Tritium distribution measurement of JET Mk IISRP divertor tiles

T. Tanabe; K. Sugiyama; T. Renvall; J. Likonen; L. Penttinen; E. Vainonen-Ahlgren; J.P. Coad

doi:10.1016/j.jnucmat.2007.01.191

Tritium distribution measurement of JET Mk IISRP divertor tiles

T. Tanabe (Corresponding Author), K. Sugiyama, T. Renvall, J. Likonen, L. Penttinen, E. Vainonen-Ahlgren, J.P. Coad

BA2F06 Fusion energy and decommissioning

Research output: Contribution to journal › Article › Scientific › peer-review

8 Citations (Scopus)

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 language	English
Pages (from-to)	960-965
Journal	Journal of Nuclear Materials
Volume	363-365
DOIs	https://doi.org/10.1016/j.jnucmat.2007.01.191
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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@article{c8eb3985e5e34618a200c20ee37c91b0,

title = "Tritium distribution measurement of JET Mk IISRP 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 {\textquoteleft}shadowed area{\textquoteright}). 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 J. Likonen and L. Penttinen and E. Vainonen-Ahlgren and J.P. Coad",

year = "2007",

doi = "10.1016/j.jnucmat.2007.01.191",

language = "English",

volume = "363-365",

pages = "960--965",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

note = "17th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, PSI17 ; Conference date: 22-05-2006 Through 26-05-2006",

}

TY - JOUR

T1 - Tritium distribution measurement of JET Mk IISRP divertor tiles

AU - Tanabe, T.

AU - Sugiyama, K.

AU - Renvall, T.

AU - Likonen, J.

AU - Penttinen, L.

AU - Vainonen-Ahlgren, E.

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

T2 - 17th International Conference on Plasma Surface Interactions in Controlled Fusion Devices

Y2 - 22 May 2006 through 26 May 2006

ER -