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Nuclear Fusion | 1991

Plasma fluctuations near the shear layer in the ATF torsatron

C. Hidalgo; J. H. Harris; T. Uckan; J. D. Bell; B. A. Carreras; J.L. Dunlap; G. R. Dyer; Ch. P. Ritz; A. J. Wootton; M.A. Meier; T.L. Rhodes; K. Carter

Electrostatic turbulence has been investigated in the edge region of the Advanced Toroidal Facility (ATF). A reversal in the poloidal phase velocity of the fluctuations has been observed (velocity shear) which determines a characteristic plasma radius. The location of this shear layer depends on the magnetic configuration, the limiter radius and the plasma conditions. Using the shear position as a reference point, the density fluctuation levels in ATF (currentless stellarator) are very similar to those previously reported in TEXT (ohmically heated tokamak), suggesting that the plasma current is not an important drive for the edge turbulence. The drives for the turbulence appear to be different inside and outside the shear location (ashear), with e/Te 1) and possibly larger e/Te in the plasma edge edge (r/ashear < 1). There is a spatial decorrelation in the fluctuations at the shear location; this suggests that the poloidal shear flow has an important influence on the edge turbulence. The poloidal correlation length depends on local plasma parameters (e.g. velocity and temperature). When neutral beam injection is added, the high frequency components of n increase.


Physics of fluids. B, Plasma physics | 1991

Characteristics of edge plasma turbulence on the ATF torsatron

T. Uckan; C. Hidalgo; J. D. Bell; J. H. Harris; J.L. Dunlap; J. B. Wilgen; Ch. P. Ritz; T.L. Rhodes; A. J. Wootton

Measurements of electrostatic fluctuations on the edge of the Advanced Toroidal Facility (ATF) torsatron [Fusion Technol. 10, 179 (1986)] are used to study the role of the edge turbulence in the particle transport in this current‐free magnetic configuration. Spatial profiles of the plasma electron density ne, temperature Te, and fluctuations in density (ne) and in the plasma floating potential (φf ) are measured at the edge in electron cyclotron heated plasmas using a Langmuir probe array. At the last closed flux surface (LCFS), r/a≊1, Te≊20–40 eV, and ne≊1012 cm−3 for a line‐averaged electron density ne=(3–6)×1012 cm−3. The relative fluctuation levels decrease as the probe is moved into the core plasma. For Te≳20 eV, ne/ne≊5%, and eφf /Te≊2ne/ne at r/a=0.95. The measured fluctuation spectra are broadband (40–300 kHz) with kρs≊(0.05–0.1), where k is the average wave number of the fluctuations and ρs is the ion Larmor radius at the sound speed. Near the LCFS, the density fluctuations can be approxi...


Nuclear Fusion | 1992

Density fluctuation measurements in ATF using correlation reflectometry

G. R. Hanson; J. H. Harris; J. B. Wilgen; C.E. Thomas; S.C. Aceto; L. R. Baylor; J. D. Bell; B. Branas; J.L. Dunlap; A.C. England; C. Hidalgo; M. Murakami; D.A. Rasmussen; J. Sanchez Sanz; J.G. Schwelberger; T. Uckan; J.J. Zielinski

A two-frequency correlation reflectometer has been operated on the Advanced Toroidal Facility (ATF) to measure plasma electron density fluctuations. This reflectometer uses quadrature phase detection to permit true phase measurement of the reflected microwave signal (probing beam). By measuring the phase fluctuations in the reflected probing beam, the amplitude of the density fluctuations can be estimated. Simultaneous two-frequency operation makes it possible to measure the coherence between fluctuations at two radially separated cut-off layers, from which the radial correlation lengths and wavenumbers can be estimated. This reflectometer has been used to study the density fluctuations in the edge gradient region of low density ATF plasmas produced by electron cyclotron heating. These studies have revealed globally coherent turbulence with a radial correlation length of up to approximately 5 cm, a radial wavenumber kr ≈ 0 cm-1 and a poloidal wavenumber kθ ≈ 1 cm-1. The rms amplitude of the fluctuations reaches a maximum of ≈ 5% at the plasma edge (ρ = 1, where ρ is the flux surface normalized radius) and decreases with decreasing radius to a level of 1%. Simultaneous measurements of the fluctuations with the reflectometer, the heavy ion beam probe and the fast reciprocating Langmuir probe provide consistent results. A comparison of the measurements with simplistic mixing length estimates, ne/ne = 1/kθLn or ne/ne = 1/krLn, shows that these estimates are too high by factors of two to more than 100, while a comparison with a more detailed estimate for the pressure gradient driven resistive interchange turbulence yields reasonable agreement with the experimentally measured fluctuation characteristics


