Abstract
We have investigated retention of deuterium in beryllium-containing, laboratory-made films whose properties resemble co-deposits observed on JET-ILW or predicted for ITER. The samples were prepared using High Power Impulse Magnetron Sputtering and Thermo-ionic Vacuum Arc Deposition. We have observed that retention depends on the flux of D atoms on the growing film, but even more prominently on its composition, structure, and morphology. Especially, inclusion of carbon by 10-15 at% in the layers can increase retention by a factor of 2-10. This we attribute to increasing number of defects as well as aromatic and aliphatic C-D bonds in the samples. Other impurities do not significantly alter the D inventory while more D is retained in samples with rough or highly modified surfaces. Our results show that reproducing the reported D concentrations of ∼5 at% in JET-ILW-like deposits requires keeping the sample temperature at 100-200 °C during the production phase and optimizing the uniformity of deposition fluxes. Data from Be-D samples further indicate that fuel retention in more ITER-relevant co-deposits would be around 1-2 at%.
Original language | English |
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Article number | 014038 |
Journal | Physica Scripta |
Volume | 2020 |
Issue number | T171 |
DOIs | |
Publication status | Published - 1 Jan 2020 |
MoE publication type | A1 Journal article-refereed |
Event | 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2019 - Eindhoven, Netherlands Duration: 20 May 2019 → 24 May 2019 |
Keywords
- Beryllium
- Co-deposition
- Fuel retention
- H2020
- Euratom