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 · Wed Dec 01 04:00:00 EST 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.

View Conference

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

Sponsoring Organization:: USDOE; USDOE Office of Science (SC)

DOE Contract Number:: AC05-00OR22725

OSTI ID:: 1833922

Conference Information:: Journal Name: Physica Scripta Journal Issue: 12 Journal Volume: 96

Country of Publication:: United States

Language:: English

References (40)

Erosion and redeposition patterns on entire erosion marker tiles after exposure in the first operation phase of WEST Balden, M.; Mayer, M.; Bliewert, B. Physica Scripta, Vol. 96, Issue 12 https://doi.org/10.1088/1402-4896/ac2182	journal	September 2021
Final integration, commissioning and start of the Wendelstein 7-X stellarator operation Bosch, H. -S.; Brakel, R.; Braeuer, T. Nuclear Fusion, Vol. 57, Issue 11 https://doi.org/10.1088/1741-4326/aa7cbb	journal	August 2017
Major results from the first plasma campaign of the Wendelstein 7-X stellarator Wolf, R. C.; Ali, A.; Alonso, A. Nuclear Fusion, Vol. 57, Issue 10 https://doi.org/10.1088/1741-4326/aa770d	journal	July 2017
Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X Sunn Pedersen, Thomas Nuclear Fusion https://doi.org/10.1088/1741-4326/ac2cf5	journal	October 2021
Hydrogen content in divertor baffle tiles in Wendelstein 7-X Oelmann, Jannis; Wüst, Erik; Brezinsek, Sebastijan Nuclear Materials and Energy, Vol. 26 https://doi.org/10.1016/j.nme.2021.100943	journal	March 2021
Progress in the design and development of a test divertor (TDU) for the start of W7-X operation Peacock, A.; Greuner, H.; Hurd, F. Fusion Engineering and Design, Vol. 84, Issue 7-11 https://doi.org/10.1016/j.fusengdes.2009.01.053	journal	June 2009
Impact of boronizations on impurity sources and performance in Wendelstein 7-X Sereda, S.; Brezinsek, S.; Wang, E. Nuclear Fusion, Vol. 60, Issue 8 https://doi.org/10.1088/1741-4326/ab937b	journal	July 2020
Physics and Engineering Design for Wendelstein VII-X Beidler, Craig; Grieger, Günter; Herrnegger, Franz Fusion Technology, Vol. 17, Issue 1 https://doi.org/10.13182/FST90-A29178	journal	January 1990
Industrial scale 10μmW coating of CFC tiles for ITER-like Wall Project at JET Ruset, C.; Grigore, E.; Munteanu, I. Fusion Engineering and Design, Vol. 84, Issue 7-11 https://doi.org/10.1016/j.fusengdes.2008.11.053	journal	June 2009
Srim-2003 Ziegler, James F. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 219-220 https://doi.org/10.1016/j.nimb.2004.01.208	journal	June 2004
Materials for the plasma-facing components of fusion reactors Bolt, H.; Barabash, V.; Krauss, W. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.005	journal	August 2004
Spectroscopic measurements of tungsten erosion in the ASDEX Upgrade divertor Thoma, A.; Asmussen, K.; Dux, R. Plasma Physics and Controlled Fusion, Vol. 39, Issue 9 https://doi.org/10.1088/0741-3335/39/9/014	journal	September 1997
Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade Dux, R.; Bobkov, V.; Herrmann, A. Journal of Nuclear Materials, Vol. 390-391 https://doi.org/10.1016/j.jnucmat.2009.01.225	journal	June 2009
Key results from the first plasma operation phase and outlook for future performance in Wendelstein 7-X Sunn Pedersen, Thomas; Dinklage, Andreas; Turkin, Yuriy Physics of Plasmas, Vol. 24, Issue 5 https://doi.org/10.1063/1.4983629	journal	May 2017
Investigation of 3D effects on heat fluxes in performance-optimized island divertor configurations at Wendelstein 7-X Effenberg, F.; Niemann, H.; Feng, Y. Nuclear Materials and Energy, Vol. 18 https://doi.org/10.1016/j.nme.2019.01.006	journal	January 2019
Methods for quantitative study of divertor heat loads on W7-X Gao, Y.; Jakubowski, Marcin W.; Drewelow, Peter Nuclear Fusion, Vol. 59, Issue 6 https://doi.org/10.1088/1741-4326/ab0f49	journal	April 2019
JET ITER-like wall—overview and experimental programme Matthews, G. F.; Beurskens, M.; Brezinsek, S. Physica Scripta, Vol. T145 https://doi.org/10.1088/0031-8949/2011/T145/014001	journal	December 2011
Improved physics in SIMNRA 7 Mayer, M. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 332 https://doi.org/10.1016/j.nimb.2014.02.056	journal	August 2014
Erosion of tungsten and carbon markers in the outer divertor of ASDEX-Upgrade Mayer, M.; Rohde, V.; Ramos, G. Physica Scripta, Vol. T128 https://doi.org/10.1088/0031-8949/2007/T128/021	journal	March 2007
Major results from the stellarator Wendelstein 7-AS Hirsch, M.; Baldzuhn, J.; Beidler, C. Plasma Physics and Controlled Fusion, Vol. 50, Issue 5 https://doi.org/10.1088/0741-3335/50/5/053001	journal	March 2008