Review of Scientific Instruments | 1990

ATF two-frequency correlation reflectometer

Gregory R. Hanson; J. B. Wilgen; E. Anabitarte; J. D. Bell; J. H. Harris; J.L. Dunlap; C.E. Thomas

The Advanced Toroidal Facility (ATF) density fluctuation reflectometer system consists of two individual reflectometers operating in the 30- to 40-GHz band. Each reflectometer consists of a tunable microwave source and a quadrature phase detector connected to the same antenna system. This arrangement allows two-frequency operation along the same radial chord for radial coherence measurements. The technique used in making radial coherence measurements is discussed and the results of such experiments are given. Initial experiments have shown high coherence when the frequencies of the two reflectometers are tuned close together and a clear loss of coherence as the radial separation of the cutoff layers is increased by increasing the frequency separation of the two reflectometers. Recent results have shown that local measurements of density fluctuations in plasmas with electron cyclotron heating (ECH) are possible and that detailed structure can be seen in the fluctuation spectra. In addition, radial correlation lengths have been found to be from 0.5 to 1.0 cm in ECH plasmas, with some frequency structures having correlation lengths up to 3 cm. In plasmas with neutral beam injection (NBI), the radial correlation lengths in the edge region have been found to be approximately 0.1--0.2 cm. 4 figs.


Physics of fluids. B, Plasma physics | 1993

Experimental exploration of profile control in the Princeton Beta Experiment‐Modified (PBX‐M) tokamak

S. Bernabei; R. Bell; M. Chance; T. K. Chu; M. Corneliussen; W. Davis; G. Gettlefinger; T. Gibney; N. Greenough; R. Hatcher; H. Hermann; D. Ignat; S. Jardin; R. Kaita; S. M. Kaye; C. Kessel; T. Kozub; H. Kugel; L. Lagin; B. LeBlanc; J. Manickam; M. Okabayashi; H. Oliver; M. Ono; S. Paul; S. Preische; P. Roney; N. Sauthoff; S. Schweitzer; S. Sesnic

The experimental program of the Princeton Beta Experiment‐Modified (PBX‐M) tokamak [Phys. Fluids B2, 1271 (1990)] is directed toward tailoring plasma profiles to achieve greater stability and confinement and to gain access to the second stability region. Modification of the current density profile has been achieved with lower‐hybrid current drive (LHCD), leading to a regime free of global magnetohydrodynamic modes, while raising the value of q(0) above unity. The diffusion of the fast electrons produced by LHCD has been examined using two‐dimensional hard x‐ray imaging. Ion Bernstein waves (IBW) have been used for ion heating: a preliminary analysis shows that ion heating was spatially localized and in agreement with theoretical calculations. Divertor biasing has modified the electric field inside the last closed surface, resulting in the formation of a transport barrier, which in turn has reduced the threshold power of neutral beam injection (NBI) for H‐mode transition by 25%.


