Investigation of deuterium trapping and release in the JET ITER-like wall divertor using TDS and TMAP

Jari Likonen; K. Heinola; A. De Backer; A. Baron-Wiechec; N. Catarino; I. Jepu; C. F. Ayres; P. Coad; Seppo Koivuranta; S. Krat; G. F. Matthews; M. Mayer; A. Widdowson; JET Contributors

doi:10.1016/j.nme.2019.02.031

Investigation of deuterium trapping and release in the JET ITER-like wall divertor using TDS and TMAP

Jari Likonen^*
, K. Heinola
, A. De Backer
, A. Baron-Wiechec
, N. Catarino
, I. Jepu
, C. F. Ayres
, P. Coad
, Seppo Koivuranta
, S. Krat
, G. F. Matthews
, M. Mayer
, A. Widdowson
, JET Contributors

^*Corresponding author for this work

University of Helsinki
Culham Science Centre
Universidade de Lisboa
National Institute for Lasers, Plasma and Radiation Physics (INFLPR)
Max-Planck-Institut für Plasmaphysik (IPP)
National Research Nuclear University (MEPhI)

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

25 Citations (Scopus)

Abstract

Selected set of samples from JET ITER-Like Wall (JET-ILW) divertor tiles exposed both in 2013–2014 and 2011–2014 has been analysed using Thermal Desorption Spectrometry (TDS). The deuterium (D) amounts obtained with TDS were compared with Ion Beam Analysis (IBA) and Secondary Ion Mass Spectrometry (SIMS) data. The highest amount of D was found on the top part of inner divertor which has regions with the thickest deposited layers. This area resides deep in the scrape-off layer. Changes in plasma configurations between the first (2011–2012) and the second (2013–2014) JET-ILW campaign altered the material migration towards the inner and the outer divertor corner increasing the amount of deposition in the shadowed areas of the divertor base tiles. D retention on the outer divertor tiles is clearly smaller than on the inner divertor tiles. Experimental TDS spectra for samples from the top part of inner divertor and from the outer strike point region were modelled using TMAP program. Experimental deuterium profiles obtained with SIMS have been used and the detrapping and the activation energies have been adjusted. Analysis of the results of the TMAP simulations enabled to determine the nature of traps in different samples.

Original language	English
Pages (from-to)	166-178
Journal	Nuclear Materials and Energy
Volume	19
DOIs	https://doi.org/10.1016/j.nme.2019.02.031
Publication status	Published - 1 May 2019
MoE publication type	Not Eligible

Funding

This project has received funding from Tekes – Finnish Funding Agency for Technology and Innovation (under grant 4433/31/2015) – and the European Union's Horizon 2020 research and innovation programme. 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.

UN SDGs

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

SDG 7 Affordable and Clean Energy

Keywords

Fuel retention
JET
TDS

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10.1016/j.nme.2019.02.031Licence: CC BY-NC-ND

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Likonen, J., Heinola, K., De Backer, A., Baron-Wiechec, A., Catarino, N., Jepu, I., Ayres, C. F., Coad, P., Koivuranta, S., Krat, S., Matthews, G. F., Mayer, M., Widdowson, A., & JET Contributors (2019). Investigation of deuterium trapping and release in the JET ITER-like wall divertor using TDS and TMAP. Nuclear Materials and Energy, 19, 166-178. https://doi.org/10.1016/j.nme.2019.02.031

@article{2f21a0366aa14a43893c8eb502ec5189,

title = "Investigation of deuterium trapping and release in the JET ITER-like wall divertor using TDS and TMAP",

abstract = "Selected set of samples from JET ITER-Like Wall (JET-ILW) divertor tiles exposed both in 2013–2014 and 2011–2014 has been analysed using Thermal Desorption Spectrometry (TDS). The deuterium (D) amounts obtained with TDS were compared with Ion Beam Analysis (IBA) and Secondary Ion Mass Spectrometry (SIMS) data. The highest amount of D was found on the top part of inner divertor which has regions with the thickest deposited layers. This area resides deep in the scrape-off layer. Changes in plasma configurations between the first (2011–2012) and the second (2013–2014) JET-ILW campaign altered the material migration towards the inner and the outer divertor corner increasing the amount of deposition in the shadowed areas of the divertor base tiles. D retention on the outer divertor tiles is clearly smaller than on the inner divertor tiles. Experimental TDS spectra for samples from the top part of inner divertor and from the outer strike point region were modelled using TMAP program. Experimental deuterium profiles obtained with SIMS have been used and the detrapping and the activation energies have been adjusted. Analysis of the results of the TMAP simulations enabled to determine the nature of traps in different samples.",

