3D modeling of <i>n</i> = 1 RMP driven heat fluxes on the SPARC tokamak PFCs using HEAT

Abstract 3D heat flux calculations at the lower outer divertor plate of SPARC using the HEAT code show that 3D fields generated from error field correction coils can lead to enhanced peak heat fluxes up to 15 times larger compared to the axisymmetric case. Previously employed to simulate axisymmetric heat flux on 3D plasma facing components, the HEAT code can now predict 3D heat flux generated by non-axisymmetric plasmas. This is achieved via a new HEAT module which leverages the 3D field line tracing capabilities of MAFOT starting from an M3D-C1 (MHD resistive code) perturbed equilibria. The resulting heat flux is assigned using the magnetic footprint and the heat flux layer model, an extension of the 2D heat flux model also known as the Eich, to 3D non-axisymmetric plasmas. For SPARC, the new capabilities of HEAT are used to calculate the 3D heat loads resulting from n = 1 perturbation fields (with n indicating the toroidal periodicity) applied through a toroidal array of six picture frame coils with different amplitude. The comparison with the unperturbed case shows significant changes in shape and intensity of the heat flux profile. The results show that the application of n = 1 3D field leads to a localized enhancement of the heat flux peak, influenced by the wetted area impacted by the magnetic footprint, and the appearance of a secondary heat flux peak, whose intensity depends on amplitude of the applied 3D field and toroidal location.

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Publication Details

Journal
Nuclear Fusion
Published
2025-08-04
DOI
https://doi.org/10.1088/1741-4326/adf760
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
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article

3D modeling of n = 1 RMP driven heat fluxes on the SPARC tokamak PFCs using HEAT

A. Wingen, Tom Looby, N.M. Ferraro, S. Munaretto et al.
1 links
Nuclear Fusion
Magnetic confinement fusion research
article

3D modeling of n = 1 RMP driven heat fluxes on the SPARC tokamak PFCs using HEAT

A. Wingen, Tom Looby, N.M. Ferraro, S. Munaretto, D. Corona, M. Scotto d’Abusco, A. Kleiner, R.M. Churchill
article en

Abstract

Abstract 3D heat flux calculations at the lower outer divertor plate of SPARC using the HEAT code show that 3D fields generated from error field correction coils can lead to enhanced peak heat fluxes up to 15 times larger compared to the axisymmetric case. Previously employed to simulate axisymmetric heat flux on 3D plasma facing components, the HEAT code can now predict 3D heat flux generated by non-axisymmetric plasmas. This is achieved via a new HEAT module which leverages the 3D field line tracing capabilities of MAFOT starting from an M3D-C1 (MHD resistive code) perturbed equilibria. The resulting heat flux is assigned using the magnetic footprint and the heat flux layer model, an extension of the 2D heat flux model also known as the Eich, to 3D non-axisymmetric plasmas. For SPARC, the new capabilities of HEAT are used to calculate the 3D heat loads resulting from n = 1 perturbation fields (with n indicating the toroidal periodicity) applied through a toroidal array of six picture frame coils with different amplitude. The comparison with the unperturbed case shows significant changes in shape and intensity of the heat flux profile. The results show that the application of n = 1 3D field leads to a localized enhancement of the heat flux peak, influenced by the wetted area impacted by the magnetic footprint, and the appearance of a secondary heat flux peak, whose intensity depends on amplitude of the applied 3D field and toroidal location.

Nuclear FusionVol. 65(9)
Oak Ridge National Laboratory (US), Princeton Plasma Physics Laboratory (US), Commonwealth Fund (US)
Openalex Percentile: Top 92%
Magnetic confinement fusion research
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