Deuterium retention on the tungsten-coated divertor tiles of JET ITER-like wall in 2015-2016 campaign

被引：7

作者：

Lahtinen, A. ^{[1
]}

Likonen, J. ^{[2
]}

Koivuranta, S. ^{[3
]}

Alves, E. ^{[3
]}

Baron-Wiechec, A. ^{[4
]}

Catarino, N. ^{[3
]}

Coad, J. P. ^{[4
]}

Heinola, K. ^{[1
]}

Raisanen, J. ^{[1
]}

Widdowson, A. ^{[4
]}

机构：

[1] Univ Helsinki, Dept Phys, POB 43, FIN-00014 Helsinki, Finland

[2] VTT Tech Res Ctr Finland Ltd, POB 1000, Espoo 02044, Finland

[3] Univ Lisbon, Inst Super Tecn, P-1049001 Lisbon, Portugal

[4] Culham Sci Ctr, CCFE, Abingdon OX14 3DB, Oxon, England

来源：

FUSION ENGINEERING AND DESIGN | 2019年 / 146卷

关键词：

JET; Fuel retention; Erosion; Deposition;

D O I：

10.1016/j.fusengdes.2019.03.081

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Tungsten-coated divertor files exposed during the third JET ITER-Like Wall (ILW) campaign in 2015-2016 (ILW-3) were studied with Secondary Ion Mass Spectrometry (SIMS). ILW-3 campaign contained more high-power plasma discharges and longer plasma time than the earlier ILW campaigns. Measurements showed increased beryllium (Be) deposition on the upper inner divertor, whereas on the outer divertor, Be deposition was lower than during the second campaign in 2013-2014 (ILW-2). Increased intensifies of nickel, molybdenum and tungsten were observed at the surface layer of the inner divertor Be dominated deposits. These layers are probably formed during the high-power plasma discharge phase near the end of the ILW-3 campaign. Compared to the earlier campaigns, D retention on the upper inner divertor was observed to on a similar level than after ILW-2, whereas at the lower inner divertor and most parts of the outer divertor, D retention was lower for ILW-3 than ILW-2. D retention was increased at lower part of outer divertor Tile 7, where Be deposition was slightly increased. Probable reason for the reduction is the higher surface temperature of the files due to higher powers used.

引用

页码：1979 / 1982

页数：4

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