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Dive into the research topics where D. O. Sparks is active.

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Featured researches published by D. O. Sparks.


Physics of Plasmas | 2002

Comparing experiments with modeling for light ion helicon plasma sources

Mark Dwain Carter; F. W. Baity; G. C. Barber; R. H. Goulding; Yoshitaka Mori; D. O. Sparks; K. F. White; E. F. Jaeger; F. R. Chang-Dı́az; Jared Philip Squire

The ability to obtain high plasma densities with high fractional ionization using readily available, low-cost components makes the helicon a candidate plasma source for many applications, including plasma rocket propulsion, fusion component testing, and materials processing. However, operation of a helicon can be a sensitive function of the magnetic field strength and geometry as well as the driving frequency, especially when using light feedstock gases such as hydrogen or helium. In this paper, results from a coupled rf and transport model are compared with experiments in the axially inhomogeneous Mini-Radio Frequency Test Facility [Goulding et al., Proceedings of the International Conference on Electromagnetics in Advanced Applications (ICEAA 99), Torino, Italy, 1999 (Litografia Geda, Torino, 1999), p. 107] (Mini-RFTF). Experimental observations of the radial shape of the density profile can be quantitatively reproduced by iteratively converging a high-resolution rf calculation including the rf parallel electric field with a transport model using reasonable choices for the transport parameters. The experimentally observed transition into the high density helicon mode is observed in the model, appearing as a nonlinear synergism between radial diffusion, the rf coupling to parallel electric fields that damp near the plasma edge, and propagation of helicon waves that collisionally damp near the axis of the device. Power deposition from various electric field components indicates that inductive coupling and absorption in the edge region can reduce the efficiency for high-density operation. The effects of absorption near the lower hybrid resonance in the near-field region of the antenna are discussed. Ponderomotive effects are also examined and found to be significant only in very low density and edge regions of the Mini-RFTF discharge.


Plasma Sources Science and Technology | 2004

High density hydrogen helicon plasma in a non-uniform magnetic field

Yoshitaka Mori; Hieki Nakashima; Frederick W Baity; R. H. Goulding; Mark Dwain Carter; D. O. Sparks

A high density (1019 m−3) hydrogen plasma has been sustained successfully in axially non-uniform static magnetic field configurations for frequencies both above and below the high density limit of the lower hybrid resonance frequency (LH-HD). Wave field measurements suggest several modes are coupling to generate these helicon plasmas. The dependence of the plasma density on the static magnetic field strength for a fixed geometry can be explained by waves, with wavelength close to the antenna length, that couple to the fundamental radial mode for frequencies below the LH-HD frequency and to the second radial mode for frequencies above the LH-HD frequency.


Review of Scientific Instruments | 1987

Eight‐shot pneumatic pellet injection system for the tokamak fusion test reactor

S.K. Combs; S. L. Milora; C.R. Foust; L. R. Baylor; G. C. Barber; R. D. Burris; P.W. Fisher; C.A. Foster; R.V. Lunsford; G. L. Schmidt; D.D. Schuresko; T. Senko; R. C. Shanlever; W. D. Shipley; D. O. Sparks; K. A. Stewart; R.B. Wysor

An eight‐shot pneumatic pellet injection system has been developed for plasma fueling of the tokamak fusion test reactor (TFTR). The active cryogenic mechanisms consist of a solid hydrogen extruder and a rotating pellet wheel that are cooled by flowing liquid‐helium refrigerant. The extruder provides solid hydrogen for stepwise loading of eight holes located circumferentially around the pellet wheel. This design allows for three different pellet diameters: 3.0 mm (three pellets), 3.5 mm (three pellets), and 4.0 mm (two pellets) in the present configuration. Each of the eight pellets can be shot independently. Deuterium pellets are accelerated in 1.0‐m‐long gun barrels with compressed hydrogen gas (at pressures from 70 to 105 bar) to velocities in the range 1.0–1.5 km/s. The pellets are transported to the plasma in an injection line that incorporates two stages of guide tubes with intermediate vacuum pumping stations. A remote, stand‐alone control and data‐acquisition system is used for injector and vacuum...