keywords = "Fuel retention, JET, TDS",

author = "Jari Likonen and K. Heinola and \{De Backer\}, A. and A. Baron-Wiechec and N. Catarino and I. Jepu and Ayres, \{C. F.\} and P. Coad and Seppo Koivuranta and S. Krat and Matthews, \{G. F.\} and M. Mayer and A. Widdowson and \{JET Contributors\}",

note = "Publisher Copyright: {\textcopyright} 2019 The Authors",

year = "2019",

month = may,

day = "1",

doi = "10.1016/j.nme.2019.02.031",

language = "English",

volume = "19",

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journal = "Nuclear Materials and Energy",

issn = "2352-1791",

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Likonen, J, Heinola, K, De Backer, A, Baron-Wiechec, A, Catarino, N, Jepu, I, Ayres, CF, Coad, P, Koivuranta, S, Krat, S, Matthews, GF, Mayer, M, Widdowson, A & JET Contributors 2019, 'Investigation of deuterium trapping and release in the JET ITER-like wall divertor using TDS and TMAP', Nuclear Materials and Energy, vol. 19, pp. 166-178. https://doi.org/10.1016/j.nme.2019.02.031

TY - JOUR

T1 - Investigation of deuterium trapping and release in the JET ITER-like wall divertor using TDS and TMAP

AU - Likonen, Jari

AU - Heinola, K.

AU - De Backer, A.

AU - Baron-Wiechec, A.

AU - Catarino, N.

AU - Jepu, I.

AU - Ayres, C. F.

AU - Coad, P.

AU - Koivuranta, Seppo

AU - Krat, S.

AU - Matthews, G. F.

AU - Mayer, M.

AU - Widdowson, A.

AU - JET Contributors

PY - 2019/5/1

Y1 - 2019/5/1

N2 - Selected set of samples from JET ITER-Like Wall (JET-ILW) divertor tiles exposed both in 2013–2014 and 2011–2014 has been analysed using Thermal Desorption Spectrometry (TDS). The deuterium (D) amounts obtained with TDS were compared with Ion Beam Analysis (IBA) and Secondary Ion Mass Spectrometry (SIMS) data. The highest amount of D was found on the top part of inner divertor which has regions with the thickest deposited layers. This area resides deep in the scrape-off layer. Changes in plasma configurations between the first (2011–2012) and the second (2013–2014) JET-ILW campaign altered the material migration towards the inner and the outer divertor corner increasing the amount of deposition in the shadowed areas of the divertor base tiles. D retention on the outer divertor tiles is clearly smaller than on the inner divertor tiles. Experimental TDS spectra for samples from the top part of inner divertor and from the outer strike point region were modelled using TMAP program. Experimental deuterium profiles obtained with SIMS have been used and the detrapping and the activation energies have been adjusted. Analysis of the results of the TMAP simulations enabled to determine the nature of traps in different samples.

AB - Selected set of samples from JET ITER-Like Wall (JET-ILW) divertor tiles exposed both in 2013–2014 and 2011–2014 has been analysed using Thermal Desorption Spectrometry (TDS). The deuterium (D) amounts obtained with TDS were compared with Ion Beam Analysis (IBA) and Secondary Ion Mass Spectrometry (SIMS) data. The highest amount of D was found on the top part of inner divertor which has regions with the thickest deposited layers. This area resides deep in the scrape-off layer. Changes in plasma configurations between the first (2011–2012) and the second (2013–2014) JET-ILW campaign altered the material migration towards the inner and the outer divertor corner increasing the amount of deposition in the shadowed areas of the divertor base tiles. D retention on the outer divertor tiles is clearly smaller than on the inner divertor tiles. Experimental TDS spectra for samples from the top part of inner divertor and from the outer strike point region were modelled using TMAP program. Experimental deuterium profiles obtained with SIMS have been used and the detrapping and the activation energies have been adjusted. Analysis of the results of the TMAP simulations enabled to determine the nature of traps in different samples.

KW - Fuel retention

KW - JET

KW - TDS

UR - https://www.scopus.com/pages/publications/85062280297

U2 - 10.1016/j.nme.2019.02.031

DO - 10.1016/j.nme.2019.02.031

M3 - Article

AN - SCOPUS:85062280297

SN - 2352-1791

VL - 19

SP - 166

EP - 178

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

ER -

Investigation of deuterium trapping and release in the JET ITER-like wall divertor using TDS and TMAP

Abstract

Funding

UN SDGs

Keywords

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