Speaker
Description
Realizing commercially viable fusion power plants (FPPs) demands whole-device modeling efforts which integrate high‐fidelity plasma simulations with engineering systems and design capabilities. Among the most pressing challenges are the accurate prediction of heat and particle exhaust in the divertor region and the self‐consistent treatment of plasma–neutral and plasma–wall interactions in the edge and scrape‐off layer. In this work, the BOUT++/Hermes-3 [1] fluid framework is extended with a Cartesian flux-coordinate-independent (FCI) discretization [2], allowing for full-device transport and turbulence studies from the core to the first wall. To fully characterize the plasma, the device wall is represented as an immersed boundary [3], from which boundary conditions are imposed on the perpendicular anomalous diffusion and ExB advection terms. For terms employing a finite volume method, plasma cells intersected by the boundary are further treated using a cut-cell discretization [4]. The parallel discretization and associated boundary conditions are presently inherited from the quasi-FCI implementation BSTING [5].
This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344. LLNL-ABS-2020022
[1] B. Dudson, M. Kryjak, H. Muhammed, P. Hill, and J. Omotani Comp. Phys. Comm. 296 108991 (2024)
[2] F. Hariri and M. Ottaviani Comp. Phys. Comm. 184 2419-2429 (2013)
[3] R. Ghias, R. Mittal, and H. Dong Journal of Computational Physics 225 528–553 (2007)
[4] H. Johansen and P. Colella Journal of Computational Physics 147, 60-85 (1998)
[5] B. Shanahan, B. Dudson, and P. Hill Plasma Phys. Control. Fusion 61 025007 (2019)