TRT Divertor Optimization in SOLPS-ITER Modeling

The analysis of possible divertor working regimes and edge plasma parameters for TRT tokamak project is performed basing on modeling. It is shown that for the separatrix power of 18 MW corresponding to approximately twice higher full input power the low divertor integral heat flux 5 MW/m2 can be provided for the separatrix plasma density lower than 7 × 1019 m–3 and the effective charge Zeff lower than 2. These parameters are realistic for this device. In case of bigger separatrix power the working regime is possible with higher divertor heat load still within the technological limits of the machine. Modeling also shows positive effect of the increase of the distance between the separatrix and the vacuum vessel structures and better performance of the corner divertor configuration comparing to the “ITER-like” one.

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Publication Details

Journal
Plasma Physics Reports
Published
2024-12-01
DOI
https://doi.org/10.1134/s1063780x24601767
Primary Topic
Magnetic confinement fusion research
Type
article
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article

TRT Divertor Optimization in SOLPS-ITER Modeling

Nikita Shtyrkhunov, V. Rozhansky, I. Senichenkov, E. Kaveeva et al.
Plasma Physics Reports
Magnetic confinement fusion research
article

TRT Divertor Optimization in SOLPS-ITER Modeling

Nikita Shtyrkhunov, V. Rozhansky, I. Senichenkov, E. Kaveeva, P. Molchanov, P. S. Kudrevatykh
article en

Abstract

The analysis of possible divertor working regimes and edge plasma parameters for TRT tokamak project is performed basing on modeling. It is shown that for the separatrix power of 18 MW corresponding to approximately twice higher full input power the low divertor integral heat flux 5 MW/m2 can be provided for the separatrix plasma density lower than 7 × 1019 m–3 and the effective charge Zeff lower than 2. These parameters are realistic for this device. In case of bigger separatrix power the working regime is possible with higher divertor heat load still within the technological limits of the machine. Modeling also shows positive effect of the increase of the distance between the separatrix and the vacuum vessel structures and better performance of the corner divertor configuration comparing to the “ITER-like” one.

Plasma Physics ReportsVol. 50(12)
Peter the Great St. Petersburg Polytechnic University (RU)
Openalex Percentile: Top 93%
Magnetic confinement fusion research
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