Physics of fluids. B, Plasma physics | 1990

Second stability in the ATF torsatron—Experiment and theory

J. H. Harris; E. Anabitarte; G. L. Bell; J. D. Bell; T. S. Bigelow; B. A. Carreras; L. A. Charlton; R.J. Colchin; E. C. Crume; N. Dominguez; J.L. Dunlap; G. R. Dyer; A. C. England; R. F. Gandy; J. C. Glowienka; J.W. Halliwell; G. R. Hanson; C. Hidalgo‐Vera; D. L. Hillis; S. Hiroe; L.D. Horton; H.C. Howe; R.C. Isler; T.C. Jernigan; H. Kaneko; J.‐N. Leboeuf; D. K. Lee; V. E. Lynch; James F. Lyon; M.M. Menon

Access to the magnetohydrodynamic (MHD) second stability regime has been achieved in the Advanced Toroidal Facility (ATF) torsatron [Fusion Technol. 10, 179 (1986)]. Operation with a field error that reduced the plasma radius and edge rotational transform resulted in peaked pressure profiles and increased Shafranov shift that lowered the theoretical transition to ideal MHD second stability to β0≊1.3%; the experimental β values (β0≤3%) are well above this transition. The measured magnetic fluctuations decrease with increasing β, and the pressure profile broadens, consistent with the theoretical expectations for self‐stabilization of resistive interchange modes. Initial results from experiments with the field error removed show that the pressure profile is now broader. These later discharges are characterized by a transition to improved (×2–3) confinement and a marked change in the edge density fluctuation spectrum, but the causal relationship of these changes is not yet clear.


Physics of fluids. B, Plasma physics | 1991

Recent results from the ATF torsatron

M. Murakami; S.C. Aceto; E. Anabitarte; D. T. Anderson; F. S. B. Anderson; D. B. Batchelor; B. Brañas; L. R. Baylor; G. L. Bell; J. D. Bell; T. S. Bigelow; B. A. Carreras; R.J. Colchin; N. A. Crocker; E. C. Crume; N. Dominguez; R. A. Dory; J.L. Dunlap; G. R. Dyer; A. C. England; R. H. Fowler; R. F. Gandy; J. C. Glowienka; R. C. Goldfinger; R. H. Goulding; G. R. Hanson; J. H. Harris; C. Hidalgo; D. L. Hillis; S. Hiroe

Recent experiments in the Advanced Toroidal Facility (ATF) torsatron [Plasma Physics and Controlled Nuclear Fusion Research 1990 (IAEA, Vienna, in press)] have emphasized the role of magnetic configuration control in transport studies. Long‐pulse plasma operation up to 20 sec has been achieved with electron cyclotron heating (ECH). With neutral beam injection (NBI) power of ≥1 MW, global energy confinement times of 30 msec have been obtained with line‐average densities up to 1.3×1020 m−3. The energy confinement and the operational space in ATF are roughly the same as those in tokamaks of similar size and field. The empirical scaling observed is similar to gyro‐reduced Bohm scaling with favorable dependences on density and field offsetting an unfavorable power dependence. The toroidal current measured during ECH is identified as the bootstrap current. The observed currents agree well with predictions of neoclassical theory in magnitude and in parametric dependence. Variations of the magnetic configuration ...


Physics of fluids. B, Plasma physics | 1993

Fluctuation and modulation transport studies in the Advanced Toroidal Facility (ATF) torsatron

J. B. Wilgen; M. Murakami; J. H. Harris; T. S. Bigelow; R. A. Dory; B. A. Carreras; S.C. Aceto; D. B. Batchelor; L. R. Baylor; G. L. Bell; J. D. Bell; R.J. Colchin; E. C. Crume; N. Dominguez; J.L. Dunlap; G. R. Dyer; A. C. England; R. F. Gandy; J. C. Glowienka; R. C. Goldfinger; R. H. Goulding; G. R. Hanson; C. Hidalgo; S. Hiroe; S.P. Hirshman; L.D. Horton; H.C. Howe; D. P. Hutchinson; R.C. Isler; T.C. Jernigan

The Advanced Toroidal Facility (ATF) torsatron [Fusion Technol. 10, 179 (1986)] has completed experiments focusing on microwave scattering measurements of density fluctuations and transport studies utilizing the modulation of dimensionless parameters. Microwave scattering measurements of electron density fluctuations in the core of low‐collisionality electron cyclotron heated (ECH) plasmas show features that might be evidence of trapped electron instabilities. Starting from gyro‐Bohm scaling, the additional dependence of confinement on the dimensionless parameters ν* and β (collisionality and beta) has been investigated by modulating each of these parameters separately, revealing the additional favorable dependence, τE∝τgBν*−0.18β+0.3.


