Publication

Digital Control System for Vertical Stability of the TCV Plasma

2014
Non-EPFL thesis
Abstract

In advanced mode operation of fusion devices, real time control plays a central role in achieving the desired plasma performance and minimizing the risk of disruptions. With the advances in digital technologies like Digital Signal Processors (DSPs), Field Programmable Gate Arrays (FPGAs) and standard commercial computer processors, the development of digital control systems to use in fusion experiments has spread to all modern tokamaks. Tokamak à Configuration Variable (TCV) had limited control capabilities due to the utilization of an analogue control system. In the first part of the PhD Program an Advanced Plasma Control System (APCS), capable of improving the capacity of control of highly configurable plasma shapes, position, current and density by the introduction of nonlinear digital controllers, was designed, implemented and integrated in TCV. Early tokamaks with circular cross-section plasmas were not prone to the vertical plasma column instability, an inherent problem arising in plasmas with vertically elongated cross sections, with benefits to the energy confinement time, increased plasma current and beta. To overcome this problem, complex closed feedback loop control systems with a vertical position measurement, signal processing, control algorithm, power supplies and active actuating coils are used. In the second part of the PhD Program a predictive vertical stabilization non-linear digital controller was designed and implemented, with the help of a new mathematical simulator based on a rigid plasma model. The layout of a method to define controllable limits for the plasma position and velocity may be used for the design of new control systems. Evidence is presented of the TCV vertical stability enhancement using the implemented controller during experimental tokamak discharges.

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Ontological neighbourhood
Related concepts (31)
Magnetic confinement fusion
Magnetic confinement fusion is an approach to generate thermonuclear fusion power that uses magnetic fields to confine fusion fuel in the form of a plasma. Magnetic confinement is one of two major branches of fusion energy research, along with inertial confinement fusion. The magnetic approach began in the 1940s and absorbed the majority of subsequent development. Fusion reactions combine light atomic nuclei such as hydrogen to form heavier ones such as helium, producing energy.
Tokamak
A tokamak (ˈtoʊkəmæk; токамáк) is a device which uses a powerful magnetic field to confine plasma in the shape of a torus. The tokamak is one of several types of magnetic confinement devices being developed to produce controlled thermonuclear fusion power. , it was the leading candidate for a practical fusion reactor. Tokamaks were initially conceptualized in the 1950s by Soviet physicists Igor Tamm and Andrei Sakharov, inspired by a letter by Oleg Lavrentiev. The first working tokamak was attributed to the work of Natan Yavlinsky on the T-1 in 1958.
Fusion power
Fusion power is a proposed form of power generation that would generate electricity by using heat from nuclear fusion reactions. In a fusion process, two lighter atomic nuclei combine to form a heavier nucleus, while releasing energy. Devices designed to harness this energy are known as fusion reactors. Research into fusion reactors began in the 1940s, but as of 2023, no device has reached net power. Fusion processes require fuel and a confined environment with sufficient temperature, pressure, and confinement time to create a plasma in which fusion can occur.
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