Abstract
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 |
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Keywords
- tritium
- JET
- divertor
- carbon-based materials
- hydrogen retention
- ITER
- fusion energy
- plasma
- tungsten
Cite this
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Tritium distribution measurement of JET Mk II SRP divertor tiles. / Tanabe, T.; Sugiyama, K.; Renvall, T.; Likonen, Jari; Penttinen, L.; Vainonen-Ahlgren, Elizaveta; Coad, J.P.
In: Journal of Nuclear Materials, Vol. 363-365, 2007, p. 960-965.Research output: Contribution to journal › Article › Scientific › peer-review
TY - JOUR
T1 - Tritium distribution measurement of JET Mk II SRP divertor tiles
AU - Tanabe, T.
AU - Sugiyama, K.
AU - Renvall, T.
AU - Likonen, Jari
AU - Penttinen, L.
AU - Vainonen-Ahlgren, Elizaveta
AU - Coad, J.P.
PY - 2007
Y1 - 2007
N2 - 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.
AB - 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.
KW - tritium
KW - JET
KW - divertor
KW - carbon-based materials
KW - hydrogen retention
KW - ITER
KW - fusion energy
KW - plasma
KW - tungsten
U2 - 10.1016/j.jnucmat.2007.01.191
DO - 10.1016/j.jnucmat.2007.01.191
M3 - Article
VL - 363-365
SP - 960
EP - 965
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
SN - 0022-3115
ER -