J. H. Harris
Oak Ridge National Laboratory
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Featured researches published by J. H. Harris.
Physics of Plasmas | 2000
J. H. Harris; N Martin; David Thorncraft; R Milliken; D Miljak; Brian Kwan; T Ng; J Kircher
In certain applications, the surface wave driven plasma column can replace metal as the guiding medium in radio frequency antennas. Such plasma antennas offer the possibility of low radar detectability and negligible mutual coupling when de-energized. Experimental results are presented confirming that the two most important physical issues, namely antenna efficiency and noise, are not compromised by the use of a plasma. It is also shown that the relatively high efficiency of the surface wave driven plasma column can be predicted by a simple calculation.
Applied Physics Letters | 1999
J. H. Harris; David G. Miljak; Noel M. Martin
Plasma offers a promising alternative to metal for a wide variety of radiofrequency antenna applications. In this letter we report measurements of efficiencies up to 50% and radiation patterns for plasma column antenna elements. It is demonstrated that the current distribution along the antenna can be controlled by the plasma density. Plasma columns can be used instead of metal elements in communications antennas.
Nuclear Fusion | 2005
T.E. Evans; R.A. Moyer; J.G. Watkins; T.H. Osborne; P.R. Thomas; M. Becoulet; J.A. Boedo; E. J. Doyle; M.E. Fenstermacher; K.H. Finken; R. J. Groebner; M. Groth; J. H. Harris; G.L. Jackson; R.J. La Haye; C.J. Lasnier; S. Masuzaki; N. Ohyabu; David Pretty; H. Reimerdes; T.L. Rhodes; D.L. Rudakov; M.J. Schaffer; M.R. Wade; G. Wang; W.P. West; L. Zeng
Large sub-millisecond heat pulses due to Type-I edge localized modes (ELMs) have been eliminated reproducibly in DIII-D for periods approaching nine energy confinement times (τE) with small dc currents driven in a simple magnetic perturbation coil. The current required to eliminate all but a few isolated Type-I ELM impulses during a coil pulse is less than 0.4% of plasma current. Based on magnetic field line modelling, the perturbation fields resonate with plasma flux surfaces across most of the pedestal region (0.9 ≤ ψN ≤ 1.0) when q95 = 3.7 ± 0.2, creating small remnant magnetic islands surrounded by weakly stochastic field lines. The stored energy, βN, H-mode quality factor and global energy confinement time are unaltered by the magnetic perturbation. Although some isolated ELMs occur during the coil pulse, long periods free of large Type-I ELMs (Δt > 4–6 τE) have been reproduced numerous times, on multiple experimental run days in high and intermediate triangularity plasmas, including cases matching the baseline ITER scenario 2 flux surface shape. In low triangularity, lower single null plasmas, with collisionalities near that expected in ITER, Type-I ELMs are replaced by small amplitude, high frequency Type-II-like ELMs and are often accompanied by one or more ELM-free periods approaching 1–2 τE. Large Type-I ELM impulses represent a severe constraint on the survivability of the divertor target plates in future burning plasma devices. Results presented in this paper demonstrate that non-axisymmetric edge magnetic perturbations provide a very attractive development path for active ELM control in future tokamaks such as ITER.
Physics of Plasmas | 2005
R.A. Moyer; T.E. Evans; T. H. Osborne; P.R. Thomas; M. Becoulet; J. H. Harris; K.H. Finken; J.A. Boedo; E. J. Doyle; M.E. Fenstermacher; P. Gohil; R. J. Groebner; M. Groth; G.L. Jackson; R.J. La Haye; C.J. Lasnier; A.W. Leonard; G.R. McKee; H. Reimerdes; T.L. Rhodes; D.L. Rudakov; M.J. Schaffer; P.B. Snyder; M.R. Wade; G. Wang; J.G. Watkins; W. P. West; L. Zeng
This work was funded by the U.S. Department of Energy under Grant Nos. DE-FC02-04ER54698, DE-FG02- 04ER54758, DE-FG03-01ER54615, W-7405-ENG-48, DEFG03-96ER54373, DE-FG02-89ER53297, DE-AC05- 00OR22725, and DE-AC04-94AL85000.
