About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Special Topics in Nuclear Materials: Reproducibility and Uncertainty; Hydrogen Effects; Space and Microreactor Systems
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| Presentation Title |
Hydrogen Isotope Retention in Displacement Damaged Tungsten |
| Author(s) |
Sabina Markelj |
| On-Site Speaker (Planned) |
Sabina Markelj |
| Abstract Scope |
This contribution presents a series of experiments on hydrogen isotope (HI) retention in displacement-damaged tungsten (W), where damage was induced by MeV W ions to simulate 14 MeV neutron irradiation from fusion. The interaction of HIs with defects and the evolution of those defects under varying temperatures were studied using deuterium (D) depth profiling and thermal desorption spectroscopy. Results show that defects act as traps for D, with their density increasing with damage dose and decreasing with temperature. A synergistic effect was observed when W was simultaneously irradiated and exposed to low-energy D at 450–1100 K, resulting in enhanced D retention. Furthermore, grain boundaries were found to influence D transport but had a limited impact on retention. Finally, recent advancements in ion channeling techniques have enabled detailed analysis of lattice damage and the localization of D in the crystal, providing critical insights into defect-HI interactions relevant for fusion materials development. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, High-Temperature Materials, |