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.
2002
Istituto gas ionizzati - IGI - Sede Padova
9
1102
1109
Nuclear fusion,
plasma physics,
magnetohydrodinamic,
instabilities,
active control
The paper is a result of the joint work of scientists operating at Consorzio RFX, which is one of the Italian Research Units part of the European Program on Controlled Thermonuclear Fusion. In Consorzio RFX scientists from CNR, ENEA and Padova University operate jointly. The RFX experiment, operative in Padova since 1992, is the world most important Reversed Field Pinch. This configuration is extensively studied in Europe, USA and Japan, due to its physical interest and its reactorial perspectives. The work was done in collaboration with the prof. A. Bondeson’s group at Chalmers Institute of Technology (Goeteborg, Sweden) one of the worldwide more quoted theoretical groups in this area. The paper is published by the famous journal Nuclear Fusion, edited by the International Atomic Energy Agency. Some of the predictions of the model have been confirmed experimentally in the Swedish Reversed Field Pinch device EXTRAP T2R operating at the Stockholm Royal Institute of Technology (KTH).
3
info:eu-repo/semantics/article
262
Paccagnella, R; Gregoratto, D; Bondeson, A
01 Contributo su Rivista::01.01 Articolo in rivista
none
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/25384
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