In this paper, DEMO-like shaped plasma equilibria are defined for RFX-mod2 tokamak operations by using the Inverse Equilibrium Tool (IET code). IET allows for the computation of the coil currents needed to obtain a predetermined plasma shape with well defined plasma global parameters (i.e. total plasma current and total poloidal magnetic flux at the boundary) by solving a constrained minimization problem. The new shape conditions would allow achieving higher plasma current and plasma density values at the same toroidal magnetic field and safety factor limits of previous RFX-mod tokamak operations. The feasibility of these new equilibria is explored in terms of coil current requirements and vertical stability analysis. This study shows that RFX-mod2 is a flexible device, able to perform DEMO-like shaped tokamak operations with low requirements on both magnitude and distribution of active coil currents.

中文翻译：

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使用类似 DEMO 的形状条件和负三角形对 RFX-mod2 托卡马克平衡进行建模

在本文中，使用逆平衡工具（IET 代码）为 RFX-mod2 托卡马克操作定义了类似 DEMO 形状的等离子体平衡。IET 允许通过解决约束最小化问题来计算获得具有明确定义的等离子体全局参数（即边界处的总等离子体电流和总极向磁通量）的预定等离子体形状所需的线圈电流。新的形状条件将允许在与先前 RFX-mod 托卡马克操作相同的环形磁场和安全系数限制下实现更高的等离子体电流和等离子体密度值。在线圈电流要求和垂直稳定性分析方面探索了这些新平衡的可行性。这项研究表明 RFX-mod2 是一种灵活的设备，