Physics of fluids. B, Plasma physics | 1992

Effects of magnetic geometry, fluctuations, and electric fields on confinement in the Advanced Toroidal Facility

R. C. Isler; S.C. Aceto; L. R. Baylor; T.S. Bigelow; G. L. Bell; J. D. Bell; Benjamin A. Carreras; R. J. Colchin; E. C. Crume; N. Dominguez; R. A. Dory; J. L. Dunlap; G. R. Dyer; A. C. England; R. F. Gandy; J. C. Glowienka; G. R. Hanson; J. H. Harris; S. Hiroe; L.D. Horton; T. C. Jernigan; H. Ji; R. A. Langley; D. K. Lee; K. M. Likin; J.F. Lyon; C. H. Ma; S. Morimoto; M. Murakami; Hiroyuki Okada

Recent experiments in the Advanced Toroidal Facility (ATF) [Fusion Technol. 10, 179 (1986)] have been directed toward investigations of the basic physics mechanisms that control confinement in this device. Measurements of the density fluctuations throughout the plasma volume have provided indications for the existence of theoretically predicted dissipative trapped electron and resistive interchange instabilities. These identifications are supported by results of dynamic configuration scans of the magnetic fields during which the magnetic well volume, shear, and fraction of confined trapped particles are changed continuously. The influence of magnetic islands on the global confinement has been studied by deliberately applying error fields which strongly perturb the nested flux‐surface geometry, and the effects of electric fields have been investigated by means of biased limiter experiments.


Physics of fluids. B, Plasma physics | 1990

Overview of results from the ATF torsatron

R. J. Colchin; M. Murakami; E. Anabitarte; F. S. B. Anderson; G. L. Bell; J. D. Bell; T. S. Bigelow; E. C. Crume; J. L. Dunlap; G. R. Dyer; A. C. England; P. W. Fisher; W. A. Gabbard; J. C. Glowienka; R. H. Goulding; J.W. Halliwell; G. R. Hanson; J. H. Harris; G. R. Haste; C. Hidalgo‐Vera; D. L. Hillis; S. Hiroe; L.D. Horton; H.C. Howe; D. P. Hutchinson; R. C. Isler; T.C. Jernigan; M. Kwon; R. A. Langley; D. K. Lee

Experiments involving plasma improvement, confinement scaling, bootstrap currents, and edge fluctuations have been carried out in the Advanced Toroidal Facility (ATF) torsatron [Fusion Technol. 10, 179 (1986)]. Average densities ne≤9×1019 m−3 have been obtained, with global energy confinement times τ*E≤20 msec. Confinement times generally follow the stellarator/torsatron empirical scaling law, τSL =0.17×P−0.58n0.69eB0.84a2R0.75 (with τSL in seconds, power P in megawatts, density ne in 1020 m−3, and plasma radius a and major radius R in meters). Gas injection during neutral beam injection (NBI) causes increases in ne, so that τ*E does not decrease during NBI. Edge plasma fluctuations are found to exhibit a mode change near the peak of the energy confinement time. Plasma currents observed during electron cyclotron heating have been identified as bootstrap currents.

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J. H. Harris

Oak Ridge National Laboratory

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J.L. Dunlap

Oak Ridge National Laboratory

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G. R. Dyer

Oak Ridge National Laboratory

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J. B. Wilgen

Oak Ridge National Laboratory

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M. Murakami

Oak Ridge National Laboratory

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A. C. England

Oak Ridge National Laboratory

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G. R. Hanson

Oak Ridge National Laboratory

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J. C. Glowienka

Oak Ridge National Laboratory

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L. R. Baylor

Oak Ridge National Laboratory

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S. Hiroe

Oak Ridge National Laboratory

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