SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas
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 fr...
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| Format: | Article |
| Language: | English |
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IOP Publishing
2025-01-01
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| Series: | Nuclear Fusion |
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| Online Access: | https://doi.org/10.1088/1741-4326/ada2a8 |
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| author | N. Rivals P. Tamain Y. Marandet X. Bonnin J.-S. Park H. Bufferand R.A. Pitts G. Falchetto H. Yang G. Ciraolo |
| author_facet | N. Rivals P. Tamain Y. Marandet X. Bonnin J.-S. Park H. Bufferand R.A. Pitts G. Falchetto H. Yang G. Ciraolo |
| author_sort | N. Rivals |
| collection | DOAJ |
| description | 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). |
| format | Article |
| id | doaj-art-1df36d3719b74a13bd9c07ef25d467ec |
| institution | Kabale University |
| issn | 0029-5515 |
| language | English |
| publishDate | 2025-01-01 |
| publisher | IOP Publishing |
| record_format | Article |
| series | Nuclear Fusion |
| spelling | doaj-art-1df36d3719b74a13bd9c07ef25d467ec2025-01-10T10:55:48ZengIOP PublishingNuclear Fusion0029-55152025-01-0165202603810.1088/1741-4326/ada2a8SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmasN. Rivals0https://orcid.org/0000-0002-4467-5857P. Tamain1Y. Marandet2https://orcid.org/0000-0002-9970-538XX. Bonnin3J.-S. Park4https://orcid.org/0000-0003-0871-7527H. Bufferand5https://orcid.org/0000-0002-9731-5855R.A. Pitts6https://orcid.org/0000-0001-9455-2698G. Falchetto7H. Yang8https://orcid.org/0000-0002-4983-1249G. Ciraolo9CEA, IRFM , F-13108 Saint-Paul-lez-Durance, France; Aix-Marseille Univ , CNRS, PIIM, Marseille, FranceCEA, IRFM , F-13108 Saint-Paul-lez-Durance, FranceAix-Marseille Univ , CNRS, PIIM, Marseille, FranceITER Organization , CS 90 046 - 13067 St Paul Lez Durance Cedex, FranceOak Ridge National Laboratory , Oak Ridge, TN 37831, United States of AmericaCEA, IRFM , F-13108 Saint-Paul-lez-Durance, FranceITER Organization , CS 90 046 - 13067 St Paul Lez Durance Cedex, FranceCEA, IRFM , F-13108 Saint-Paul-lez-Durance, FranceCEA, IRFM , F-13108 Saint-Paul-lez-Durance, FranceCEA, IRFM , F-13108 Saint-Paul-lez-Durance, FranceThe 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).https://doi.org/10.1088/1741-4326/ada2a8edge plasmasimulationITERfirst-wallscrape-off layerplasma-neutral interactions |
| spellingShingle | N. Rivals P. Tamain Y. Marandet X. Bonnin J.-S. Park H. Bufferand R.A. Pitts G. Falchetto H. Yang G. Ciraolo SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas Nuclear Fusion edge plasma simulation ITER first-wall scrape-off layer plasma-neutral interactions |
| title | SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas |
| title_full | SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas |
| title_fullStr | SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas |
| title_full_unstemmed | SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas |
| title_short | SOLEDGE3X full vessel plasma boundary simulations of ITER non-active phase plasmas |
| title_sort | soledge3x full vessel plasma boundary simulations of iter non active phase plasmas |
| topic | edge plasma simulation ITER first-wall scrape-off layer plasma-neutral interactions |
| url | https://doi.org/10.1088/1741-4326/ada2a8 |
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