This title appears in the Scientific Report :
2022
Please use the identifier:
http://dx.doi.org/10.1088/1741-4326/ac2ef3 in citations.
Please use the identifier: http://hdl.handle.net/2128/32236 in citations.
Investigation of plasma wall interactions between tungsten plasma facing components and helium plasmas in the WEST tokamak
Investigation of plasma wall interactions between tungsten plasma facing components and helium plasmas in the WEST tokamak
ITER will operate with a tungsten divertor, a material featuring surface morphology changes when exposed to helium plasmas, in particular the formation of the so called tungsten fuzz under specific conditions. Investigating interactions between tungsten plasma facing components and helium plasmas in...
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Personal Name(s): | Tsitrone, E. |
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Pegourie, B. / Gunn, J. P. / Bernard, E. / Bruno, V. / Corre, Y. / Delpech, L. / Diez, M. / Douai, D. / Ekedahl, A. / Fedorczak, N. / Gallo, A. / Loarer, T. / Vartanian, S. / Gaspar, J. / Le Bohec, M. / Rigollet, F. / Bisson, R. / Brezinsek, S. (Corresponding author) / Dittmar, T. / De Temmerman, G. / Hakola, A. / Wauters, T. / Balden, M. / Mayer, M. / WEST Team | |
Contributing Institute: |
Plasmaphysik; IEK-4 |
Published in: | Nuclear fusion, 62 (2022) 7, S. 076028 - |
Imprint: |
Vienna
IAEA
2022
|
DOI: |
10.1088/1741-4326/ac2ef3 |
Document Type: |
Journal Article |
Research Program: |
Plasma-Wand-Wechselwirkung |
Link: |
Get full text Published on 2022-05-06. Available in OpenAccess from 2023-05-06. |
Publikationsportal JuSER |
Please use the identifier: http://hdl.handle.net/2128/32236 in citations.
ITER will operate with a tungsten divertor, a material featuring surface morphology changes when exposed to helium plasmas, in particular the formation of the so called tungsten fuzz under specific conditions. Investigating interactions between tungsten plasma facing components and helium plasmas in a tokamak environment is therefore a key point to consolidate predictions for the ITER divertor performance and lifetime. To this end, a dedicated helium campaign was performed in the full tungsten WEST tokamak, cumulating ∼2000 s of repetitive L mode discharges. It is shown that conditions for tungsten fuzz formation, as derived from linear devices experiments (incident helium energy Einc > 20 eV, helium fluence >1024 He/m2, surface temperature Tsurf > 700 °C), were met in the outer strike point (OSP) area of the inertially cooled tungsten divertor elements of WEST. Preliminary inspection of the components after the campaign did not show visible signs of surface modification, but points to significant net erosion in the OSP area. An extensive post mortem analysis is now ongoing to confirm these first indications. These results underline that the complex balance between erosion/redeposition (in particular linked to impurities) and tungsten fuzz formation needs to be taken into account in tokamak conditions. |