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; S. Koivuranta; S. Krat; A. Lahtinen; J. 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, S. Koivuranta, S. Krat, A. Lahtinen, J. Likonen, M. Mayer, P. Petersson, M. Rubel, S. Van Boxel

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

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
Number of pages	7
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

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Keywords

deposition
dust
erosion
fuel retention
jet
tungsten coating

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

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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, S.; Krat, S.; Lahtinen, A.; Likonen, J.; 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, S.

AU - Krat, S.

AU - Lahtinen, A.

AU - Likonen, J.

AU - Mayer, M.

AU - Petersson, P.

AU - Rubel, M.

AU - Van Boxel, S.

PY - 2017/8/1

Y1 - 2017/8/1

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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

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Access to Document

10.1016/j.nme.2016.12.008

Link to publication in Scopus