SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas

Abstract The onset of detachment in the ITER machine is analyzed in this work through the help of 2D-axisymmetric boundary plasma simulations with the SOLEDGE3X-EIRENE code, which features a numerical domain for the plasma solver extending up to the first wall. The plasma boundary is computed in scenarios from the first non-active phase of ITER, in pure H and at 20 MW. This set of simulations is used in two aspects: first, to study the plasma detachment in the divertor, and second, the plasma conditions, fluxes, and beryllium erosion at the first wall. Here, the code results are also compared to those obtained with the well-established SOLPS-ITER code, which includes a plasma numerical domain only covering the main SOL. Results show an increase in the SOL width λ q with increasing density, and a detailed analysis is carried out, for the first time, on each of the different plasma-neutral interactions in the code’s physics model in EIRENE. The gross beryllium erosion rates of first wall panels are estimated from 2D simulations, with the aim of assessing their sensitivity to two parameters: the divertor density regime, and the presence of density shoulders in the far-SOL formed by enhanced perpendicular transport at this location. The erosion contributions from neutrals and ions are considered in each case, and the charge-exchange atoms fluxes and energy distributions are provided, highlighting the two atom populations (cold and charge-exchange).

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Publication Details

Journal
Nuclear Fusion
Published
2024-12-23
DOI
https://doi.org/10.1088/1741-4326/ada2a8
Citations
5
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
3.30

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article

SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas

X. Bonnin, G. Ciraolo, H. Bufferand, G. Falchetto et al.
5 citations
Nuclear Fusion
Magnetic confinement fusion research
3.30
article

SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas

X. Bonnin, G. Ciraolo, H. Bufferand, G. Falchetto, H. Yang, J. Park, Y. Marandet, R.A. Pitts, N. Rivals, P. Tamain
article en
5 citations

Abstract

Abstract The onset of detachment in the ITER machine is analyzed in this work through the help of 2D-axisymmetric boundary plasma simulations with the SOLEDGE3X-EIRENE code, which features a numerical domain for the plasma solver extending up to the first wall. The plasma boundary is computed in scenarios from the first non-active phase of ITER, in pure H and at 20 MW. This set of simulations is used in two aspects: first, to study the plasma detachment in the divertor, and second, the plasma conditions, fluxes, and beryllium erosion at the first wall. Here, the code results are also compared to those obtained with the well-established SOLPS-ITER code, which includes a plasma numerical domain only covering the main SOL. Results show an increase in the SOL width λ q with increasing density, and a detailed analysis is carried out, for the first time, on each of the different plasma-neutral interactions in the code’s physics model in EIRENE. The gross beryllium erosion rates of first wall panels are estimated from 2D simulations, with the aim of assessing their sensitivity to two parameters: the divertor density regime, and the presence of density shoulders in the far-SOL formed by enhanced perpendicular transport at this location. The erosion contributions from neutrals and ions are considered in each case, and the charge-exchange atoms fluxes and energy distributions are provided, highlighting the two atom populations (cold and charge-exchange).

Nuclear FusionVol. 65(2)
ITER (FR), Oak Ridge National Laboratory (US), Aix-Marseille Université (FR), Commissariat à l'Énergie Atomique et aux Énergies Alternatives (FR), CEA Cadarache (FR)
EUROfusion, European Commission, Euratom Research and Training Programme
Openalex Percentile: Top 6%
Magnetic confinement fusion research
3.30
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