RFX-mod is a flexible experiment, equipped with a full coverage MHD control system, composed by 192 (48 toroidal x 4 poloidal) coils. Being built as a high current RFP (a/R = 0.46m/2.0m; Ip max 2 MA) it has recently operated also as a low current circular tokamak ( Bt = 0.45 T; Ip 85 kA @ q(a) ~ 3 ; Ip 150 kA @ q(a) ~ 2), achieving the full stabilization of m=2, n=1 mode at q(a) ~ 2. In order to extend the significance of MHD control experiments, there arose the need of creating non circular shaped discharges, exploiting the flexibility of the 16 shaping coils of the machine. Plasma of with moderate elliptical and triangular shape can be obtained both in tokamak and RFP configuration. Moreover tokamak D-shaped plasmas with double X-point have been obtained by proper reconfiguration of the power supply. The design structure and the experimental performance of the new shape reconstruction, plasma position and shape real-time control algorithms, tested in both RFP and tokamak configuration, are presented and discussed, along with some preliminary results of the MHD mode interaction and control behavior with the modified plasma shapes.
Multi configuration axysimmetric plasma shaping control on RFX-mod
G Marchiori;G Manduchi;M Zuin;L Marrelli;
2013
Abstract
RFX-mod is a flexible experiment, equipped with a full coverage MHD control system, composed by 192 (48 toroidal x 4 poloidal) coils. Being built as a high current RFP (a/R = 0.46m/2.0m; Ip max 2 MA) it has recently operated also as a low current circular tokamak ( Bt = 0.45 T; Ip 85 kA @ q(a) ~ 3 ; Ip 150 kA @ q(a) ~ 2), achieving the full stabilization of m=2, n=1 mode at q(a) ~ 2. In order to extend the significance of MHD control experiments, there arose the need of creating non circular shaped discharges, exploiting the flexibility of the 16 shaping coils of the machine. Plasma of with moderate elliptical and triangular shape can be obtained both in tokamak and RFP configuration. Moreover tokamak D-shaped plasmas with double X-point have been obtained by proper reconfiguration of the power supply. The design structure and the experimental performance of the new shape reconstruction, plasma position and shape real-time control algorithms, tested in both RFP and tokamak configuration, are presented and discussed, along with some preliminary results of the MHD mode interaction and control behavior with the modified plasma shapes.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
