| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Meeting Materials Challenges for the Future of Fusion Energy
|
| Presentation Title |
Simulating Plasma-Surface Interactions with Deuterium Beams Experiments: Effect of Tungsten Oxidation |
| Author(s) |
Aleksandr Afonin, Axel Dunand, Florin Ghiorghiu, Mykola Ialovega, Matthieu Latournerie, Eric Salomon, Marco Minissale, Céline Martin, Thierry Angot, Etienne A Hodille, Régis Bisson |
| On-Site Speaker (Planned) |
Régis Bisson |
| Abstract Scope |
Harnessing fusion’s power is ITER’s goal. Power exhaust will occur on tungsten (W) tiles. Current fusion reactors show varying oxygen contamination on W tiles, from sub-monolayer to micron-thick layers [1]. A detailed understanding of deuterium/tritium (D/T) interaction with W in presence of oxygen is needed because of T radioactivity.
We present deuterium beams experiments to disentangle the plasma-wall interactions complexity. W native oxide appears to resist to D ions sputtering and leads to significant trapping of D in the bulk of W. To better understand this behavior, D interaction with W is compared for a clean W surface, a W surface covered with half-a-monolayer O coverage and a 30 nm thick crystalline WO3. These W surfaces behave differently with respect to bulk and surface D retention. Theoretical modeling using macroscopic rate equations and DFT calculations helps to rationalize these differences [2,3].
[1] https://doi.org/10.1088/1402-4896/ac267e (2021)
[2] https://doi.org/10.1088/1741-4326/aa6d24 (2017)
[3] https://doi.org/10.1088/1741-4326/ad2a29 (2024) |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Surface Modification and Coatings, Thin Films and Interfaces |