Novel SOLPS-ITER simulations of X-point target and snowflake divertors
The design and understanding of alternative divertor configurations may be crucial for achieving acceptable steady-state heat and particle material loads for magnetic confinement fusion reactors. Multiple X-point alternative divertor geometries such as snowflakes and X-point targets have great poten...
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| Veröffentlicht in: | Plasma physics and controlled fusion 2023-03, Vol.65 (3), p.35011 |
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| container_title | Plasma physics and controlled fusion |
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| creator | Cowley, C Kuang, A Q Moulton, D Lore, J D Canik, J Umansky, M Wigram, M Ballinger, S Lipschultz, B Bonnin, X |
| description | The design and understanding of alternative divertor configurations may be crucial for achieving acceptable steady-state heat and particle material loads for magnetic confinement fusion reactors. Multiple X-point alternative divertor geometries such as snowflakes and X-point targets have great potential in reducing power loads, but have not yet been simulated widely in codes with kinetic neutrals. This paper discusses recent changes made to the SOLPS-ITER code to allow for the simulation of X-point target and low-field side snowflake divertor geometries. Snowflake simulations using this method are presented, in addition to the first SOLPS-ITER simulation of the X-point target. Analysis of these results show reasonable consistency with the simple modelling and theoretical predictions, supporting the validity of the methodology implemented. |
| doi_str_mv | 10.1088/1361-6587/acb4ba |
| format | Article |
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| subjects | advanced divertor divertor simulation snowflake SOLPS SOLPS-ITER X-point target |
| title | Novel SOLPS-ITER simulations of X-point target and snowflake divertors |
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