Evolution and cleaning of the deposit layers on the lower divertor of WEST fully equipped with ITER grade components

After 3 h of accumulated time from repeated plasma shots during C7 campaign performed in 2023, a deposited layer appeared on the ITER-grade W-monoblock of the lower divertor of WEST, mostly on the high field side. The growth of the deposit was observed during the campaign using infrared cameras, showing a large increase of the area covered by the deposit (x4) in the last two hours of cumulated plasma time. The deposit becomes problematic for the operation as it generates flakes which provoke radiative collapse when entering the plasma. A cleaning of the lower divertor is mandatory. A first cleaning was done using adhesive tape to remove all weakly adhered parts of the deposit. This method was chosen because it was easy to implement and did not generate dusts inside the tokamak. The cleaning enables partial removal of the more lightly adhered deposits but a large fraction remains stuck on the monoblock. A second cleaning was tried during 2024 operation by using the plasma as cleaner. A scenario was developed to put the inner strike line directly on the deposit to heat it and try to remove it by thermal stress. The deposit reaches temperature up to 1560°C but was not removed. The impurities generated were higher than normal operation and decreased during the cleaning session (−50% of light impurities observed at the end of the cleaning discharge session), showing an effect of cleaning by removing impurities from the deposit. • The erosion of the ITER-grade W monoblock under plasma condition leads to W-deposit layers. • Deposit has higher emissivity and poor thermal contact. • Cleaning the deposit on the lower divertor is mandatory for the operation. • Adhesive tape removes only weakly adhered deposit. • Deposit can resist to high temperature from plasma.

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Publication Details

Journal
Nuclear Materials and Energy
Published
2024-10-28
DOI
https://doi.org/10.1016/j.nme.2024.101783
Citations
2
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
0.23
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article

Evolution and cleaning of the deposit layers on the lower divertor of WEST fully equipped with ITER grade components

J. Gaspar, C. Guillemaut, C. Hernández, A. Huart et al.
2 citations
Nuclear Materials and Energy
Fusion materials and technologies
0.23
article

Evolution and cleaning of the deposit layers on the lower divertor of WEST fully equipped with ITER grade components

J. Gaspar, C. Guillemaut, C. Hernández, A. Huart, L. Dubus, M. Firdaouss, A. Grosjean, J. Gérardin, C. Desgranges, M. Diez, Y. Corre, S. Vivès, H. Roche
article en
2 citations

Abstract

After 3 h of accumulated time from repeated plasma shots during C7 campaign performed in 2023, a deposited layer appeared on the ITER-grade W-monoblock of the lower divertor of WEST, mostly on the high field side. The growth of the deposit was observed during the campaign using infrared cameras, showing a large increase of the area covered by the deposit (x4) in the last two hours of cumulated plasma time. The deposit becomes problematic for the operation as it generates flakes which provoke radiative collapse when entering the plasma. A cleaning of the lower divertor is mandatory. A first cleaning was done using adhesive tape to remove all weakly adhered parts of the deposit. This method was chosen because it was easy to implement and did not generate dusts inside the tokamak. The cleaning enables partial removal of the more lightly adhered deposits but a large fraction remains stuck on the monoblock. A second cleaning was tried during 2024 operation by using the plasma as cleaner. A scenario was developed to put the inner strike line directly on the deposit to heat it and try to remove it by thermal stress. The deposit reaches temperature up to 1560°C but was not removed. The impurities generated were higher than normal operation and decreased during the cleaning session (−50% of light impurities observed at the end of the cleaning discharge session), showing an effect of cleaning by removing impurities from the deposit. • The erosion of the ITER-grade W monoblock under plasma condition leads to W-deposit layers. • Deposit has higher emissivity and poor thermal contact. • Cleaning the deposit on the lower divertor is mandatory for the operation. • Adhesive tape removes only weakly adhered deposit. • Deposit can resist to high temperature from plasma.

Nuclear Materials and EnergyVol. 41
Centre National de la Recherche Scientifique (FR), Aix-Marseille Université (FR), Commissariat à l'Énergie Atomique et aux Énergies Alternatives (FR), Knoxville College (US), CEA Cadarache (FR), Centrale Méditerranée (FR), University of Tennessee at Knoxville (US)
Industry, innovation and infrastructure
Openalex Percentile: Top 50%
Fusion materials and technologies
0.23
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