Fuel retention in JET ITER-Like Wall from post-mortem analysis

K. Heinola (Corresponding Author), A. Widdowson, J. Likonen, E. Alves, A. Baron-Wiechec, N. Barradas, S. Brzinsek, N. Catarino, P. Coad, S. Koivuranta, G.F. Matthews, M. Mayer, P Petersson, JET-EFDA Contributors

Research output: Contribution to journalArticleScientificpeer-review

33 Citations (Scopus)

Abstract

Selected Ion Beam Analysis techniques applicable for detecting deuterium and heavier impurities have been used in the post-mortem analyses of tiles removed after the first JET ITER-Like Wall (JET-ILW) campaign. Over half of the retained fuel was measured in the divertor region. The highest figures for fuel retention were obtained from regions with the thickest deposited layers, i.e. in the inner divertor on top of tile 1 and on the High Field Gap Closure tile, which resides deep in the plasma scrape-off layer. Least retention was found in the main chamber high erosion regions, i.e. in the mid-plane of Inner Wall Guard Limiter. The fuel retention values found typically varied with deposition layer thicknesses. The reported retention values support the observed decrease in fuel retention obtained with gas balance experiments of JET-ILW.
Original languageEnglish
Pages (from-to)961-965
JournalJournal of Nuclear Materials
Volume463
DOIs
Publication statusPublished - 2015
MoE publication typeA1 Journal article-refereed

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Tile
tiles
Deuterium
Limiters
Ion beams
Erosion
Gases
closures
erosion
Impurities
deuterium
Plasmas
chambers
ion beams
impurities
gases
Experiments

Cite this

Heinola, K., Widdowson, A., Likonen, J., Alves, E., Baron-Wiechec, A., Barradas, N., ... Contributors, JET-EFDA. (2015). Fuel retention in JET ITER-Like Wall from post-mortem analysis. Journal of Nuclear Materials, 463, 961-965. https://doi.org/10.1016/j.jnucmat.2014.12.098
Heinola, K. ; Widdowson, A. ; Likonen, J. ; Alves, E. ; Baron-Wiechec, A. ; Barradas, N. ; Brzinsek, S. ; Catarino, N. ; Coad, P. ; Koivuranta, S. ; Matthews, G.F. ; Mayer, M. ; Petersson, P ; Contributors, JET-EFDA. / Fuel retention in JET ITER-Like Wall from post-mortem analysis. In: Journal of Nuclear Materials. 2015 ; Vol. 463. pp. 961-965.
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abstract = "Selected Ion Beam Analysis techniques applicable for detecting deuterium and heavier impurities have been used in the post-mortem analyses of tiles removed after the first JET ITER-Like Wall (JET-ILW) campaign. Over half of the retained fuel was measured in the divertor region. The highest figures for fuel retention were obtained from regions with the thickest deposited layers, i.e. in the inner divertor on top of tile 1 and on the High Field Gap Closure tile, which resides deep in the plasma scrape-off layer. Least retention was found in the main chamber high erosion regions, i.e. in the mid-plane of Inner Wall Guard Limiter. The fuel retention values found typically varied with deposition layer thicknesses. The reported retention values support the observed decrease in fuel retention obtained with gas balance experiments of JET-ILW.",
author = "K. Heinola and A. Widdowson and J. Likonen and E. Alves and A. Baron-Wiechec and N. Barradas and S. Brzinsek and N. Catarino and P. Coad and S. Koivuranta and G.F. Matthews and M. Mayer and P Petersson and JET-EFDA Contributors",
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Heinola, K, Widdowson, A, Likonen, J, Alves, E, Baron-Wiechec, A, Barradas, N, Brzinsek, S, Catarino, N, Coad, P, Koivuranta, S, Matthews, GF, Mayer, M, Petersson, P & Contributors, JET-EFDA 2015, 'Fuel retention in JET ITER-Like Wall from post-mortem analysis', Journal of Nuclear Materials, vol. 463, pp. 961-965. https://doi.org/10.1016/j.jnucmat.2014.12.098

Fuel retention in JET ITER-Like Wall from post-mortem analysis. / Heinola, K. (Corresponding Author); Widdowson, A.; Likonen, J.; Alves, E.; Baron-Wiechec, A.; Barradas, N.; Brzinsek, S.; Catarino, N.; Coad, P.; Koivuranta, S.; Matthews, G.F.; Mayer, M.; Petersson, P; Contributors, JET-EFDA.

In: Journal of Nuclear Materials, Vol. 463, 2015, p. 961-965.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Fuel retention in JET ITER-Like Wall from post-mortem analysis

AU - Heinola, K.

AU - Widdowson, A.

AU - Likonen, J.

AU - Alves, E.

AU - Baron-Wiechec, A.

AU - Barradas, N.

AU - Brzinsek, S.

AU - Catarino, N.

AU - Coad, P.

AU - Koivuranta, S.

AU - Matthews, G.F.

AU - Mayer, M.

AU - Petersson, P

AU - Contributors, JET-EFDA

N1 - Project code: 104445

PY - 2015

Y1 - 2015

N2 - Selected Ion Beam Analysis techniques applicable for detecting deuterium and heavier impurities have been used in the post-mortem analyses of tiles removed after the first JET ITER-Like Wall (JET-ILW) campaign. Over half of the retained fuel was measured in the divertor region. The highest figures for fuel retention were obtained from regions with the thickest deposited layers, i.e. in the inner divertor on top of tile 1 and on the High Field Gap Closure tile, which resides deep in the plasma scrape-off layer. Least retention was found in the main chamber high erosion regions, i.e. in the mid-plane of Inner Wall Guard Limiter. The fuel retention values found typically varied with deposition layer thicknesses. The reported retention values support the observed decrease in fuel retention obtained with gas balance experiments of JET-ILW.

AB - Selected Ion Beam Analysis techniques applicable for detecting deuterium and heavier impurities have been used in the post-mortem analyses of tiles removed after the first JET ITER-Like Wall (JET-ILW) campaign. Over half of the retained fuel was measured in the divertor region. The highest figures for fuel retention were obtained from regions with the thickest deposited layers, i.e. in the inner divertor on top of tile 1 and on the High Field Gap Closure tile, which resides deep in the plasma scrape-off layer. Least retention was found in the main chamber high erosion regions, i.e. in the mid-plane of Inner Wall Guard Limiter. The fuel retention values found typically varied with deposition layer thicknesses. The reported retention values support the observed decrease in fuel retention obtained with gas balance experiments of JET-ILW.

U2 - 10.1016/j.jnucmat.2014.12.098

DO - 10.1016/j.jnucmat.2014.12.098

M3 - Article

VL - 463

SP - 961

EP - 965

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

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