FreeMHD: experimental validation of a fully-3D-non inductive-MHD solver for liquid metal flows in fusion devices
POSTER
Abstract
Liquid metals (LM) are an alternative to solid plasma-facing components in divertors of fusion reactors, where melting and erosion has been observed. LM flows could exhaust heat from the plasma through advection (fast-flow regime) or by conduction to a substrate (slow-flows regime). Free-surface-LM flows inside nuclear-fusion-reactor conditions have been considered for this purpose. However, the analysis of this type of flows under strong magnetic fields through simulations has been a challenge due as extremely thin Hartmann layers in the flow and ripples at the free surface could make numerical convergence unattainable.
FreeMHD is a fully three-dimensional and transient numerical tool for the simulation of free surface, thermo-MHD phenomena is developed in the framework of the finite volume method and implemented using the OpenFOAM open-source toolkit. It provides a new simulation tool that has been recently developed. FreeMHD is the first simulation code validated against a series of experiments under different MHD conditions while varying: substrate conductivity and thickness, applied external currents and magnitude of external magnetic fields. These experiments were executed in the Liquid Metal eXperiment - Upgrade (LMX-U) and in the Liquid Metal FRee-surface EXperiment (LMFREX) at the Oroshhi-2 Superconducting Magnet Facility of the National Institute for Fusion Science (NIFS). Additionally, simulations at the reactor scale were executed, which evidences the code stability at strong magnetic fields.
FreeMHD is a fully three-dimensional and transient numerical tool for the simulation of free surface, thermo-MHD phenomena is developed in the framework of the finite volume method and implemented using the OpenFOAM open-source toolkit. It provides a new simulation tool that has been recently developed. FreeMHD is the first simulation code validated against a series of experiments under different MHD conditions while varying: substrate conductivity and thickness, applied external currents and magnitude of external magnetic fields. These experiments were executed in the Liquid Metal eXperiment - Upgrade (LMX-U) and in the Liquid Metal FRee-surface EXperiment (LMFREX) at the Oroshhi-2 Superconducting Magnet Facility of the National Institute for Fusion Science (NIFS). Additionally, simulations at the reactor scale were executed, which evidences the code stability at strong magnetic fields.
Publication: 1. "Experimental, numerical and analytical evaluation of jxB-thrust for fast-liquid-metal-flow-divertor systems of nuclear fusion devices" by Francisco Saenz, et al. In revision.Article reference: NF-106257<br>2. Z. Sun et al 2023 Nucl. Fusion 63 076022
Presenters
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Francisco J Saenz
Princeton Plasma Physics Laboratory
Authors
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Francisco J Saenz
Princeton Plasma Physics Laboratory
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Brian R Wynne
Princeton University
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Jabir Al-Salami
Kyushu University
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Changhong Hu
Kyushu University
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Kazuaki Hanada
Kyushu University
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Egemen Kolemen
Princeton University