1,721,072 research outputs found
Derivation of free boundary equilibrium linear models by a flux perturbation method
A new method to derive linear models of the axisymmetric plasma dynamic is detailed. The method follows the modified inductance approach but adopts a different set of independent variables to perturb the equilibrium. This different basis permits one to reduce the numerical computation of the model and has revealed an interesting property of the inverse inductance matrix whose elements are influenced by the plasma only if they refer to circuits facing directly the plasma column. In terms of approximations, the method proposed is equivalent to the standard modified inductance method but has the additional advantage of ensuring numerical convergence of the perturbed equilibria and therefore it allows using Picard based numerical Grad-Shafranov solvers. A linear model of the RFX-mod machine was derived with this approach and it was validated against the experiment
Electromagnetic analysis of the new ITER blanket modules for vertical passive stabilization
Model reduction techniques in tokamak modelling
In present tokamak experiments, there is the need of sufficiently detailed models describing the plasma behaviour and its electromagnetic coupling with the active and metallic structures for simulation and control design. The required level of detail yields linearized model of the system at particular working points of very high order, thus complicating the design of controllers of the position and shape of the plasma. In this paper, several model reduction techniques which are available from linear state-space control theory are considered with application to tokamak modelling. In particular, a technique based on selective modal analysis is proposed, and its effectiveness in approximating the overall system behaviour while retaining the physical meaning of the state variables is show
Optimization of the Power Supply Demand for Plasma Shape Control in a Tokamak
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
Model reduction for electromechanical systems with application to tokamak control," in Advances in Systems Science: Measurements, Circuits and Control
Electrical and Computer Engineering Serie
Plasma current and shape control in tokamaks using H-infinity synthesis
This paper is focused on the plasma shape and current control in a large, next generation tokamak characterized by long-duration plasma discharges. The new features of these fusion devices are described and their impact on the feedback control requirements are investigated. Many of the controller design issues are addressed in the H∞/Î1⁄4 synthesis framework, including the model reduction, the power constraints, the voltage limits and plant uncertainties. The application to the case of the International Thermonuclear Experimental Reactor (ITER) shows the effectiveness of this approach for the design of plasma controllers
Model reduction for electromechanical systems with application to tokamak control," in Advances in Systems Science: Measurements, Circuits and Control
Electrical and Computer Engineering Serie
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