Deuterium retention in the divertor tiles of JET ITER-Like wall

A. Lahtinen; Jari Likonen; Seppo Koivuranta; Antti Hakola; A. Heinola; C.F. Ayres; A. Baron-Wiechec; J.P. Coad; A. Widdowson; J. Räisänen; JET Contributors

doi:10.1016/j.nme.2017.04.007

Deuterium retention in the divertor tiles of JET ITER-Like wall

A. Lahtinen^*, Jari Likonen, Seppo Koivuranta, Antti Hakola, A. Heinola, C.F. Ayres, A. Baron-Wiechec, J.P. Coad, A. Widdowson, J. Räisänen, JET Contributors

^*Corresponding author for this work

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

16 Citations (Scopus)

Abstract

Divertor tiles removed after the second JET ITER-Like Wall campaign 2013-2014 (ILW-2) were studied using Secondary Ion Mass Spectrometry (SIMS). Measurements show that the thickest beryllium (Be) dominated deposition layers are located at the upper part of the inner divertor and are up to ~40µm thick at the lower part of Tile 0 exposed in 2011-2014. The highest deuterium (D) amounts (>8 · 10¹⁸ at./cm²), in contrast, were found on the upper part of Tile 1 (2013-2014), where the Be deposits are ~10µm thick. D was mainly retained in the near-surface layer of the Be deposits but also deeper in tungsten (W) and molybdenum (Mo) layers of the marker coated tiles, especially at W-Mo layer interfaces. D retention for the ILW-2 divertor tiles is higher than for the first campaign 2011-2012 (ILW-1) and probable reasons for the difference are that SIMS measurements for the ILW-2 samples were done deeper than for the ILW-1 samples, some of the tiles were exposed during both ILW-1 and ILW-2 and therefore had a longer exposure time, and the differences between ILW-1 and ILW-2 campaigns e.g. in strike point distributions and injected powers.

Original language	English
Pages (from-to)	655-661
Journal	Nuclear Materials and Energy
Volume	12
DOIs	https://doi.org/10.1016/j.nme.2017.04.007
Publication status	Published - 1 Aug 2017
MoE publication type	A1 Journal article-refereed
Event	22nd International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI-22) - Rome, Italy Duration: 30 May 2016 → 3 Jun 2016

Funding

This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training program 2014–2018 under grant agreement No 633053.

Keywords

JET
fuel retention
erosion
deposition
Fuel retention
Deposition
Erosion

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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Cite this

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title = "Deuterium retention in the divertor tiles of JET ITER-Like wall",

abstract = "Divertor tiles removed after the second JET ITER-Like Wall campaign 2013-2014 (ILW-2) were studied using Secondary Ion Mass Spectrometry (SIMS). Measurements show that the thickest beryllium (Be) dominated deposition layers are located at the upper part of the inner divertor and are up to ~40µm thick at the lower part of Tile 0 exposed in 2011-2014. The highest deuterium (D) amounts (>8 · 1018 at./cm²), in contrast, were found on the upper part of Tile 1 (2013-2014), where the Be deposits are ~10µm thick. D was mainly retained in the near-surface layer of the Be deposits but also deeper in tungsten (W) and molybdenum (Mo) layers of the marker coated tiles, especially at W-Mo layer interfaces. D retention for the ILW-2 divertor tiles is higher than for the first campaign 2011-2012 (ILW-1) and probable reasons for the difference are that SIMS measurements for the ILW-2 samples were done deeper than for the ILW-1 samples, some of the tiles were exposed during both ILW-1 and ILW-2 and therefore had a longer exposure time, and the differences between ILW-1 and ILW-2 campaigns e.g. in strike point distributions and injected powers.",

keywords = "JET, fuel retention, erosion, deposition, Fuel retention, Deposition, Erosion",

author = "A. Lahtinen and Jari Likonen and Seppo Koivuranta and Antti Hakola and A. Heinola and C.F. Ayres and A. Baron-Wiechec and J.P. Coad and A. Widdowson and J. R{\"a}is{\"a}nen and {JET Contributors}",

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doi = "10.1016/j.nme.2017.04.007",

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T1 - Deuterium retention in the divertor tiles of JET ITER-Like wall

AU - Lahtinen, A.

AU - Likonen, Jari

AU - Koivuranta, Seppo

AU - Hakola, Antti

AU - Heinola, A.

AU - Ayres, C.F.

AU - Baron-Wiechec, A.

AU - Coad, J.P.

AU - Widdowson, A.

AU - Räisänen, J.

AU - JET Contributors

PY - 2017/8/1

Y1 - 2017/8/1

N2 - Divertor tiles removed after the second JET ITER-Like Wall campaign 2013-2014 (ILW-2) were studied using Secondary Ion Mass Spectrometry (SIMS). Measurements show that the thickest beryllium (Be) dominated deposition layers are located at the upper part of the inner divertor and are up to ~40µm thick at the lower part of Tile 0 exposed in 2011-2014. The highest deuterium (D) amounts (>8 · 1018 at./cm²), in contrast, were found on the upper part of Tile 1 (2013-2014), where the Be deposits are ~10µm thick. D was mainly retained in the near-surface layer of the Be deposits but also deeper in tungsten (W) and molybdenum (Mo) layers of the marker coated tiles, especially at W-Mo layer interfaces. D retention for the ILW-2 divertor tiles is higher than for the first campaign 2011-2012 (ILW-1) and probable reasons for the difference are that SIMS measurements for the ILW-2 samples were done deeper than for the ILW-1 samples, some of the tiles were exposed during both ILW-1 and ILW-2 and therefore had a longer exposure time, and the differences between ILW-1 and ILW-2 campaigns e.g. in strike point distributions and injected powers.

AB - Divertor tiles removed after the second JET ITER-Like Wall campaign 2013-2014 (ILW-2) were studied using Secondary Ion Mass Spectrometry (SIMS). Measurements show that the thickest beryllium (Be) dominated deposition layers are located at the upper part of the inner divertor and are up to ~40µm thick at the lower part of Tile 0 exposed in 2011-2014. The highest deuterium (D) amounts (>8 · 1018 at./cm²), in contrast, were found on the upper part of Tile 1 (2013-2014), where the Be deposits are ~10µm thick. D was mainly retained in the near-surface layer of the Be deposits but also deeper in tungsten (W) and molybdenum (Mo) layers of the marker coated tiles, especially at W-Mo layer interfaces. D retention for the ILW-2 divertor tiles is higher than for the first campaign 2011-2012 (ILW-1) and probable reasons for the difference are that SIMS measurements for the ILW-2 samples were done deeper than for the ILW-1 samples, some of the tiles were exposed during both ILW-1 and ILW-2 and therefore had a longer exposure time, and the differences between ILW-1 and ILW-2 campaigns e.g. in strike point distributions and injected powers.

KW - JET

KW - fuel retention

KW - erosion

KW - deposition

KW - Fuel retention

KW - Deposition

KW - Erosion

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JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

T2 - 22nd International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI-22)

Y2 - 30 May 2016 through 3 June 2016

ER -

Deuterium retention in the divertor tiles of JET ITER-Like wall

Abstract

Funding

Keywords

UN SDGs

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