Inferring the scrape-off layer heat flux width in a divertor with a low degree of axisymmetry

Plasma facing components (PFCs) in the next generation of tokamak devices will operate in challenging environments, with heat loads predicted to exceed 10 MW/m 2 . The magnitude of these heat loads is set by the width of the channel, the ‘scrape-off layer’ (SOL), into which heat is exhausted, and can be characterised by an e-folding length scale for the decay of heat flux across the channel. It is expected this channel will narrow as tokamaks move towards reactor relevant conditions. Understanding the processes involved in setting the SOL heat flux width is imperative to be able to predict the heat loads PFCs must handle in future devices. Measurements of the SOL width are performed on the high-field spherical tokamak, ST40, using a newly commissioned infrared thermography system. With its high on-axis toroidal magnetic field ( ≥ 1.5 T) ST40 is uniquely positioned to investigate the influence of toroidal field on the heat flux width in spherical tokamaks, whilst also extending measurements of the SOL width in spherical tokamaks to increased poloidal field ( ≥ 0.3 T). Due to the divertor on ST40 having a low degree of axisymmetry, it is necessary for a set of radial measurements of the heat flux to be taken across the divertor, made possible using an automated toolchain that fully incorporates its 3D geometry. These radial profiles are combined with the magnetic geometry of the plasma to infer the width of the SOL, with both Eich and double exponential profiles of heat flux observed. A reduction in the heat flux is observed toroidally across part of the divertor, along with increased heat loads observed locally around the edges of the tiles. Future work in characterising the impact of tile misalignment and uncertainties in the reconstructed divertor magnetic geometry is required in order to further understand the observed heat flux patterns, as are additional investigations into the role potentially being played by an inhomogeneous sheath electric field. • A new IR thermography system has been commissioned on the spherical tokamak ST40. • The scrape-off layer heat flux width is measured on the outer divertor region. • The low degree of axisymmetry of the divertor requires a 3D approach.

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Publication Details

Journal
Nuclear Materials and Energy
Published
2024-10-22
DOI
https://doi.org/10.1016/j.nme.2024.101773
Citations
5
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
3.30
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article

Inferring the scrape-off layer heat flux width in a divertor with a low degree of axisymmetry

M. Sertoli, X. Zhang, E. O. Vekshina, M. Moscheni et al.
5 citations
Nuclear Materials and Energy
Magnetic confinement fusion research
3.30
article

Inferring the scrape-off layer heat flux width in a divertor with a low degree of axisymmetry

M. Sertoli, X. Zhang, E. O. Vekshina, M. Moscheni, Timothy Gray, A. Scarabosio, F. Romanelli, A. Rengle, C. Marsden
article en
5 citations

Abstract

Plasma facing components (PFCs) in the next generation of tokamak devices will operate in challenging environments, with heat loads predicted to exceed 10 MW/m 2 . The magnitude of these heat loads is set by the width of the channel, the ‘scrape-off layer’ (SOL), into which heat is exhausted, and can be characterised by an e-folding length scale for the decay of heat flux across the channel. It is expected this channel will narrow as tokamaks move towards reactor relevant conditions. Understanding the processes involved in setting the SOL heat flux width is imperative to be able to predict the heat loads PFCs must handle in future devices. Measurements of the SOL width are performed on the high-field spherical tokamak, ST40, using a newly commissioned infrared thermography system. With its high on-axis toroidal magnetic field ( ≥ 1.5 T) ST40 is uniquely positioned to investigate the influence of toroidal field on the heat flux width in spherical tokamaks, whilst also extending measurements of the SOL width in spherical tokamaks to increased poloidal field ( ≥ 0.3 T). Due to the divertor on ST40 having a low degree of axisymmetry, it is necessary for a set of radial measurements of the heat flux to be taken across the divertor, made possible using an automated toolchain that fully incorporates its 3D geometry. These radial profiles are combined with the magnetic geometry of the plasma to infer the width of the SOL, with both Eich and double exponential profiles of heat flux observed. A reduction in the heat flux is observed toroidally across part of the divertor, along with increased heat loads observed locally around the edges of the tiles. Future work in characterising the impact of tile misalignment and uncertainties in the reconstructed divertor magnetic geometry is required in order to further understand the observed heat flux patterns, as are additional investigations into the role potentially being played by an inhomogeneous sheath electric field. • A new IR thermography system has been commissioned on the spherical tokamak ST40. • The scrape-off layer heat flux width is measured on the outer divertor region. • The low degree of axisymmetry of the divertor requires a 3D approach.

Nuclear Materials and EnergyVol. 41
Oak Ridge National Laboratory (US), Tokamak Energy (United Kingdom) (GB), Fusion (United States) (US), Fusion Academy (US), LINKS Foundation (IT)
Affordable and clean energy
Openalex Percentile: Top 6%
Magnetic confinement fusion research
3.30
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