Physics basis for design of 3D coils in tokamaks. (9th June 2021)

• Record Type: Journal Article
• Authors: Logan, N.C.; Zhu, C.; Park, J.-K.; Yang, S.M.; Hu, Q.
• Is Part Of: Nuclear fusion. Volume 61:Number 7(2021)
• Publication Date: 2021-06-09
• Subjects: tokamak error field -- resonant magnetic perturbation (RMP) -- neoclassical toroidal viscosity (NTV); Nuclear fusion -- Periodicals; 621.48405
• DOI: 10.1088/1741-4326/abff05
• Languages: English
• ISSNs: 0029-5515

Abstract

Abstract: Recent progress in 3D tokamak modeling is now leveraged to create a conceptual design of new external 3D field coils for the DIII-D tokamak. In this work generalized perturbed equilibrium code is used to determine optimally efficient spectrum for driving total, core, and edge neoclassical toroidal viscosity torque. These fundamental modes of 3D control are shown to have consistent outboard structures across a wide variety of plasma scenarios and machines. Given these target spectra, the currents and 3D geometry of multiple coils can be optimized to increase efficient drive for the physics of interest without undesired secondary effects. Here, this nonlinear optimization is demonstrated using the flexible optimized coils using space-curves code. The optimized coils are individually distorted in space, creating toroidal 'arrays' containing a variety of shapes that often wrap around a significant poloidal extent of the machine. Importantly, efficient coupling can be maintained even when enforcing large distances between coils and the plasma during the geometric optimization of coil designs. The physics-driven optimization presented here thus provides a practical path to utilizing coils built on the exterior of the vacuum chamber in future reactors to obtain the powerful 3D field benefits demonstrated on current machines with close, internal coils.