Fusion Science and Technology | 2009

Development of a Twin-Screw D 2 Extruder for the ITER Pellet Injection System

S. J. Meitner; L. R. Baylor; Juan J. Carbajo; S.K. Combs; D. T. Fehling; C.R. Foust; Marshall T McFee; James M McGill; D.A. Rasmussen; R G Sitterson; D. O. Sparks; A L Qualls

A twin-screw extruder for the ITER pellet injection system is under development at the Oak Ridge National Laboratory. The extruder will provide a stream of solid hydrogen isotopes to a secondary section, where pellets are cut and accelerated with single-stage gas gun into the plasma. A one-fifth ITER scale prototype extruder has been built to produce a continuous solid deuterium extrusion. Deuterium gas is precooled and liquefied before being introduced into the extruder. The precooler consists of a copper vessel containing liquid nitrogen surrounded by a deuterium gas filled copper coil. The liquefier is comprised of a copper cylinder connected to a Cryomech AL330 cryocooler, which is surrounded by a copper coil that the precooled deuterium flows through. The lower extruder barrel is connected to a Cryomech GB-37 cryocooler to solidify the deuterium (at 15 K) before it is forced through the extruder nozzle. A viewport located below the extruder nozzle provides a direct view of the extrusion. A camera is used to document the extrusion quality and duration. A data acquisition system records the extruder temperatures, torque, and speed, upstream, and downstream pressures. This paper will describe the prototype twin-screw extruder and initial extrusion results.


Review of Scientific Instruments | 2008

H− ion source developments at the SNSa)

R. F. Welton; M. P. Stockli; S N Murray Jr; Terry R Pennisi; Baoxi Han; Y. Kang; R. H. Goulding; Danny W Crisp; D. O. Sparks; Nicholas P Luciano; Justin R Carmichael; Jerry Carr

The U.S. Spallation Neutron Source (SNS) will require substantially higher average and pulse H(-) beam currents than can be produced from conventional ion sources such as the base line SNS source. H(-) currents of 40-50 mA (SNS operations) and 70-100 mA (power upgrade project) with a rms emittance of 0.20-0.35pi mm mrad and a approximately 7% duty factor will be needed. We are therefore investigating several advanced ion source concepts based on rf plasma excitation. First, the performance characteristics of an external antenna source based on an Al(2)O(3) plasma chamber combined with an external multicusp magnetic configuration, an elemental Cs system, and plasma gun will be discussed. Second, the first plasma measurements of a helicon-driven H(-) ion source will also be presented.


Radio frequency power in plasmas | 2008

Results of Folded Waveguide Tests on RFTF

F.W. Baity; T. S. Bigelow; Mark Dwain Carter; W. L. Gardner; R. H. Goulding; G. R. Haste; D. J. Hoffman; D. O. Sparks

Experiments with the 80‐MHz prototype folded waveguide on the Radio‐Frequency Test Facility (RFTF) at Oak Ridge National Laboratory have achieved substantially higher power levels than any previous tests on comparably sized loop antennas. This result, combined with a superior wave spectrum, suggests that the folded waveguide should be capable of coupling several times the power flux of a loop antenna into a tokamak plasma.


RADIO FREQUENCY POWER IN PLASMAS: 15th Topical Conference on Radio Frequency Power in Plasmas | 2003

Initial operation of the JET ITER‐like High‐Power Prototype ICRF Antenna

R. H. Goulding; F.W. Baity; F. Durodié; A. Fadnek; J. C. Hosea; G. H. Jones; G. D. Loesser; B. Nelson; D.A. Rasmussen; P.M. Ryan; D. O. Sparks; David W. Swain; R. Walton

Fabrication and assembly of a High Power Prototype (HPP) of the JET ITER‐like Ion Cyclotron Range of Frequencies (ICRF) launcher have been completed at Oak Ridge National Laboratory (ORNL), and high power tests have begun. The HPP consists of one quadrant of the full 7.5 MW antenna (1). The prototype is the product of a collaboration between ORNL, Princeton Plasma Physics Laboratory, and EFDA‐JET/UKAEA. Internal matching capacitors are utilized in a circuit that maintains a voltage standing wave ratio (VSWR) at the input 45 kV peak voltage at the internal matching capacitors, which is greater than the original design voltage. High power pulses up to 2s have been run. Diagnostics include thermocouples, voltage probes at the capacitors and along the integral λ/4 matching transformer, and an optical temperature sensor for in‐situ measurements of capacitor temperatures. Low power measurements of electrical characterist...


