Low Effort<mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" id="M1"><mml:mrow><mml:msub><mml:mrow><mml:mi>L</mml:mi></mml:mrow><mml:mrow><mml:mi>i</mml:mi></mml:mrow></mml:msub></mml:mrow></mml:math>Nuclear Fusion Plasma Control Using Model Predictive Control Laws

Garrido, Izaskun; Garrido, Aitor J.; Romero, Jesús; Carrascal, Edorta; Sevillano, M. Goretti; Barambones, Óscar

doi:10.1155/2015/527420

Cited by 34 publications

(15 citation statements)

References 40 publications

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“…Only the first element of the N c optimal predicted voltage sequence is input back to the plant [17]. This procedure, known as the receding horizon strategy, provides a degree of robustness to modeling errors and uncertainty, since the input at each step takes into account the current state values to compute future events.…”

Section: Model Predictive Control Designmentioning

confidence: 99%

Real-Time Control for the EHU Stellarator

et al. 2019

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At present, two main magnetic confinement fusion devices exist: tokamaks and stellarators. Moreover, stellarators have been demonstrated to be a good alternative to tokamaks, due to their ability to operate in continuous mode, which eventually translates into a higher commercial profitability. In stellarators, the magnetic confinement of the plasma is achieved exclusively by the coils, thus no electric current through the plasma is needed. In particular, this article presents the Columbia Non-Neutral Torus stellarator that is located in the Automatic Control Group of Euskal Herriko Unibertsitatea (EHU). This EHU stellarator maintains symmetry in its structure due to the topology of the mesh that is formed by its coils. A cornerstone of future fusion reactors is to obtain real-time control that enables a sustained reaction. In this article, a control-oriented model for the installed magnetic confinement coils is presented. The model is based on matrices that preserve symmetry, which is defined from physical principles and then validated by different sets of experimental data. Then, based on this model, a novel predictive control suited to this particular model with symmetric objective function is implemented in the numerical simulations, and its response is compared to that of traditional controllers. Finally, this control is implemented in a real plant and the satisfactory experiment results provide validation of both the numerical model and proposed controller.

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Section: Model Predictive Control Designmentioning

confidence: 99%

Real-Time Control for the EHU Stellarator

et al. 2019

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“…It has been determined that the internal circuit of the stellarator can be represented by the following lumped parameter electrical system (Figure 2). This lumped parameter approach is widely employed when in fusion devices [7][8][9]:…”

Section: System Modellingmentioning

confidence: 99%

“…There exist different control approaches for this purpose, being the most used traditional PID-based schemes, robust (sliding-mode) schemes and MPC schemes [11][12][13][14][15][16][17][18][19][20][21][22][23]. In particular, when dealing with fusion devices where the available energy is limited, MPC is especially interesting due to its ability to ensure that both the control action and the solution error are minimal [9].…”

Section: Controller Descriptionmentioning

confidence: 99%

State-space Coil Modelling in Plasma Magnetic Confinement Devices

Garrido

González

et al. 2017

MATEC Web Conf.

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Abstract. The need of robust and optimal control schemes is a key factor for the development of future fusion reactors. This paper has dealt with the state-space modelling of the Ultra-Low Iota Super Elongated Stellarator of the UPV/EHU, using a physical lumped parameter equivalent circuit approach. The model obtained has been validated by means of experimental output data showing an excellent matching with the real system. Besides, it has been designed a MPC scheme that has been successfully implemented both in simulation and experimentally using a real-time control platform.

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“…The intrinsic minimization of the MPC further reduces the current drive source requirements [31]. Therefore, MPC composes an excellent control option since it not only considers the information related to the system at an operation instant as in other advanced controllers [32,33], but also takes into account the predicted future information so as to obtain an optimal control action.…”

Section: Introductionmentioning

confidence: 99%

“…Furthermore, the Ohmic Heating (OH) coil may reduce the power requirements of the non-inductive current drive sources required for current profile control due to its ability to transiently manipulate the low order moments of the current profile. Until recently, this line of research [31][32][33] had been carried out with plant models of the type described in [34], which are two orders of magnitude smaller than the RZIp model. These models are excellent for real time control algorithms although the underlying plasma physics are reflected in a limited manner.…”

Section: Introductionmentioning

confidence: 99%

Real Time Hybrid Model Predictive Control for the Current Profile of the Tokamak à Configuration Variable (TCV)

Garrido

Coda

et al. 2016

Energies

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Plasma stability is one of the obstacles in the path to the successful operation of fusion devices. Numerical control-oriented codes as it is the case of the widely accepted RZIp may be used within Tokamak simulations. The novelty of this article relies in the hierarchical development of a dynamic control loop. It is based on a current profile Model Predictive Control (MPC) algorithm within a multiloop structure, where a MPC is developed at each step so as to improve the Proportional Integral Derivative (PID) global scheme. The inner control loop is composed of a PID-based controller that acts over the Multiple Input Multiple Output (MIMO) system resulting from the RZIp plasma model of the Tokamak à Configuration Variable (TCV). The coefficients of this PID controller are initially tuned using an eigenmode reduction over the passive structure model. The control action corresponding to the state of interest is then optimized in the outer MPC loop. For the sake of comparison, both the traditionally used PID global controller as well as the multiloop enhanced MPC are applied to the same TCV shot. The results show that the proposed control algorithm presents a superior performance over the conventional PID algorithm in terms of convergence. Furthermore, this enhanced MPC algorithm contributes to extend the discharge length and to overcome the limited power availability restrictions that hinder the performance of advanced tokamaks.

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Low EffortLiNuclear Fusion Plasma Control Using Model Predictive Control Laws

Cited by 34 publications

References 40 publications

Real-Time Control for the EHU Stellarator

Real-Time Control for the EHU Stellarator

State-space Coil Modelling in Plasma Magnetic Confinement Devices

Real Time Hybrid Model Predictive Control for the Current Profile of the Tokamak à Configuration Variable (TCV)

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