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.
Authors
- E.A. Unterberg (ORCID: https://orcid.org/0000-0003-1353-8865)
- Travis Gray (ORCID: https://orcid.org/0000-0001-8220-8195)
- O. Asunta (ORCID: https://orcid.org/0000-0001-5618-5380)
- Tom Looby (ORCID: https://orcid.org/0000-0002-1275-2758)
- Steven McNamara (ORCID: https://orcid.org/0000-0002-0477-5247)
- E. O. Vekshina (ORCID: https://orcid.org/0000-0001-9771-5579)
- P. Bunting (ORCID: https://orcid.org/0000-0002-6493-0632)
- M. Moscheni (ORCID: https://orcid.org/0000-0002-6355-7274)
- A. Rengle (ORCID: https://orcid.org/0009-0001-9037-1125)
- C. Marsden (ORCID: https://orcid.org/0000-0003-1322-5236)
- Erin Joy C. Tinacba (ORCID: https://orcid.org/0000-0001-9915-3397)
Institutions
- Oak Ridge National Laboratory (US)
- Tokamak Energy (United Kingdom) (GB)
- Decision Systems (United States) (US)
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
Funders
- U.S. Department of Energy