13th Topical Conference on Applications of Radio Frequency Power to Plasmas, Princeton, NJ, April 12-14, 1999 | 1999

Design of RF systems for the RTD mission VASIMR

F.W. Baity; G.C. Barber; Mark Dwain Carter; R. H. Goulding; D. O. Sparks; F. R. Chang-Dı́az; G. E. McCaskill; J. P. Squire

The first flight test of the variable specific impulse magnetoplasma rocket (VASIMR) is tentatively scheduled for the Radiation and Technology Demonstration (RTD) in 2003. This mission to map the radiation environment out to several earth radii will employ both a Hall thruster and a VASIMR during its six months duration, beginning from low earth orbit. The mission will be powered by a solar array providing 12 kW of direct current electricity at 50 V. The VASIMR utilizes radiofrequency (RF) power both to generate a high-density plasma in a helicon source and to accelerate the plasma ions to high velocity by ion cyclotron resonance heating (ICRH). The VASIMR concept is being developed by the National Aeronautics and Space Administration (NASA) in collaboration with national laboratories and universities. Prototype plasma sources, RF amplifiers, and antennas are being developed in the experimental facilities of the Advanced Space Propulsion Laboratory (ASPL).


13th Topical Conference on Applications of Radio Frequency Power to Plasmas, Princeton, NJ, April 12-14, 1999 | 1999

Electrical Testing of the Full-Scale model of the NSTX HHFW Antenna Array

P. M. Ryan; David W. Swain; J. B. Wilgen; A. Fadnek; D. O. Sparks

The 30 MHz high harmonic fast wave (HHFW) antenna array for NSTX consists of 12 current straps, evenly spaced in the toroidal direction. Each pair of straps is connected as a half-wave resonant loop and will be driven by one transmitter, allowing rapid phase shift between transmitters. A decoupling network using shunt stub tuners has been designed to compensate for the mutual inductive coupling between adjacent current straps, effectively isolating the six transmitters from one another. One half of the array, consisting of six full-scale current strap modules, three shunt stub decouplers, and powered by three phase-adjustable rf amplifiers had been built for electrical testing at ORNL. Low power testing includes electrical characterization of the straps, operation and performance of the decoupler system, and mapping of the rf fields in three dimensions.


ieee symposium on fusion engineering | 1989

The ORNL plasma fueling program

M. J. Gouge; S. L. Milora; C.A. Foster; S.K. Combs; P.W. Fisher; C.C. Tsai; B.E. Argo; G. C. Barber; L. R. Baylor; D. T. Fehling; C.R. Foust; T.C. Jernigan; A.L. Qualls; D.E. Schechter; D.W. Simmons; C.W. Sohns; D. O. Sparks

Advanced plasma fueling systems for magnetic confinement devices are under development at the Oak Ridge National Laboratory (ORNL). The general approach is to produce and accelerate frozen hydrogen-isotope pellets at speeds ranging from 1 to 2 km/s and higher. Recently, ORNL provided pneumatic-based pellet fueling systems for two of the worlds largest tokamak experiments, the Tokamak Fusion Test Reactor (TFTR) and the Joint European Torus (JET). A new, versatile, centrifuge-type injector is being installed on the Tore Supra tokamak. Also, a new, simplified, eight-shot injector has been developed, and injectors based on this design are operating on the Princeton Beta Experiment (PBX) and the ORNL Advanced Toroidal Facility (ATF). In addition to these confinement-physics-related activities, ORNL is pursuing advanced technologies to achieve pellet velocities significantly in excess of 2 km/s, and has carried out a tritium proof of principle experiment in which the fabrication and acceleration of tritium pellets were demonstrated. These ongoing activities are described.<<ETX>>

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R. H. Goulding

Oak Ridge National Laboratory

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D.A. Rasmussen

Oak Ridge National Laboratory

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G. C. Barber

Oak Ridge National Laboratory

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F.W. Baity

Oak Ridge National Laboratory

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A. Fadnek

Oak Ridge National Laboratory

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C.R. Foust

Oak Ridge National Laboratory

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J. B. Wilgen

Oak Ridge National Laboratory

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L. R. Baylor

Oak Ridge National Laboratory

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S. L. Milora

Oak Ridge National Laboratory

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S.K. Combs

Oak Ridge National Laboratory

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