Erosion of tungsten marker layers in W7-X

Mayer, M; Balden, M; Brezinsek, S.; Dhard, c; Elgeti, S; Fajardo, D; Fellinger, Joris; Corominas, M Guitart; Hiret, P; Kandler, M; Loesser, Douglas; Lumsdaine, Arnold; Naujoks, d; Neilson, G.; Neu, Rudolf; Oelmann, J.; Ruset, C; Schmidt-Dencker, J-H

doi:10.1088/1402-4896/ac3b68

Erosion of tungsten marker layers in W7-X

Conference · 01 December 2021 · Physica Scripta

DOI:https://doi.org/10.1088/1402-4896/ac3b68· OSTI ID:1833922

Mayer, M ^[1]; Balden, M ^[1]; Brezinsek, S. ^[2]; Dhard, c ^[3]; Elgeti, S ^[1]; Fajardo, D ^[1]; Fellinger, Joris ^[4]; Corominas, M Guitart ^[1]; Hiret, P ^[1]; Kandler, M ^[1]; Loesser, Douglas ^[5]; ^[6]; Naujoks, d ^[3]; Neilson, G. ^[5]; Neu, Rudolf ^[7]; Oelmann, J. ^[8]; Ruset, C ^[9]; Schmidt-Dencker, J-H ^[1]

Max Planck Institute for Plasma Physics, Garching, Germany
Forschungszentrum Julich, Germany
Max Planck Institute of Plasma Physics, Greifswald, Germany
Max-Planck-Institut fur Plasmaphysik, Griefswald, Germany
Princeton Plasma Physics Laboratory (PPPL)
ORNL
EURATOM / IPP Garching, Germany
Forschungszentrum Jülich GmbH
National Institute for Laser, Plasma and Radiation Physics, Bucharest, Romania

In order to get first insight into net tungsten erosion in W7-X, tungsten (W) marker layers were exposed during the operational phase OP 1.2b at one position of the Test Divertor Unit (TDU), at 21 different positions of the inner heat shield, and at two scraper elements. The maximum tungsten erosion rate at the TDU strike line was 0.13 nm s^-1 averaged over the whole campaign. The erosion was inhomogeneous on a microscopic scale, with higher erosion on ridges of the rough surface inclined towards the plasma and deposition of hydrocarbon layers in the recessed areas of the rough surface. The W erosion at the inner heat shield was below the detection limit of 3–6 × 10¹² W-atoms/cm²s, and all inner heat shield tiles were covered with a thin B/C/O layer with thickness in the range 2 × 10¹⁷–10¹⁸ B + C atoms/cm² (about 20–100 nm B + C). W-erosion of the marker layers on the scraper elements was also below the detection limit.

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Research Organization:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Science (SC)

DOE Contract Number:: AC05-00OR22725

OSTI ID:: 1833922

Journal Information:: Physica Scripta, Vol. 96, Issue 12; Conference: 18th International Conference on Plasma-Facing Materials and Components for Fusion Applications (PFMC) - Virtual, Tennessee, United States of America - 5/17/2021 8:00:00 AM-5/21/2021 8:00:00 AM; ISSN 0031-8949

Publisher:: IOP Publishing

Country of Publication:: United States

Language:: English

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