Physics of Plasmas | 2000
Christine Charles; A. W. Degeling; T. E. Sheridan; J. H. Harris; M. A. Lieberman; Roderick Boswell
Measurements of the rf electric field have been made along the z axis of a helicon reactor using a retarding field energy analyzer. A fluid code and a simple analytical model have been developed to analyze the ion energy distribution functions, especially in the case of bimodal distributions where the ion transit time through the sheath in front of the analyzer is comparable to the rf period. A generalized curve (and an analytical approximation to that curve) has been developed from the analytical model and confirmed by the self-consistent fluid model for high, low, and intermediate ion transit time, which can be used by experimenters to quickly convert the experimental results (energy peak separation, plasma potential and density, electron temperature), which are related to rf sheath oscillations, to absolute values of the rf electric field. An analysis of the errors involved in the derivation of the field is given. The results agree qualitatively with rf pickup measured with a floating Langmuir probe.
Nuclear Fusion | 1988
B. A. Carreras; G. Grieger; J. H. Harris; J.L. Johnson; James F. Lyon; O. Motojima; F. Rau; H. Renner; J.A. Rome; K. Uo; Masahiro Wakatani; H. Wobig
Substantial progress was made during the period 1981-1986 in plasma parameters, physics understanding, and improvement of the stellarator/heliotron concept. Recent advances include (1) substantial achievements in higher plasma parameters and currentless plasma operation, (2) new theoretical results with respect to higher beta limits, second stability region, effect of a helical axis, effect of electric fields on transport, and reduction of secondary currents; and (3) improvements to the reactor concept. The key issues have been further refined, and the short-term direction of the program is clear; a number of new facilities that were designed to resolve these issues are about to come into operation or are in the final design stages. This report summarizes these advances.
Nuclear Fusion | 1998
M. Goniche; D. Guilhem; P. Bibet; P. Froissard; X. Litaudon; G. Rey; J. Mailloux; Y. Demers; V. Fuchs; P. Jacquet; J. H. Harris; J. Hogan
As a result of experimental observations of localized heat flux on components magnetically connected to radiating waveguides in Tore Supra and in TdeV, the acceleration of electrons near lower hybrid (LH) antennas has been investigated. A simple analytical model has been developed to compute the dynamics of the particles in the near field approximation. Landau damping of the very high N|| (20 < N|| < 100) component of the launched spectrum on the thermal electrons of the scrape-off layer (SOL) is found to occur. Simulation of a typical LH pulse in Tore Supra indicates that the electrons can be accelerated up to 2-3 keV. Modelling of the interaction of this fast electron population with the edge plasma allows a calculation of the heat flux on plasma facing components that are magnetically connected to the antenna. Model results and the results of experiments in Tore Supra and TdeV are compared. The calculated heat fluxes are found to be fairly consistent when the variation of convective heat flux at the grill aperture is taken into account. From this analysis, it is concluded that, for an LH power density of 25 MW/m2, the resulting heat flux along the field lines (3.5 MW/m2) is manageable for the components connected to the antenna, provided that good coupling can be maintained at a low density in front of the grill.
Physics of fluids. B, Plasma physics | 1990
R. D. Stambaugh; S. M. Wolfe; R.J. Hawryluk; J. H. Harris; H. Biglari; Stewart C. Prager; R.J. Goldston; R. J. Fonck; T. Ohkawa; B. G. Logan; E. Oktay
The physics of enhanced confinement regimes in tokamaks is reviewed and some directions for further enhancements are assessed. The H‐mode confinement regime is examined. A number of other observations of enhanced confinement, having in common peaked density profiles, are compared to the theory of ion temperature gradient modes. Two schemes of promise in enhancing confinement, second stability and control of electric fields, are discussed. The contributions of alternate concepts to understanding tokamak transport are described.
Nuclear Fusion | 1991
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.
Review of Scientific Instruments | 1989
R.J. Colchin; F. S. B. Anderson; A. C. England; R. F. Gandy; J. H. Harris; M. A. Henderson; D. L. Hillis; R.R. Kindsfather; D. K. Lee; D. Million; M. Murakami; G.H. Neilson; M.J. Saltmarsh; C. M. Simpson
The beam from an electron gun was used to trace flux surfaces in the Advanced Toroidal Facility (ATF) torsatron. The ATF magnetic field was run steady state at 0.1 T, and the electron beam was detected optically with an image‐intensified, solid‐state camera when it impinged on a phosphor‐coated screen. Closed flux surfaces and islands at several low‐order resonances were observed. The largest island, located at the ι= 1/2 surface, was from 5 to 6 cm in width, and its presence implied the existence of magnetic field errors. To determine if these error fields could be traced to small misalignments of the magnetic coils, a device capable of accurately measuring the radial and vertical magnetic field components of individual coil sets was placed in the center of ATF. This device allowed for a determination of the precise location of each of the coils that make up the ATF coil set. No significant coil misalignments were found. A further investigation of the coil configuration led to the identification of dipol...