Predictive turbulence-driven flux model of scrape-off layer widths across confinement regimes in tokamaks

Abstract Reliable scrape-off layer (SOL) profile decay lengths predictions are needed to design and operate future tokamaks. The present manuscript describes a new model based on turbulent transport that is able to predict SOL widths for both L-mode and H-mode plasmas. The model is based upon the sheared-spectral filament paradigm (Peret et al (WEST Team) 2022 Phys. Plasmas 29 072306), however, incorporating the effects of thermal transport in order to calculate the parallel heat fluxes. The effects of magnetic shear and <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:mi>E</mml:mi> <mml:mrow> <mml:mo>×</mml:mo> </mml:mrow> <mml:mi>B</mml:mi> </mml:mrow> </mml:math> shear on the cross-field transport are crucial to explain the shorter SOL decay lengths found in H-mode. The model is validated against a database of thousands of DIII-D L-mode and H-mode SOL profiles. We also calculate SOL decay length predictions in terms of plasma and engineer control parameters, which are in agreement with the multi-machine empirical H-mode scaling (Eich et al (ASDEX Upgrade Team and JET EFDA Contributors) 2013 Nucl. Fusion 53 093031), however, with an additional device geometry dependence. ITER SOL width predictions by the model are 3 times higher than the empirical scaling.

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Publication Details

Journal
Nuclear Fusion
Published
2025-04-22
DOI
https://doi.org/10.1088/1741-4326/adcf37
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
0.00

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article

Predictive turbulence-driven flux model of scrape-off layer widths across confinement regimes in tokamaks

T. N. Bernard, M. Peret, J. Guterl, N. Fedorczak et al.
Nuclear Fusion
Magnetic confinement fusion research
article

Predictive turbulence-driven flux model of scrape-off layer widths across confinement regimes in tokamaks

T. N. Bernard, M. Peret, J. Guterl, N. Fedorczak, Federico David Halpern
article en

Abstract

Abstract Reliable scrape-off layer (SOL) profile decay lengths predictions are needed to design and operate future tokamaks. The present manuscript describes a new model based on turbulent transport that is able to predict SOL widths for both L-mode and H-mode plasmas. The model is based upon the sheared-spectral filament paradigm (Peret et al (WEST Team) 2022 Phys. Plasmas 29 072306), however, incorporating the effects of thermal transport in order to calculate the parallel heat fluxes. The effects of magnetic shear and <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:mi>E</mml:mi> <mml:mrow> <mml:mo>×</mml:mo> </mml:mrow> <mml:mi>B</mml:mi> </mml:mrow> </mml:math> shear on the cross-field transport are crucial to explain the shorter SOL decay lengths found in H-mode. The model is validated against a database of thousands of DIII-D L-mode and H-mode SOL profiles. We also calculate SOL decay length predictions in terms of plasma and engineer control parameters, which are in agreement with the multi-machine empirical H-mode scaling (Eich et al (ASDEX Upgrade Team and JET EFDA Contributors) 2013 Nucl. Fusion 53 093031), however, with an additional device geometry dependence. ITER SOL width predictions by the model are 3 times higher than the empirical scaling.

Nuclear FusionVol. 65(5)
Oak Ridge Associated Universities (US), Commissariat à l'Énergie Atomique et aux Énergies Alternatives (FR), CEA Cadarache (FR), General Atomics (United States) (US)
U.S. Department of Energy, Office of Science, Fusion Energy Sciences
Openalex Percentile: Top 96%
Magnetic confinement fusion research
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Predictive turbulence-driven flux model of scrape-off layer widths across confinement regimes in tokamaks — T. N. Bernard, M. Peret, et al. · Nuclear Fusion (2025) | TGRS Research Map | TGRS