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

JET-EFDA Contributors

doi:10.1016/j.jnucmat.2014.12.098

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

JET-EFDA Contributors

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

54 Scopus citations

Abstract

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 language	English
Article number	48830
Pages (from-to)	961-965
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	463
DOIs	https://doi.org/10.1016/j.jnucmat.2014.12.098
State	Published - 22 Jul 2015
Externally published	Yes

Access to Document

10.1016/j.jnucmat.2014.12.098

Cite this

@article{3505f72bdef04303ade932a22e0d5b43,

title = "Fuel retention in JET ITER-Like Wall from post-mortem analysis",

abstract = "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 = "{JET-EFDA Contributors} and K. Heinola and A. Widdowson and J. Likonen and E. Alves and A. Baron-Wiechec and N. Barradas and S. Brezinsek and N. Catarino and P. Coad and S. Koivuranta and Matthews, {G. F.} and M. Mayer and P. Petersson",

note = "Publisher Copyright: {\textcopyright} 2015 EURATOM.",

year = "2015",

month = jul,

day = "22",

doi = "10.1016/j.jnucmat.2014.12.098",

language = "英语",

volume = "463",

pages = "961--965",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

}

TY - JOUR

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

AU - JET-EFDA Contributors

AU - Heinola, K.

AU - Widdowson, A.

AU - Likonen, J.

AU - Alves, E.

AU - Baron-Wiechec, A.

AU - Barradas, N.

AU - Brezinsek, S.

AU - Catarino, N.

AU - Coad, P.

AU - Koivuranta, S.

AU - Matthews, G. F.

AU - Mayer, M.

AU - Petersson, P.

PY - 2015/7/22

Y1 - 2015/7/22

N2 - 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.

AB - 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.

UR - http://www.scopus.com/inward/record.url?scp=84937629112&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2014.12.098

DO - 10.1016/j.jnucmat.2014.12.098

M3 - 文章

AN - SCOPUS:84937629112

SN - 0022-3115

VL - 463

SP - 961

EP - 965

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

M1 - 48830

ER -

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

Abstract

Access to Document

Other files and links

Fingerprint

Cite this