Control of plasma parameters by the externally applied toroidal field in RFX-mod

被引：4

作者：

Cavinato, M. ^{[1
]}

Cavazzana, R. ^{[1
]}

Luchetta, A. ^{[1
]}

Manduchi, G. ^{[1
]}

Marchiori, G. ^{[1
]}

Soppelsa, A. ^{[2
]}

Spolaore, M. ^{[1
]}

Taliercio, C. ^{[1
]}

机构：

[1] Assoc Euratom ENEA Fusione, Consorzio RFX, Corso Stati Uniti 4, I-35127 Padua, Italy

[2] Univ Padua, Dept Elect Engn, I-35100 Padua, Italy

来源：

FUSION ENGINEERING AND DESIGN | 2008年 / 83卷 / 2-3期

关键词：

plasma control; RFP; power supplies;

D O I：

10.1016/j.fusengdes.2007.12.017

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The recent modifications brought to the RFX experiment, now RFX-mod, pose a strong focus on the active control of the plasma magnetic configuration. The new machine layout features a thin stabilizing shell which makes active control feasible and necessary at the same time. The new set of actuators includes a complex saddle coils system and a redesigned power supply system driving the toroidal field coils. The new toroidal power supply system allows a great flexibility since each sector, composed by four coils, is driven by an independent d.c./d.c. switching converter, in series with the main power supply providing the bias current. The current control on the load, performed by the four quadrant fast switching converter, allows producing the desired waveforms of toroidal field. To fully exploit the capabilities of such a system two different controllers have been designed enabling to track automatically a selected evolution of either the toroidal field at the plasma edge or the reversal F parameter, respectively. The new control systems allow to perform experiments in specified plasma configurations targeting particular physics issues and improved the overall reproducibility of the RFX-mod discharges. (c) 2007 Elsevier B.V. All rights reserved.

引用

页码：220 / 223

页数：4

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