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, qtarget, 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...

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Main Authors: E.J.C. Tinacba, T.K. Gray, M. Moscheni, C. Marsden, E. Vekshina, O. Asunta, P. Bunting, S. McNamara, A. Rengle, T. Looby, E.A. Unterberg
Format: Article
Language:English
Published: Elsevier 2024-12-01
Series:Nuclear Materials and Energy
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Online Access:http://www.sciencedirect.com/science/article/pii/S235217912400214X
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author E.J.C. Tinacba
T.K. Gray
M. Moscheni
C. Marsden
E. Vekshina
O. Asunta
P. Bunting
S. McNamara
A. Rengle
T. Looby
E.A. Unterberg
author_facet E.J.C. Tinacba
T.K. Gray
M. Moscheni
C. Marsden
E. Vekshina
O. Asunta
P. Bunting
S. McNamara
A. Rengle
T. Looby
E.A. Unterberg
author_sort E.J.C. Tinacba
collection DOAJ
description The Heat Flux Engineering Analysis Toolkit (HEAT) (Looby et al., 2022) was used to simulate the heat flux, qtarget, 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 qtarget was used in OpenFOAM to calculate the corresponding temperature, T, on the divertors. Results showed that a good agreement on the simulated qtarget, 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.
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series Nuclear Materials and Energy
spelling doaj-art-6a72112dc7ff4501a727d309ef2ee2532025-08-20T02:34:55ZengElsevierNuclear Materials and Energy2352-17912024-12-014110179110.1016/j.nme.2024.101791HEAT simulation and IR data comparison for ST40 plasma-facing componentsE.J.C. Tinacba0T.K. Gray1M. Moscheni2C. Marsden3E. Vekshina4O. Asunta5P. Bunting6S. McNamara7A. Rengle8T. Looby9E.A. Unterberg10Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, 37830, TN, USA; Corresponding author.Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, 37830, TN, USATokamak Energy Ltd., Milton Park, Oxfordshire, OX14 4SD, United Kingdom of Great Britain and Northern IrelandTokamak Energy Ltd., Milton Park, Oxfordshire, OX14 4SD, United Kingdom of Great Britain and Northern IrelandOak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, 37830, TN, USATokamak Energy Ltd., Milton Park, Oxfordshire, OX14 4SD, United Kingdom of Great Britain and Northern IrelandTokamak Energy Ltd., Milton Park, Oxfordshire, OX14 4SD, United Kingdom of Great Britain and Northern IrelandTokamak Energy Ltd., Milton Park, Oxfordshire, OX14 4SD, United Kingdom of Great Britain and Northern IrelandTokamak Energy Ltd., Milton Park, Oxfordshire, OX14 4SD, United Kingdom of Great Britain and Northern IrelandCommonwealth Fusion Systems, 148 Sidney Street, Cambridge, 02139, MA, USAOak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, 37830, TN, USAThe Heat Flux Engineering Analysis Toolkit (HEAT) (Looby et al., 2022) was used to simulate the heat flux, qtarget, 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 qtarget was used in OpenFOAM to calculate the corresponding temperature, T, on the divertors. Results showed that a good agreement on the simulated qtarget, 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.http://www.sciencedirect.com/science/article/pii/S235217912400214XFusionHeat flux calculationST40IR thermography
spellingShingle E.J.C. Tinacba
T.K. Gray
M. Moscheni
C. Marsden
E. Vekshina
O. Asunta
P. Bunting
S. McNamara
A. Rengle
T. Looby
E.A. Unterberg
HEAT simulation and IR data comparison for ST40 plasma-facing components
Nuclear Materials and Energy
Fusion
Heat flux calculation
ST40
IR thermography
title HEAT simulation and IR data comparison for ST40 plasma-facing components
title_full HEAT simulation and IR data comparison for ST40 plasma-facing components
title_fullStr HEAT simulation and IR data comparison for ST40 plasma-facing components
title_full_unstemmed HEAT simulation and IR data comparison for ST40 plasma-facing components
title_short HEAT simulation and IR data comparison for ST40 plasma-facing components
title_sort heat simulation and ir data comparison for st40 plasma facing components
topic Fusion
Heat flux calculation
ST40
IR thermography
url http://www.sciencedirect.com/science/article/pii/S235217912400214X
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