Electromagnetic System Conceptual Design for a Negative Triangularity Tokamak

TL;DR

This paper presents a detailed electromagnetic design for a compact negative triangularity tokamak aimed at testing control software and understanding NT operation, utilizing existing copper magnet technology.

Contribution

It introduces a pre-conceptual design of a negative triangularity tokamak with specific coil configurations and stability measures, advancing NT device development.

Findings

Achieves a wide range of plasma geometries with specified triangularity and elongation.

Demonstrates passive stabilization reduces vertical instability growth rates by approximately 75%.

Predicts mechanical loads on coils and passive structures during disruptions.

Abstract

Negative triangularity (NT) tokamak configurations have several key benefits including sufficient core confinement, improved power handling, and reduced edge pressure gradients that allow for edge-localized mode (ELM) free operation. We present the design of a compact NT device for testing sophisticated simulation and control software, with the aim of demonstrating NT controllability and informing power plant operation. The TokaMaker code is used to develop the basic electromagnetic system of the $R_0$ = 1 m, $a$ = 0.27 m, $B_t$ = 3 T, $I_p$ = 0.75 MA tokamak. The proposed design utilizes eight poloidal field coils with maximum currents of 1 MA to achieve a wide range of plasma geometries with $-0.7 < \delta < -0.3$ and $1.5 < \kappa < 1.9$. Scenarios with strong negative triangularity and high elongation are particularly susceptible to vertical instability, necessitating the inclusion of high-field side and/or low-field side passive stabilizing plates which together reduce vertical instability growth rates by $\approx$75%. Upper limits for the forces on poloidal and toroidal field coils are predicted and mechanical loads on passive structures during current quench events are assessed. The 3 T on-axis toroidal field is achieved with 16 demountable copper toroidal field coils, allowing for easy maintenance of the vacuum vessel and poloidal field coils. This pre-conceptual design study demonstrates that the key capabilities required of a dedicated NT tokamak experiment can be realized with existing copper magnet technologies.