We focus on the estimation of the minimum poloidal field coil voltages for the plasma shape control in a tokamak. For given coil locations and for a class of disturbances we propose a procedure for the evaluation of the minimum voltages needed to guarantee that the plasma boundary displacement remains within specified limits. The impact of this problem on the minimization of the power supply cost is discussed for the case of the International Thermonuclear Experimental Reactor (ITER
The eXtreme Shape Controller, designed and implemented on the JET tokamak, was described. The contro...
The plasma in a tokamak is magnetically confined through electromagnetic fields generated by a set o...
An advanced tokamak plasma configuration is developed based on equilibrium, ideal-MHD stability, boo...
We focus on the estimation of the minimum poloidal field coil voltages for the plasma shape control ...
International audienceThis paper presents the modelling of the evolution of plasma equilibrium in th...
International audienceThis paper presents the modelling of the evolution of plasma equilibrium in th...
The paper deals with the application of the so-called Reference (or Command) Governor constrained co...
Poloidal field magnetic control in tokamak has the essential functions of stabilizing the vertical i...
In this paper we present an approach for the design of a plasma current and shape feedback control s...
The International Thermonuclear Experimental Reactor (ITER) is the next step toward the realization ...
The International Thermonuclear Experimental Reactor (ITER) is the next step toward the realization ...
This paper is focused on the plasma shape and current control in a large, next generation tokamak ch...
The capability of the poloidal field coil system, as presently designed, to provide an effective ver...
This paper is focused on the plasma shape and current control in a large, next generation tokamak ch...
This paper presents an application of a novel constrained control methodology known as Command Gover...
The eXtreme Shape Controller, designed and implemented on the JET tokamak, was described. The contro...
The plasma in a tokamak is magnetically confined through electromagnetic fields generated by a set o...
An advanced tokamak plasma configuration is developed based on equilibrium, ideal-MHD stability, boo...
We focus on the estimation of the minimum poloidal field coil voltages for the plasma shape control ...
International audienceThis paper presents the modelling of the evolution of plasma equilibrium in th...
International audienceThis paper presents the modelling of the evolution of plasma equilibrium in th...
The paper deals with the application of the so-called Reference (or Command) Governor constrained co...
Poloidal field magnetic control in tokamak has the essential functions of stabilizing the vertical i...
In this paper we present an approach for the design of a plasma current and shape feedback control s...
The International Thermonuclear Experimental Reactor (ITER) is the next step toward the realization ...
The International Thermonuclear Experimental Reactor (ITER) is the next step toward the realization ...
This paper is focused on the plasma shape and current control in a large, next generation tokamak ch...
The capability of the poloidal field coil system, as presently designed, to provide an effective ver...
This paper is focused on the plasma shape and current control in a large, next generation tokamak ch...
This paper presents an application of a novel constrained control methodology known as Command Gover...
The eXtreme Shape Controller, designed and implemented on the JET tokamak, was described. The contro...
The plasma in a tokamak is magnetically confined through electromagnetic fields generated by a set o...
An advanced tokamak plasma configuration is developed based on equilibrium, ideal-MHD stability, boo...