HEAT simulation and IR data comparison for ST40 plasma-facing components

The Heat Flux Engineering Analysis Toolkit (HEAT) (Looby et al., 2022) was used to simulate the heat flux, q t a r g e t , on ST40 molybdenum divertors. Results were compared with experimental infrared (IR) data. Two shots, 11419 and 11376 at time instants 119 ms and 120 ms, with lower-biased disconnected double null geometries, were studied. Single- λ and multi- λ heat flux profiles were used as input in HEAT simulation. The simulated q t a r g e t was used in OpenFOAM to calculate the corresponding temperature, T , on the divertors. Results showed that a good agreement on the simulated q t a r g e t , T and shape of the heat flux on the divertor with the IR data was achieved when a multi- λ heat flux profile was used for 11419, and single- λ heat flux profile for 11376. This indicates that HEAT can be reliable in analyzing and understanding the heat loading of plasma facing components in tokamak devices. • HEAT simulation results were compared with IR data from ST40 divertors. • Single- λ and multi- λ heat flux profiles were used to model the deposited heat flux. • Simulated target heat flux and temperature have a good agreement with the IR data.

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Publication Details

Journal
Nuclear Materials and Energy
Published
2024-11-21
DOI
https://doi.org/10.1016/j.nme.2024.101791
Citations
2
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
1.32

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article

HEAT simulation and IR data comparison for ST40 plasma-facing components

E.A. Unterberg, Travis Gray, O. Asunta, Tom Looby et al.
2 citations
Nuclear Materials and Energy
Magnetic confinement fusion research
1.32
article

HEAT simulation and IR data comparison for ST40 plasma-facing components

E.A. Unterberg, Travis Gray, O. Asunta, Tom Looby, Steven McNamara, E. O. Vekshina, P. Bunting, M. Moscheni, A. Rengle, C. Marsden, Erin Joy C. Tinacba
article en
2 citations

Abstract

The Heat Flux Engineering Analysis Toolkit (HEAT) (Looby et al., 2022) was used to simulate the heat flux, q t a r g e t , on ST40 molybdenum divertors. Results were compared with experimental infrared (IR) data. Two shots, 11419 and 11376 at time instants 119 ms and 120 ms, with lower-biased disconnected double null geometries, were studied. Single- λ and multi- λ heat flux profiles were used as input in HEAT simulation. The simulated q t a r g e t was used in OpenFOAM to calculate the corresponding temperature, T , on the divertors. Results showed that a good agreement on the simulated q t a r g e t , T and shape of the heat flux on the divertor with the IR data was achieved when a multi- λ heat flux profile was used for 11419, and single- λ heat flux profile for 11376. This indicates that HEAT can be reliable in analyzing and understanding the heat loading of plasma facing components in tokamak devices. • HEAT simulation results were compared with IR data from ST40 divertors. • Single- λ and multi- λ heat flux profiles were used to model the deposited heat flux. • Simulated target heat flux and temperature have a good agreement with the IR data.

Nuclear Materials and EnergyVol. 41
Oak Ridge National Laboratory (US), Tokamak Energy (United Kingdom) (GB), Decision Systems (United States) (US)
U.S. Department of Energy
Affordable and clean energy
Openalex Percentile: Top 10%
Magnetic confinement fusion research
1.32
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