The power supply system of RFX

Maschio, Alvise; Piovan, R.; Benfatto, I.; Collarin, P.; Lorenzi, A. De; Fellin, L.; Gaio, E.; Gray, Jonathan; Hood, M.; Toigo, V.

doi:10.1016/0920-3796(94)00282-c

Cited by 29 publications

(7 citation statements)

References 8 publications

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“…For the shots shown in this paper the electrode insertion was 7 cm inside the LCFS in both circular and SN plasma poloidal shaping. The biasing circuit scheme is also shown in fig.1 The electrode has been fed using one of the main power supplies of the machine, a single quadrant 6 phases regulated bridge [16]. An L-R network is used to filter the fire sequence of the thyristors as shown in Fig.…”

Section: Methodsmentioning

confidence: 99%

H-mode achievement and edge features in RFX-mod tokamak operation

Spolaore¹,

Cavazzana²,

Marrelli³

et al. 2017

Nucl. Fusion

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The RFX-Mod experiment is a fusion device designed to operate as a Reversed Field Pinch (RFP), with a major radius R " 2 m and a minor radius a " 0.459 m. Its high versatility recently allowed operating also as an ohmic tokamak allowing comparative studies between the two configurations in the same device. The device is equipped with a state of the art MHD mode feedback control system, providing a magnetic boundary effective control and modulation, by applying resonant or nonresonant magnetic perturbations (MP) both in RFP and in tokamak configurations. In the fusion community the application of MPs is widely studied as a promising tool in particular to limit the impact of plasma filaments and ELMs, in particular on plasma facing components. An important issue is envisaged in the exploitation of the RFX-Mod active control system for ELM mitigation studies.As a first step in this direction, this paper will focus on the most recent achievements in term of RFX-Mod tokamak explored scenarios, which allowed the first investigation of the ohmic and edge biasing induced H-mode. In particular the realization of D-shaped tokamak discharges and the design and deployment of an insertable polarized electrode were accomplished. Both operations took advantage of the implementation of a real-time feedback control system of the electron density and of a multivariable shape feedback control system designed on a full modelbased approach. Indications of Ohmic H-mode were transiently observed during Single Null shaped plasmas. Stationary H-mode phases were instead obtained with insertable electrode biasing stimulation. The edge biasing is applied in new operation scenarios relatively unexplored with this technique in particular in plasma shaped Single Null discharges and in the very low-q circular plasma discharges, qpaq ă 2, achievable in RFX-Mod. Important modification of the edge plasma density and flow properties are observed as well as, in some cases, a complex "dithering" phenomenology, characterized by very fast L-H and H-L transitions. These strong fluctuations appear associated to the onset of MHD activity, whose behaviour will be analyzed and discussed in the paper along with the filamentary structures observed in the fast turbulence electromagnetic fluctuations.Published as a journal article in Nuclear Fusion http://iopscience.iop.org/article/Abstract The RFX-mod experiment is a fusion device designed to operate as a Reversed Field Pinch (RFP), with a major radius R= 2 m and a minor radius a = 0.459 m. Its high versatility recently allowed operating also as an ohmic tokamak allowing comparative studies between the two configurations in the same device. The device is equipped with a state of the art MHD mode feedback control system, providing a magnetic boundary effective control, by applying resonant or non-resonant magnetic perturbations (MP) both in RFP and in tokamak configurations. In the fusion community the application of MPs is widely studied as a promising tool to limit the impact of plasma filaments and ELMs on p...

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Section: Methodsmentioning

confidence: 99%

H-mode achievement and edge features in RFX-mod tokamak operation

Spolaore¹,

Cavazzana²,

Marrelli³

et al. 2017

Nucl. Fusion

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“…The RFX poloidal magnetic system [7] includes the Field Shaping (FS) coils and the Magnetizing Winding (MW) along with three conducting structures surrounding the plasma: vacuum vessel, thin copper shell and supporting structure, as sketched in Fig. 1.…”

Section: Model Descriptionmentioning

confidence: 99%

Adaptive plasma current control in RFX-mod

Bettini

Blanchini

Cavazzana

et al. 2011

Fusion Engineering and Design

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“…1, including the Ohmic field coils (OH1-OH13), the EQ coils (EQ1-EQ6), the Toroidal Field (TF) coils and passive conductor (the stabilizing copper shell and vessel) around the plasma. The detailed KTX PF coil parameters [10] are listed in t Table 1 and Table 2. Table 1 and Table 2 respectively show the geometric parameters of Ohmic coils and EQ coils.…”

Section: Poloidal Field System Of Ktxmentioning

confidence: 99%

“…As a result, it is a large technical difficulty to design the EQ coils power. Considering the design ideas [10] of RFX [11] , the packet connection of PF coils is meant to avoid the surge voltage in EQ coils. The PF coils circuit connections diagram [1,9] is shown in Fig.…”

Section: The Couple Between Pf Coils and Plasmamentioning

confidence: 99%

Capability Assessment of the Equilibrium Field System in KTX

Luo

Xiao

et al. 2016

Plasma Sci. Technol.

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Radial equilibrium of the KTX plasma column is maintained by the vertical field which is produced by the equilibrium field coils. The equilibrium is also affected by the eddy current, which is generated by the coupling of copper shell, plasma and poloidal field coils. An equivalent circuit model is developed to analyze the dynamic performance of equilibrium field coils, without auxiliary power input to equilibrium field coils and passive conductors. Considering the coupling of poloidal field coils, copper shell and plasma, the evolution of spatial distribution of the eddy current density on the copper shell is estimated by finite element to analyze the effect of shell to balance. The simulation results show that the copper shell and equilibrium field coils can provide enough vertical field to balance 1 MA plasma current in phase 1 of a KTX discharge. Auxiliary power supply on the EQ coils is necessary to control the horizontal displacement of KTX due to the finite resistance effect of the shell.

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The power supply system of RFX

Cited by 29 publications

References 8 publications

H-mode achievement and edge features in RFX-mod tokamak operation

H-mode achievement and edge features in RFX-mod tokamak operation

Adaptive plasma current control in RFX-mod

Capability Assessment of the Equilibrium Field System in KTX

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