Plasma-wall interaction studies in W7-X: main results from the recent divertor operations Dhard, C. P.; Brezinsek, S.; Mayer, M. Physica Scripta, Vol. 96, Issue 12 https://doi.org/10.1088/1402-4896/ac35c0	journal	November 2021
Erosion, screening, and migration of tungsten in the JET divertor Brezinsek, S.; Kirschner, A.; Mayer, M. Nuclear Fusion, Vol. 59, Issue 9 https://doi.org/10.1088/1741-4326/ab2aef	journal	August 2019
Deuterium inventory in Tore Supra: reconciling particle balance and post-mortem analysis Tsitrone, E.; Brosset, C.; Pégourié, B. Nuclear Fusion, Vol. 49, Issue 7 https://doi.org/10.1088/0029-5515/49/7/075011	journal	June 2009
Ion beam analysis of rough thin films Mayer, M. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 194, Issue 2 https://doi.org/10.1016/S0168-583X(02)00689-4	journal	August 2002
Plasma–surface interaction in the stellarator W7-X: conclusions drawn from operation with graphite plasma-facing components BrezƖnsek, S.; Dhard, C. P.; Jakubowski, M. Nuclear Fusion, Vol. 62, Issue 1 https://doi.org/10.1088/1741-4326/ac3508	journal	December 2021
Material erosion and deposition on the divertor of W7-X Mayer, M.; Balden, M.; Brezinsek, S. Physica Scripta, Vol. T171 https://doi.org/10.1088/1402-4896/ab4b8c	journal	January 2020
First results from divertor operation in Wendelstein 7-X Pedersen, Thomas Sunn; König, Ralf; Krychowiak, Maciej Plasma Physics and Controlled Fusion, Vol. 61, Issue 1 https://doi.org/10.1088/1361-6587/aaec25	journal	November 2018
Confirmation of the topology of the Wendelstein 7-X magnetic field to better than 1:100,000 Pedersen, T. Sunn; Otte, M.; Lazerson, S. Nature Communications, Vol. 7, Issue 1 https://doi.org/10.1038/ncomms13493	journal	November 2016
Conclusions about the use of tungsten in the divertor of ASDEX Upgrade Krieger, K.; Maier, H.; Neu, R. Journal of Nuclear Materials, Vol. 266-269 https://doi.org/10.1016/S0022-3115(98)00890-3	journal	March 1999
Ex situ analysis of W7-X divertor plasma-facing components by picosecond laser diagnostics Zhao, D.; Yi, R.; Oelmann, J. Physica Scripta, Vol. T171 https://doi.org/10.1088/1402-4896/ab3ee1	journal	January 2020
SigmaCalc recent development and present status of the evaluated cross-sections for IBA Gurbich, A. F. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 371 https://doi.org/10.1016/j.nimb.2015.09.035	journal	March 2016
The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment Bucalossi, J.; Missirlian, M.; Moreau, P. Fusion Engineering and Design, Vol. 89, Issue 7-8 https://doi.org/10.1016/j.fusengdes.2014.01.062	journal	October 2014
Ion beam analysis of fusion plasma-facing materials and components: facilities and research challenges Mayer, M.; Möller, S.; Rubel, M. Nuclear Fusion, Vol. 60, Issue 2 https://doi.org/10.1088/1741-4326/ab5817	journal	December 2019
Erosion of tungsten and steel in the main chamber of ASDEX Upgrade Hakola, A.; Koivuranta, S.; Likonen, J. Journal of Nuclear Materials, Vol. 463 https://doi.org/10.1016/j.jnucmat.2014.11.034	journal	August 2015
Impurity sources and fluxes in W7-X: from the plasma-facing components to the edge layer Wang, E.; Brezinsek, S.; Sereda, S. Physica Scripta, Vol. T171 https://doi.org/10.1088/1402-4896/ab4c04	journal	January 2020
Plasma–wall interaction at the ASDEX Upgrade tungsten heat shield Krieger, K.; Maier, H.; Neu, R. Fusion Engineering and Design, Vol. 56-57 https://doi.org/10.1016/S0920-3796(01)00257-5	journal	October 2001
Comparison of JET inner wall erosion in the first three ITER-like wall campaigns Krat, S.; Mayer, M.; Coad, J. P. Nuclear Materials and Energy, Vol. 29 https://doi.org/10.1016/j.nme.2021.101072	journal	December 2021
Design, R&D and commissioning of EAST tungsten divertor Yao, D. M.; Luo, G. N.; Zhou, Z. B. Physica Scripta, Vol. T167 https://doi.org/10.1088/0031-8949/2015/T167/014003	journal	December 2015
Non-boronized compared with boronized operation of ASDEX Upgrade with full-tungsten plasma facing components Kallenbach, A.; Dux, R.; Mayer, M. Nuclear Fusion, Vol. 49, Issue 4 https://doi.org/10.1088/0029-5515/49/4/045007	journal	March 2009
On impurity handling in high performance stellarator/heliotron plasmas Burhenn, R.; Feng, Y.; Ida, K. Nuclear Fusion, Vol. 49, Issue 6 https://doi.org/10.1088/0029-5515/49/6/065005	journal	April 2009

Similar Records

Plasma–surface interaction in the stellarator W7-X: conclusions drawn from operation with graphite plasma-facing components

Journal Article · Wed Dec 01 19:00:00 EST 2021 · Nuclear Fusion · OSTI ID:1828773

Erosion of tungsten marker layers in W7-X

Citation Formats

References (40)

Similar Records

Related Subjects