Development and validation of non-axisymmetric heat flux simulations with 3D fields using the HEAT code
Open Access
- 23 July 2025
- journal article
- Published by IOP Publishing in Nuclear Fusion
- Vol. 65 (8) , 086029
Abstract
A new comprehensive module to simulate heat fluxes from three-dimensional (3D) magnetic fields has been implemented in the HEAT code. Especially compact tokamaks like SPARC require tools to predict and manage large heat fluxes. Existing release versions of HEAT can only simulate axisymmetric heat flux on 3D plasma facing components. The new module uses an M3D-C1 perturbed equilibrium and the MAFOT code to trace field lines of the perturbed 3D magnetic field. Heat flux is then assigned to the resulting footprints via a 3D layer model. The model distinguishes between the scrape-off layer, the magnetic lobes and the private flux region, and employs only 0D parameters like the layer width, diffusive spread and the last closed flux surface position in the perturbed edge to generate a heat flux profile. The magnitude is normalized to the total input power. Resulting heat flux simulations are compared and validated against infrared measurements in the DIII-D tokamak with applied 3D fields; good agreement is found for several cases. The new module can now be applied to the SPARC tokamak; a preliminary result for applied rotating 3D fields is shown.Keywords
Funding Information
- Commonwealth Fusion Systems
- Fusion Energy Sciences (AC05-00OR22725)
This publication has 21 references indexed in Scilit:
- Shadow masks predictions in SPARC tokamak plasma-facing components using HEAT code and machine learning methodsFusion Engineering and Design, 2025
- A Software Package for Plasma-Facing Component Analysis and Design: The Heat Flux Engineering Analysis Toolkit (HEAT)Fusion Science and Technology, 2022
- Divertor heat flux challenge and mitigation in SPARCJournal of Plasma Physics, 2020
- Physics basis for the first ITER tungsten divertorNuclear Materials and Energy, 2019
- Design optimization of the ITER tungsten divertor vertical targetsFusion Engineering and Design, 2018
- Heat flux modeling using ion drift effects in DIII-D H-mode plasmas with resonant magnetic perturbationsPhysics of Plasmas, 2014
- High resolution numerical studies of separatrix splitting due to non-axisymmetric perturbation in DIII-DNuclear Fusion, 2009
- Footprint structures due to resonant magnetic perturbations in DIII-DPhysics of Plasmas, 2009
- Error field correction in ITERNuclear Fusion, 2008
- Chapter 3: MHD stability, operational limits and disruptionsNuclear Fusion, 2007