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.
Authors
- T. N. Bernard (ORCID: https://orcid.org/0000-0002-7331-9704)
- M. Peret (ORCID: https://orcid.org/0000-0002-9773-5534)
- J. Guterl (ORCID: https://orcid.org/0000-0002-1049-3094)
- N. Fedorczak (ORCID: https://orcid.org/0000-0001-7123-7433)
- Federico David Halpern (ORCID: https://orcid.org/0000-0002-0387-6038)
Institutions
- Oak Ridge Associated Universities (US)
- Commissariat à l'Énergie Atomique et aux Énergies Alternatives (FR)
- CEA Cadarache (FR)
- General Atomics (United States) (US)
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
Funders
- U.S. Department of Energy
- Office of Science
- Fusion Energy Sciences