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.
2013
Istituto gas ionizzati - IGI - Sede Padova
Inglese
Bulletin of the American Physical Society - 55th Annual Meeting of the APS Division of Plasma Physics
55th Annual Meeting of the APS Division of Plasma Physics
http://meetings.aps.org/Meeting/DPP13/Event/200182
November 11-15, 2013
Denver, Colorado, USA
Session CP8: Poster Session II: Astro, Simulations, RFP, Tokamak, Stellarator; Abstract: CP8.00101. Il periodico esiste dal 1925, con ISSN 0003-0503, come risulta dal record ACNP. Il record ISSN invece non è attualizzato.
12
info:eu-repo/semantics/conferenceObject
none
274
04 Contributo in convegno::04.02 Abstract in Atti di convegno
Cavazzana, R; Finotti, C; Marchiori, G; Manduchi, G; Zanotto, L; Kudlacek, O; Zuin, M; Franz, P; Zanca, P; Marrelli, L; Luce, Tc; Jackson, Gl
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/254467
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