Experience on divertor fuel retention after two ITER-Like Wall campaigns

K. Heinola; A. Widdowson; Jari Likonen; T. Ahlgren; E. Alves; C.F. Ayres; A. Baron-Wiechec; N. Barradas; S. Brezinsek; N. Catarino; P. Coad; C. Guillemaut; I. Jepu; S. Krat; A. Lahtinen; G.F. Matthews; M. Mayer

doi:10.1088/1402-4896/aa9283

Experience on divertor fuel retention after two ITER-Like Wall campaigns

K. Heinola (Corresponding Author), A. Widdowson, Jari Likonen, T. Ahlgren, E. Alves, C.F. Ayres, A. Baron-Wiechec, N. Barradas, S. Brezinsek, N. Catarino, P. Coad, C. Guillemaut, I. Jepu, S. Krat, A. Lahtinen, G.F. Matthews, M. Mayer

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

22 Citations (Scopus)

Abstract

The JET ITER-Like Wall experiment, with its all-metal plasma-facing components, provides a unique environment for plasma and plasma-wall interaction studies. These studies are of great importance in understanding the underlying phenomena taking place during the operation of a future fusion reactor. Present work summarizes and reports the plasma fuel retention in the divertor resulting from the two first experimental campaigns with the ITER-Like Wall. The deposition pattern in the divertor after the second campaign shows same trend as was observed after the first campaign: highest deposition of 10-15 μm was found on the top part of the inner divertor. Due to the change in plasma magnetic configurations from the first to the second campaign, and the resulted strike point locations, an increase of deposition was observed on the base of the divertor. The deuterium retention was found to be affected by the hydrogen plasma experiments done at the end of second experimental campaign.

Original language	English
Number of pages	8
Journal	Physica Scripta
Issue number	T170
DOIs	https://doi.org/10.1088/1402-4896/aa9283
Publication status	Published - 2017
MoE publication type	A4 Article in a conference publication

Keywords

fusion reactor materials
fusion products effects
plasma-based ion implantations and deposition
fuel retention
deposition

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10.1088/1402-4896/aa9283

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Heinola, K., Widdowson, A., Likonen, J., Ahlgren, T., Alves, E., Ayres, C. F., Baron-Wiechec, A., Barradas, N., Brezinsek, S., Catarino, N., Coad, P., Guillemaut, C., Jepu, I., Krat, S., Lahtinen, A., Matthews, G. F., & Mayer, M. (2017). Experience on divertor fuel retention after two ITER-Like Wall campaigns. Physica Scripta, (T170). https://doi.org/10.1088/1402-4896/aa9283

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title = "Experience on divertor fuel retention after two ITER-Like Wall campaigns",

abstract = "The JET ITER-Like Wall experiment, with its all-metal plasma-facing components, provides a unique environment for plasma and plasma-wall interaction studies. These studies are of great importance in understanding the underlying phenomena taking place during the operation of a future fusion reactor. Present work summarizes and reports the plasma fuel retention in the divertor resulting from the two first experimental campaigns with the ITER-Like Wall. The deposition pattern in the divertor after the second campaign shows same trend as was observed after the first campaign: highest deposition of 10-15 μm was found on the top part of the inner divertor. Due to the change in plasma magnetic configurations from the first to the second campaign, and the resulted strike point locations, an increase of deposition was observed on the base of the divertor. The deuterium retention was found to be affected by the hydrogen plasma experiments done at the end of second experimental campaign.",

keywords = "fusion reactor materials, fusion products effects, plasma-based ion implantations and deposition, fuel retention, deposition",

author = "K. Heinola and A. Widdowson and Jari Likonen and T. Ahlgren and E. Alves and C.F. Ayres and A. Baron-Wiechec and N. Barradas and S. Brezinsek and N. Catarino and P. Coad and C. Guillemaut and I. Jepu and S. Krat and A. Lahtinen and G.F. Matthews and M. Mayer",

note = "Project code: 114280 Funding Information: This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 under grant agreement No. 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. Publisher Copyright: {\textcopyright} 2017 University of Helsinki. Copyright: Copyright 2020 Elsevier B.V., All rights reserved.",

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doi = "10.1088/1402-4896/aa9283",

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T1 - Experience on divertor fuel retention after two ITER-Like Wall campaigns

AU - Heinola, K.

AU - Widdowson, A.

AU - Likonen, Jari

AU - Ahlgren, T.

AU - Alves, E.

AU - Ayres, C.F.

AU - Baron-Wiechec, A.

AU - Barradas, N.

AU - Brezinsek, S.

AU - Catarino, N.

AU - Coad, P.

AU - Guillemaut, C.

AU - Jepu, I.

AU - Krat, S.

AU - Lahtinen, A.

AU - Matthews, G.F.

AU - Mayer, M.

N1 - Project code: 114280 Funding Information: This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014–2018 under grant agreement No. 633053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. Publisher Copyright: © 2017 University of Helsinki. Copyright: Copyright 2020 Elsevier B.V., All rights reserved.

PY - 2017

Y1 - 2017

N2 - The JET ITER-Like Wall experiment, with its all-metal plasma-facing components, provides a unique environment for plasma and plasma-wall interaction studies. These studies are of great importance in understanding the underlying phenomena taking place during the operation of a future fusion reactor. Present work summarizes and reports the plasma fuel retention in the divertor resulting from the two first experimental campaigns with the ITER-Like Wall. The deposition pattern in the divertor after the second campaign shows same trend as was observed after the first campaign: highest deposition of 10-15 μm was found on the top part of the inner divertor. Due to the change in plasma magnetic configurations from the first to the second campaign, and the resulted strike point locations, an increase of deposition was observed on the base of the divertor. The deuterium retention was found to be affected by the hydrogen plasma experiments done at the end of second experimental campaign.

AB - The JET ITER-Like Wall experiment, with its all-metal plasma-facing components, provides a unique environment for plasma and plasma-wall interaction studies. These studies are of great importance in understanding the underlying phenomena taking place during the operation of a future fusion reactor. Present work summarizes and reports the plasma fuel retention in the divertor resulting from the two first experimental campaigns with the ITER-Like Wall. The deposition pattern in the divertor after the second campaign shows same trend as was observed after the first campaign: highest deposition of 10-15 μm was found on the top part of the inner divertor. Due to the change in plasma magnetic configurations from the first to the second campaign, and the resulted strike point locations, an increase of deposition was observed on the base of the divertor. The deuterium retention was found to be affected by the hydrogen plasma experiments done at the end of second experimental campaign.

KW - fusion reactor materials

KW - fusion products effects

KW - plasma-based ion implantations and deposition

KW - fuel retention

KW - deposition

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U2 - 10.1088/1402-4896/aa9283

DO - 10.1088/1402-4896/aa9283

M3 - Article in a proceedings journal

JO - Physica Scripta

JF - Physica Scripta

SN - 0031-8949

IS - T170

ER -

Experience on divertor fuel retention after two ITER-Like Wall campaigns

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Keywords

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