Overall plant design, layout and commissioning

Fellin, L.; Kusstatscher, Peter; Rostagni, G.

doi:10.1016/0920-3796(94)00279-g

Cited by 31 publications

(19 citation statements)

References 3 publications

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“…On one hand, the inward directed radial electric field found at the edge could be interpreted as a proof of a nonstochastic behavior of the magnetic field lines. On the other hand, in some experiments the presence of superthermal electrons at the edge has been interpreted as a proof of the extension of this stochastic region up to the wall [9,14,15].In this Letter, we report the edge structure of the plasma potential in the RFX reversed field pinch experiment (R 2 m, a 0.457 m) [16]. Our results suggest that the negative E r at the edge is due to FLR losses.…”

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confidence: 73%

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Plasma Potential Well and Velocity Shear Layer at the Edge of Reversed Field Pinch Plasmas

Antoni¹,

Desideri²,

Martines³

et al. 1997

Phys. Rev. Lett.

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The first evidence of an electrostatic potential well at the edge of plasmas confined in a reversed field pinch configuration is reported, based on measurements made on the RFX experiment. The radial width of the well decreases with plasma current, whereas the potential drop is a few times the electron temperature at the edge, almost independent of plasma current. The resulting radial electric field points inward at the edge and this behavior has been related to finite Larmor radius losses as in tokamaks. Because of the spatial structure of the plasma potential, a naturally occurring double velocity shear layer has been identified at the edge with a shear value comparable to that of tokamaks and stellarators

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mentioning

confidence: 73%

“…In this Letter, we report the edge structure of the plasma potential in the RFX reversed field pinch experiment (R 2 m, a 0.457 m) [16]. Our results suggest that the negative E r at the edge is due to FLR losses.…”

mentioning

confidence: 76%

Plasma Potential Well and Velocity Shear Layer at the Edge of Reversed Field Pinch Plasmas

Antoni¹,

Desideri²,

Martines³

et al. 1997

Phys. Rev. Lett.

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“…For B P ϭ0.8 T, corresponding on RFX to the 2 MA design maximum value of the toroidal plasma current, 5 it results in t F Ϸ15 ms, the value which has been accepted for the project. For B P ϭ0.8 T, corresponding on RFX to the 2 MA design maximum value of the toroidal plasma current, 5 it results in t F Ϸ15 ms, the value which has been accepted for the project.…”

Section: Experimental Equipment: Design Considerationsmentioning

confidence: 99%

“…5 In Sec. A new one has been developed for the RFP experiment RFX ͑major radius Rϭ2 m; minor radius aϭ0.457 m͒.…”

Section: Introductionmentioning

confidence: 99%

A fast moving diagnostic system on the RFX experiment

Desideri¹,

Serianni²,

Antoni³

et al. 1999

Review of Scientific Instruments

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A fast rotating graphite arm equipped with two Langmuir probes has been developed to investigate the temperature, density, and plasma potential profiles at the edge in the reversed field pinch experiment RFX. The system, driven by an electromagnetic torque, allows a 5 cm radial insertion in about 20 ms with a magnetic field of 0.3 T. The motion of the arm takes place on a plane having an angle of 45° with respect to the direction of the poloidal magnetic field. The probe collecting area is constant during the movement. The initial and final positions of the graphite arm are monitored by electrical contacts. To reconstruct the motion of the equipment, an equivalent lumped-constant network has been developed. The equivalent resistance and inductance are measured before each discharge. By this system radially resolved measurements of edge plasma parameters in a single RFX plasma discharge have been obtained

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“…To perform these measurements in RFX [3], the highest current RFP experiment nowadays in operation (major radius R = 2 m, minor radius a = 0.457 m, target plasma current I = 2 MA), a 8 chord -pinhole camera [4], housing miniaturised metal foil bolometers [5], was installed. These detectors, which, thank to their accuracy and reliability, are becoming a standard for total radiation measurements in fusion experiments and are used in the major tokamak and stellarator experiments, such as Tore-Supra [6], JET [7], Asdex-U [8] and FTU [9], were calibrated absolutely in situ, whereas the nominal gain of the amplifiers was doublechecked on the bench before installation, in order to ensure the precision of the measurements.…”

Section: Introductionmentioning

confidence: 99%

Total radiation losses and emissivity profiles in RFX

Marrelli¹,

Martin

Murari

et al. 1998

Nucl. Fusion

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Abstract.The radiation emitted by RFX plasmas has been investigated using a 8 chord-bolometric camera, whose detectors have been calibrated absolutely. From the experimental data the emissivity profiles have been reconstructed by means of a generalized tomography reconstruction algorithm. This analysis confirms that the emitted radiation in RFX is systematically concentrated at the edge. The emitted power dependence on the plasma density shows that the radiation increases approaching the high density regime, but it rarely goes beyond 30% of the input power for stationary discharges. This behaviour is strongly dependent on the concentration of impurities, but in any case in RFX there is no evidence of disruptions. A simple local energy balance allows to obtain a preliminary evaluation of the radial heat flux profile.

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Overall plant design, layout and commissioning

Cited by 31 publications

References 3 publications

Plasma Potential Well and Velocity Shear Layer at the Edge of Reversed Field Pinch Plasmas

Plasma Potential Well and Velocity Shear Layer at the Edge of Reversed Field Pinch Plasmas

A fast moving diagnostic system on the RFX experiment

Total radiation losses and emissivity profiles in RFX

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