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

JET Contributors

Research output: Contribution to journalArticleScientificpeer-review

1 Citation (Scopus)

Abstract

Tungsten-coated divertor tiles 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 intensities 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 tiles due to higher powers used.

Original languageEnglish
JournalFusion Engineering and Design
DOIs
Publication statusE-pub ahead of print - 27 Apr 2019
MoE publication typeA1 Journal article-refereed

Fingerprint

Beryllium
Tungsten
Deuterium
Tile
Beryllium deposits
Plasmas
Molybdenum
Secondary ion mass spectrometry
Nickel
Temperature

Keywords

  • Deposition
  • Erosion
  • Fuel retention
  • JET

Cite this

@article{1c1adcd3f4554e91a116e9dfee02ad38,
title = "Deuterium retention on the tungsten-coated divertor tiles of JET ITER-like wall in 2015–2016 campaign",
abstract = "Tungsten-coated divertor tiles 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 intensities 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 tiles due to higher powers used.",
keywords = "Deposition, Erosion, Fuel retention, JET",
author = "A. Lahtinen and J. Likonen and S. Koivuranta and E. Alves and A. Baron-Wiechec and N. Catarino and Coad, {J. P.} and K. Heinola and J. R{\"a}is{\"a}nen and A. Widdowson and {JET Contributors}",
year = "2019",
month = "4",
day = "27",
doi = "10.1016/j.fusengdes.2019.03.081",
language = "English",
journal = "Fusion Engineering and Design",
issn = "0920-3796",
publisher = "Elsevier",

}

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

In: Fusion Engineering and Design, 27.04.2019.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Deuterium retention on the tungsten-coated divertor tiles of JET ITER-like wall in 2015–2016 campaign

AU - Lahtinen, A.

AU - Likonen, J.

AU - Koivuranta, S.

AU - Alves, E.

AU - Baron-Wiechec, A.

AU - Catarino, N.

AU - Coad, J. P.

AU - Heinola, K.

AU - Räisänen, J.

AU - Widdowson, A.

AU - JET Contributors

PY - 2019/4/27

Y1 - 2019/4/27

N2 - Tungsten-coated divertor tiles 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 intensities 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 tiles due to higher powers used.

AB - Tungsten-coated divertor tiles 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 intensities 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 tiles due to higher powers used.

KW - Deposition

KW - Erosion

KW - Fuel retention

KW - JET

UR - http://www.scopus.com/inward/record.url?scp=85064747541&partnerID=8YFLogxK

U2 - 10.1016/j.fusengdes.2019.03.081

DO - 10.1016/j.fusengdes.2019.03.081

M3 - Article

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

SN - 0920-3796

ER -