Abstract
Tritium surface distribution on the JET Mark II Septum Replacement Plate (Mk II SRP) divertor tiles was measured by imaging plate technique. It was observed that areal tritium concentration was higher at the entrance of inner/outer pumping slots (so called ‘shadowed area’).
The tritium distribution profiles were similar to those obtained in the Mk IIA divertor which was exposed to a series of D–T plasma operation (DTE1). Tritium concentration of the plasma facing surface was lower compared to that of the shadowed area. Particularly, it was very low at the outer divertor surface.
The inner divertor surface also showed low level of tritium retention, though it was covered by the thick carbon deposition on that. This could be caused by tritium release due to the temperature rise when the inner strike point was on the tiles.
On the plasma shadowed area like tile gaps, high tritium retention owing to the codeposition was observed.
The tritium distribution profiles were similar to those obtained in the Mk IIA divertor which was exposed to a series of D–T plasma operation (DTE1). Tritium concentration of the plasma facing surface was lower compared to that of the shadowed area. Particularly, it was very low at the outer divertor surface.
The inner divertor surface also showed low level of tritium retention, though it was covered by the thick carbon deposition on that. This could be caused by tritium release due to the temperature rise when the inner strike point was on the tiles.
On the plasma shadowed area like tile gaps, high tritium retention owing to the codeposition was observed.
| Original language | English |
|---|---|
| Pages (from-to) | 960-965 |
| Journal | Journal of Nuclear Materials |
| Volume | 363-365 |
| DOIs | |
| Publication status | Published - 2007 |
| MoE publication type | A1 Journal article-refereed |
| Event | 17th International Conference on Plasma Surface Interactions in Controlled Fusion Devices - Hefei, China Duration: 22 May 2006 → 26 May 2006 |
Keywords
- tritium
- JET
- divertor
- carbon-based materials
- hydrogen retention
- ITER
- fusion energy
- plasma
- tungsten
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Tanabe, T., Sugiyama, K., Renvall, T., Likonen, J., Penttinen, L., Vainonen-Ahlgren, E., & Coad, J. P. (2007). Tritium distribution measurement of JET Mk IISRP divertor tiles. Journal of Nuclear Materials, 363-365, 960-965. https://doi.org/10.1016/j.jnucmat.2007.01.191