Erosion of tungsten and carbon markers in the outer divertor of ASDEX-Upgrade

M. Mayer, V. Rohde, G. Ramos, Elizaveta Vainonen-Ahlgren, Jari Likonen, J.L. Chen

Research output: Contribution to journalArticleScientificpeer-review

27 Citations (Scopus)

Abstract

The erosion of tungsten and carbon marker layers was studied in the outer divertor of ASDEX Upgrade. The outer strike point area and a large fraction of the outer baffle are net erosion areas for both materials.
The net erosion rate of carbon is about 10–20 times larger than the net erosion rate of tungsten.
The erosion is strongly inhomogeneous due to surface roughness, with a large erosion on plasma exposed areas of the rough surfaces, and deposition in recessions and pores.
Original languageEnglish
Pages (from-to)106-110
JournalPhysica Scripta
Volume2007
Issue numberT128
DOIs
Publication statusPublished - 2007
MoE publication typeA1 Journal article-refereed

Fingerprint

Erosion
markers
erosion
Carbon
tungsten
carbon
Baffle
recession
baffles
Rough Surface
Surface Roughness
surface roughness
Plasma
porosity

Keywords

  • JET
  • plasma
  • fusion energy
  • fusion reactors
  • ITER
  • plasma toroidal confinement
  • divertor tiles
  • tungsten
  • plasma-wall interactions

Cite this

Mayer, M., Rohde, V., Ramos, G., Vainonen-Ahlgren, E., Likonen, J., & Chen, J. L. (2007). Erosion of tungsten and carbon markers in the outer divertor of ASDEX-Upgrade. Physica Scripta, 2007(T128), 106-110. https://doi.org/10.1088/0031-8949/2007/T128/021
Mayer, M. ; Rohde, V. ; Ramos, G. ; Vainonen-Ahlgren, Elizaveta ; Likonen, Jari ; Chen, J.L. / Erosion of tungsten and carbon markers in the outer divertor of ASDEX-Upgrade. In: Physica Scripta. 2007 ; Vol. 2007, No. T128. pp. 106-110.
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abstract = "The erosion of tungsten and carbon marker layers was studied in the outer divertor of ASDEX Upgrade. The outer strike point area and a large fraction of the outer baffle are net erosion areas for both materials. The net erosion rate of carbon is about 10–20 times larger than the net erosion rate of tungsten. The erosion is strongly inhomogeneous due to surface roughness, with a large erosion on plasma exposed areas of the rough surfaces, and deposition in recessions and pores.",
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Mayer, M, Rohde, V, Ramos, G, Vainonen-Ahlgren, E, Likonen, J & Chen, JL 2007, 'Erosion of tungsten and carbon markers in the outer divertor of ASDEX-Upgrade', Physica Scripta, vol. 2007, no. T128, pp. 106-110. https://doi.org/10.1088/0031-8949/2007/T128/021

Erosion of tungsten and carbon markers in the outer divertor of ASDEX-Upgrade. / Mayer, M.; Rohde, V.; Ramos, G.; Vainonen-Ahlgren, Elizaveta; Likonen, Jari; Chen, J.L.

In: Physica Scripta, Vol. 2007, No. T128, 2007, p. 106-110.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Erosion of tungsten and carbon markers in the outer divertor of ASDEX-Upgrade

AU - Mayer, M.

AU - Rohde, V.

AU - Ramos, G.

AU - Vainonen-Ahlgren, Elizaveta

AU - Likonen, Jari

AU - Chen, J.L.

PY - 2007

Y1 - 2007

N2 - The erosion of tungsten and carbon marker layers was studied in the outer divertor of ASDEX Upgrade. The outer strike point area and a large fraction of the outer baffle are net erosion areas for both materials. The net erosion rate of carbon is about 10–20 times larger than the net erosion rate of tungsten. The erosion is strongly inhomogeneous due to surface roughness, with a large erosion on plasma exposed areas of the rough surfaces, and deposition in recessions and pores.

AB - The erosion of tungsten and carbon marker layers was studied in the outer divertor of ASDEX Upgrade. The outer strike point area and a large fraction of the outer baffle are net erosion areas for both materials. The net erosion rate of carbon is about 10–20 times larger than the net erosion rate of tungsten. The erosion is strongly inhomogeneous due to surface roughness, with a large erosion on plasma exposed areas of the rough surfaces, and deposition in recessions and pores.

KW - JET

KW - plasma

KW - fusion energy

KW - fusion reactors

KW - ITER

KW - plasma toroidal confinement

KW - divertor tiles

KW - tungsten

KW - plasma-wall interactions

U2 - 10.1088/0031-8949/2007/T128/021

DO - 10.1088/0031-8949/2007/T128/021

M3 - Article

VL - 2007

SP - 106

EP - 110

JO - Physica Scripta

JF - Physica Scripta

SN - 0031-8949

IS - T128

ER -