimolar refractory alloys and carbides [9–12], offer improved performance in energetic particle environments compared to traditional W and W-based alloys, they remain impractical for developing new radiation-resistant materials needed for fusion energy applications [13]. Recent strategies towards new “chemically simplified alloys” will be introduced to show that the fundamental metallurgical concept of terminal solid solution may still be a suitable approach for the quest of new radiation-resistant fusion materials [13,14]. This approach aims to bridge the gap between using simple pure W and complex high-entropy alloys, offering a potential pathway for innovation in nuclear fusion research.

References:
1. Davis, J. et al. Journal of Nuclear Materials 258, 308–312 (1998).
2. Harrison, R. W. Vacuum 160, 355–370 (2019).
3. Yi, X. et al. Acta Materialia 92, 163–177 (2015).
4. Yi, X. et al. Acta Materialia 112, 105–120 (2016).
5. Yi, X. et al. Nuclear Materials and Energy 18, 93–98 (2019).
6. Ferroni, F. et al. Acta Materialia 90, 380–393 (2015).
7. Yi, X. et al. Materials Characterization 145, 77–86 (2018).
8. Yi, X. et al. Fusion Engineering and Design 125, 454–457 (2017).
9. El-Atwani, O. et al. Science Advances 5, eaav2002 (2019).
10. Tunes, M. A. et al. Applied Materials Today 32, 101796 (2023).
11. Tunes, M. A. et al. Acta Materialia 250, 118856 (2023).
12. El-Atwani, O. et al. Nature Communications 14, 1–12 (2023).
13. Tunes, M. A. et al. Advanced Science, e2417659 (2025).
14. Nahavandian, M. et al. (2024). arXiv:2412.13343.