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

ST40 team

doi:10.1016/j.nme.2024.101791

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

ST40 team

Research output: Contribution to journal › Article › peer-review

2 Scopus citations

Abstract

The Heat Flux Engineering Analysis Toolkit (HEAT) (Looby et al., 2022) was used to simulate the heat flux, q_target, 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_target was used in OpenFOAM to calculate the corresponding temperature, T, on the divertors. Results showed that a good agreement on the simulated q_target, 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.

Original language	English
Article number	101791
Journal	Nuclear Materials and Energy
Volume	41
DOIs	https://doi.org/10.1016/j.nme.2024.101791
State	Published - Dec 2024

Funding

This work has been authored by UT-Battelle, LLC, with the US Department of Energy (DOE). Work supported in part by the US DOE under contracts DE-AC05-00OR22725 and U.S. DOE CRADA NFE-19-07769 .

Keywords

Fusion
Heat flux calculation
IR thermography
ST40

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10.1016/j.nme.2024.101791

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title = "HEAT simulation and IR data comparison for ST40 plasma-facing components",

abstract = "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.",

keywords = "Fusion, Heat flux calculation, IR thermography, ST40",

author = "\{ST40 team\} and Tinacba, \{E. J.C.\} and Gray, \{T. K.\} and M. Moscheni and C. Marsden and E. Vekshina and O. Asunta and P. Bunting and S. McNamara and A. Rengle and T. Looby and Unterberg, \{E. A.\}",

note = "Publisher Copyright: {\textcopyright} 2024",

year = "2024",

month = dec,

doi = "10.1016/j.nme.2024.101791",

language = "English",

volume = "41",

journal = "Nuclear Materials and Energy",

issn = "2352-1791",

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TY - JOUR

T1 - HEAT simulation and IR data comparison for ST40 plasma-facing components

AU - ST40 team

AU - Tinacba, E. J.C.

AU - Gray, T. K.

AU - Moscheni, M.

AU - Marsden, C.

AU - Vekshina, E.

AU - Asunta, O.

AU - Bunting, P.

AU - McNamara, S.

AU - Rengle, A.

AU - Looby, T.

AU - Unterberg, E. A.

PY - 2024/12

Y1 - 2024/12

N2 - 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.

AB - 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.

KW - Fusion

KW - Heat flux calculation

KW - IR thermography

KW - ST40

UR - https://www.scopus.com/pages/publications/85210300903

U2 - 10.1016/j.nme.2024.101791

DO - 10.1016/j.nme.2024.101791

M3 - Article

AN - SCOPUS:85210300903

SN - 2352-1791

VL - 41

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

M1 - 101791

ER -

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

Abstract

Funding

Keywords

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