Overview of the JET ITER-like wall divertor

A. Widdowson; E. Alves; A. Baron-Wiechec; N.P. Barradas; N. Catarino; J.P. Coad; V. Corregidor; A. Garcia-Carrasco; K. Heinola; Seppo Koivuranta; S. Krat; A. Lahtinen; Jari Likonen; M. Mayer; P. Petersson; M. Rubel; S. Van Boxel

doi:10.1016/j.nme.2016.12.008

Overview of the JET ITER-like wall divertor

A. Widdowson, E. Alves, A. Baron-Wiechec, N.P. Barradas, N. Catarino, J.P. Coad, V. Corregidor, A. Garcia-Carrasco, K. Heinola, Seppo Koivuranta, S. Krat, A. Lahtinen, Jari Likonen, M. Mayer, P. Petersson, M. Rubel, S. Van Boxel

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

32 Citations (Scopus)

Abstract

The work presented draws on new analysis of components removed following the second JET ITER-like wall campaign 2013-14 concentrating on the upper inner divertor, inner and outer divertor corners, lifetime issues relating to tungsten coatings on JET carbon fibre composite divertor tiles and dust/particulate generation. The results show that the upper inner divertor remains the region of highest deposition in the JET-ILW. Variations in plasma configurations between the first and second campaign have altered material migration to the corners of the inner and outer divertor. Net deposition is shown to be beneficial in the sense that it reduces W coating erosion, covers small areas of exposed carbon surfaces and even encapsulates particles.

Original language	English
Pages (from-to)	499-505
Journal	Nuclear Materials and Energy
Volume	12
Early online date	2017
DOIs	https://doi.org/10.1016/j.nme.2016.12.008
Publication status	Published - 1 Aug 2017
MoE publication type	A1 Journal article-refereed

Keywords

deposition
dust
erosion
fuel retention
jet
tungsten coating

Access to Document

10.1016/j.nme.2016.12.008Licence: CC BY-NC-ND

Cite this

Widdowson, A., Alves, E., Baron-Wiechec, A., Barradas, N. P., Catarino, N., Coad, J. P., Corregidor, V., Garcia-Carrasco, A., Heinola, K., Koivuranta, S., Krat, S., Lahtinen, A., Likonen, J., Mayer, M., Petersson, P., Rubel, M., & Van Boxel, S. (2017). Overview of the JET ITER-like wall divertor. Nuclear Materials and Energy, 12, 499-505. https://doi.org/10.1016/j.nme.2016.12.008

Widdowson, A. ; Alves, E. ; Baron-Wiechec, A. ; Barradas, N.P. ; Catarino, N. ; Coad, J.P. ; Corregidor, V. ; Garcia-Carrasco, A. ; Heinola, K. ; Koivuranta, Seppo ; Krat, S. ; Lahtinen, A. ; Likonen, Jari ; Mayer, M. ; Petersson, P. ; Rubel, M. ; Van Boxel, S. / Overview of the JET ITER-like wall divertor. In: Nuclear Materials and Energy. 2017 ; Vol. 12. pp. 499-505.

@article{f8ed4a5d3c9e4c10a922af433d64985f,

title = "Overview of the JET ITER-like wall divertor",

abstract = "The work presented draws on new analysis of components removed following the second JET ITER-like wall campaign 2013-14 concentrating on the upper inner divertor, inner and outer divertor corners, lifetime issues relating to tungsten coatings on JET carbon fibre composite divertor tiles and dust/particulate generation. The results show that the upper inner divertor remains the region of highest deposition in the JET-ILW. Variations in plasma configurations between the first and second campaign have altered material migration to the corners of the inner and outer divertor. Net deposition is shown to be beneficial in the sense that it reduces W coating erosion, covers small areas of exposed carbon surfaces and even encapsulates particles.",

keywords = "deposition, dust, erosion, fuel retention, jet, tungsten coating",

author = "A. Widdowson and E. Alves and A. Baron-Wiechec and N.P. Barradas and N. Catarino and J.P. Coad and V. Corregidor and A. Garcia-Carrasco and K. Heinola and Seppo Koivuranta and S. Krat and A. Lahtinen and Jari Likonen and M. Mayer and P. Petersson and M. Rubel and {Van Boxel}, S.",

