FLIPEC, an ideal MHD free-boundary axisymmetric equilibrium solver in the presence of macroscopic flows

G. F.-Torija Daza, J.M. Reynolds-Barredo, R. Sanchez, A. Loarte, V. Tribaldos2024年8月Nuclear FusionIF 3 出版社

The most relevant features of FLIPEC (Free fLow Iterative Plasma Equilibrium Code) are presented. This new code iteratively calculates free-boundary, axisymmetric ideal MHD equilibria with arbitrary poloidal and toroidal plasma flows. FLIPEC is a mature code that has emerged from a complete overhaul of a previous version (F-Torija Daza 2022 et alNucl. Fusion62 126044). It uses a (inverse) curvilinear coordinate representation for the Grad–Shafranov–Bernoulli equation system, which allows FLIPEC to extend its free-boundary capabilities to arbitrary plasma shapes and removes many limitations with regards to the distance between plasma and external coils. Run-time stabilization of vertical modes has also been implemented by means of artificial feedback coils. Finally, active targeting schemes have also been included. These capabilities are illustrated on two very different cases: the ITER tokamak baseline configuration and a NSTX spherical tokamak equilibrium.

iter低精度(概要文一致)nstx-u低精度(概要文一致)

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ENThis paper should be read by fusion researchers and engineers working on plasma equilibrium modeling and control, as it presents a powerful new tool for studying the effects of flows on plasma stability and shape.#PlasmaEquilibrium #MHDEquilibrium #PlasmaFlows #FusionResearch

FLIPEC is a new code that can calculate free-boundary, axisymmetric ideal MHD equilibria with plasma flows. It uses a curvilinear coordinate system to handle complex plasma shapes and coil positions. FLIPEC can also stabilize vertical modes and actively target specific equilibrium configurations.

この論文は、自由境界、軸対称理想MHD平衡を任意の流れ場で計算できる新しいコード「FLIPEC」について説明しています。FLIPEC は、プラズマと外部コイルの距離に制限がなく、垂直不安定性の抑制や目標追跡機能も備えています。ITER標準配位やNSTXスフェリカルトカマクなどの例を示し、その機能を実証しています。