Tritium distribution measurement of JET Mk II SRP divertor tiles

T. Tanabe, K. Sugiyama, T. Renvall, Jari Likonen, L. Penttinen, Elizaveta Vainonen-Ahlgren, J.P. Coad

Research output: Contribution to journalArticleScientificpeer-review

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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.
Original languageEnglish
Pages (from-to)960-965
JournalJournal of Nuclear Materials
Volume363-365
DOIs
Publication statusPublished - 2007
MoE publication typeA1 Journal article-refereed

Fingerprint

septum
Tritium
tiles
Tile
tritium
Plasmas
slots
entrances
pumping
Carbon
Imaging techniques
carbon
profiles

Keywords

  • tritium
  • JET
  • divertor
  • carbon-based materials
  • hydrogen retention
  • ITER
  • fusion energy
  • plasma
  • tungsten

Cite this

Tanabe, T., Sugiyama, K., Renvall, T., Likonen, J., Penttinen, L., Vainonen-Ahlgren, E., & Coad, J. P. (2007). Tritium distribution measurement of JET Mk II SRP divertor tiles. Journal of Nuclear Materials, 363-365, 960-965. https://doi.org/10.1016/j.jnucmat.2007.01.191
Tanabe, T. ; Sugiyama, K. ; Renvall, T. ; Likonen, Jari ; Penttinen, L. ; Vainonen-Ahlgren, Elizaveta ; Coad, J.P. / Tritium distribution measurement of JET Mk II SRP divertor tiles. In: Journal of Nuclear Materials. 2007 ; Vol. 363-365. pp. 960-965.
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title = "Tritium distribution measurement of JET Mk II SRP divertor tiles",
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.",
keywords = "tritium, JET, divertor, carbon-based materials, hydrogen retention, ITER, fusion energy, plasma, tungsten",
author = "T. Tanabe and K. Sugiyama and T. Renvall and Jari Likonen and L. Penttinen and Elizaveta Vainonen-Ahlgren and J.P. Coad",
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Tanabe, T, Sugiyama, K, Renvall, T, Likonen, J, Penttinen, L, Vainonen-Ahlgren, E & Coad, JP 2007, 'Tritium distribution measurement of JET Mk II SRP divertor tiles', Journal of Nuclear Materials, vol. 363-365, pp. 960-965. https://doi.org/10.1016/j.jnucmat.2007.01.191

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 journalArticleScientificpeer-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

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