Feedback stabilization of magnetohydrodynamical modes in reversed field pinches is studied in cylindrical geometry, taking into account a finite number of coils, both in poloidal and toroidal directions. The robustness and stability of the feedback scheme is analysed by means of Nyquist diagrams for different arrangements of the feedback coils and magnetic sensors. The feedback can be adversely affected by the coupling of different Fourier components from the discrete coils, and configurations are sought where this coupling does not seriously degrade the performance. The requirements on the feedback system are discussed for different cases and low gain solutions are identified. We remark that the theoretical investigation of the possibility of active controlling these plasma modes is very important in order to access the fusion perspectives of the magnetic confinement schemes. This work is therefore at the front end of the research in this area and propose a very useful approach to the problem. The work is specifically oriented to the Reversed Field Pinch configuration but can found applications also for other devices, like tokamaks. For example applications to the next generation devices like the International Thermonuclear Experimental Reactor (ITER) are possible.
Feedback control of resistive wall modes in reversed field pinches
R Paccagnella;
2002
Abstract
Feedback stabilization of magnetohydrodynamical modes in reversed field pinches is studied in cylindrical geometry, taking into account a finite number of coils, both in poloidal and toroidal directions. The robustness and stability of the feedback scheme is analysed by means of Nyquist diagrams for different arrangements of the feedback coils and magnetic sensors. The feedback can be adversely affected by the coupling of different Fourier components from the discrete coils, and configurations are sought where this coupling does not seriously degrade the performance. The requirements on the feedback system are discussed for different cases and low gain solutions are identified. We remark that the theoretical investigation of the possibility of active controlling these plasma modes is very important in order to access the fusion perspectives of the magnetic confinement schemes. This work is therefore at the front end of the research in this area and propose a very useful approach to the problem. The work is specifically oriented to the Reversed Field Pinch configuration but can found applications also for other devices, like tokamaks. For example applications to the next generation devices like the International Thermonuclear Experimental Reactor (ITER) are possible.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
