Sliding mode stabilization of the current profile in Tokamak plasmas

Abstract

This paper deals with the robust stabilization of the spatial distribution of the tokamak plasmas current profile using a sliding mode feedback control approach. The control design is based on the 1D resistive diffusion equation of the magnetic flux that governs the plasma current profile evolution. The feedback control law is derived in the infinite dimensional setting without spatial discretisation. Numerical simulations are provided and the tuning of the controller parameters that would reject uncertain perturbations is discussed. Manuscript received March 2, 2011. This work was supported in part by the CEA (Commissariatá l'Energie Atomique) and the French région Pays de Loire. O. Gaye is with LISA (EA 4094

Robust stabilization of the current profile in tokamak plasmas using sliding mode approach in infinite dimension

“…The second boundary condition in (2) ∂ψ ∂t (t, 1) = −V 0 (based on a time derivative) can be also found in numerous references Witrant et al (2007), Argomedo et al (2010), Ouarit et al (2011) and Gaye et al (2011).…”

“…Simulation results, using the METIS (see the work of Artaud (2008)) code dedicated to plasma scenario studies, are provided in section 5. A preliminary version of the proposed results without simulation METIS has been published by Gaye et al (2011). Finally,…”

Robust control of the safety factor profile and stored energy evolutions in high performance burning plasma scenarios in the ITER tokamak

“…The integrated feedback controller (17)-(18) is now tested through simulation with the FPD, physics-based model of the poloidal magnetic flux profile evolution developed in [12] and the volume-averaged plasma energy balance (8) tailored to H-mode burning plasma scenarios in ITER. First, a target q-profile and stored energy evolution is obtained by executing a feedforward-only simulation with a nominal set of input trajectories and initial conditions q nom (ρ,t 0 ) andW nom (t 0 ), where t 0 = 45 sec.…”

Distributed and backstepping boundary controls for port-Hamiltonian systems with symmetries

“…The objective of the control (regulation) is to achieve some non uniform steady state radial flux profiles which help to avoid magneto-hydrodynamic (MHD) instabilities and to improve the plasma confinement. It is one of the control challenges which is frequently studied in the recent tokamak control literature [1], [5], [13]. In [21], the IDA-PBC laws were derived for a finite-dimensional PHS model representing the plasma dynamics.…”