note = "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. This work was also part-funded by the RCUK Energy Programme under grant EP/I501045. 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. This work was also part-funded by the RCUK Energy Programme under grant EP/I501045. Publisher Copyright: {\textcopyright} 2017 Elsevier Ltd Copyright: Copyright 2020 Elsevier B.V., All rights reserved.",

year = "2017",

month = aug,

day = "1",

doi = "10.1016/j.nme.2016.12.008",

language = "English",

volume = "12",

pages = "499--505",

journal = "Nuclear Materials and Energy",

issn = "2352-1791",

publisher = "Elsevier",

}

Overview of the JET ITER-like wall divertor. / Widdowson, A.; Alves, E.; Baron-Wiechec, A.; Barradas, N.P.; Catarino, N.; Coad, J.P.; Corregidor, V.; Garcia-Carrasco, A.; Heinola, K.; Koivuranta, Seppo; Krat, S.; Lahtinen, A.; Likonen, Jari; Mayer, M.; Petersson, P.; Rubel, M.; Van Boxel, S.

In: Nuclear Materials and Energy, Vol. 12, 01.08.2017, p. 499-505.

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

TY - JOUR

T1 - Overview of the JET ITER-like wall divertor

AU - Widdowson, A.

AU - Alves, E.

AU - Baron-Wiechec, A.

AU - Barradas, N.P.

AU - Catarino, N.

AU - Coad, J.P.

AU - Corregidor, V.

AU - Garcia-Carrasco, A.

AU - Heinola, K.

AU - Koivuranta, Seppo

AU - Krat, S.

AU - Lahtinen, A.

AU - Likonen, Jari

AU - Mayer, M.

AU - Petersson, P.

AU - Rubel, M.

AU - Van Boxel, S.

N1 - 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. This work was also part-funded by the RCUK Energy Programme under grant EP/I501045. 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. This work was also part-funded by the RCUK Energy Programme under grant EP/I501045. Publisher Copyright: © 2017 Elsevier Ltd Copyright: Copyright 2020 Elsevier B.V., All rights reserved.

PY - 2017/8/1

Y1 - 2017/8/1

N2 - The work presented draws on new analysis of components removed following the second JET ITER-like wall campaign 2013-14 concentrating on the upper inner divertor, inner and outer divertor corners, lifetime issues relating to tungsten coatings on JET carbon fibre composite divertor tiles and dust/particulate generation. The results show that the upper inner divertor remains the region of highest deposition in the JET-ILW. Variations in plasma configurations between the first and second campaign have altered material migration to the corners of the inner and outer divertor. Net deposition is shown to be beneficial in the sense that it reduces W coating erosion, covers small areas of exposed carbon surfaces and even encapsulates particles.

AB - The work presented draws on new analysis of components removed following the second JET ITER-like wall campaign 2013-14 concentrating on the upper inner divertor, inner and outer divertor corners, lifetime issues relating to tungsten coatings on JET carbon fibre composite divertor tiles and dust/particulate generation. The results show that the upper inner divertor remains the region of highest deposition in the JET-ILW. Variations in plasma configurations between the first and second campaign have altered material migration to the corners of the inner and outer divertor. Net deposition is shown to be beneficial in the sense that it reduces W coating erosion, covers small areas of exposed carbon surfaces and even encapsulates particles.

KW - deposition

KW - dust

KW - erosion

KW - fuel retention

KW - jet

KW - tungsten coating

UR - http://www.scopus.com/inward/record.url?scp=85012897195&partnerID=8YFLogxK

U2 - 10.1016/j.nme.2016.12.008

DO - 10.1016/j.nme.2016.12.008

M3 - Article

VL - 12

SP - 499

EP - 505

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

SN - 2352-1791

ER -

Overview of the JET ITER-like wall divertor

Abstract

Keywords

Access to Document

Other files and links

Fingerprint

Cite this