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Dive into the research topics where S.K. Combs is active.

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Featured researches published by S.K. Combs.


Review of Scientific Instruments | 1993

Pellet injection technology

S.K. Combs

During the last 10 to 15 years, significant progress has been made worldwide in the area of pellet injection technology. This specialized field of research originated as a possible solution to the problem of depositing atoms of fuel deep within magnetically confined, hot plasmas for refueling of fusion power reactors. Using pellet injection systems, frozen macroscopic (millimeter‐size) pellets composed of the isotopes of hydrogen are formed, accelerated, and transported to the plasma for fueling. The process and benefits of plasma fueling by this approach have been demonstrated conclusively on a number of toroidal magnetic confinement configurations; consequently, pellet injection is the leading technology for deep fueling of magnetically confined plasmas for controlled thermonuclear fusion research. Hydrogen pellet injection devices operate at very low temperatures (≂10 K) at which solid hydrogen ice can be formed and sustained. Most injectors use conventional pneumatic (light gas gun) or centrifuge (mec...


Review of Scientific Instruments | 1985

Repeating pneumatic hydrogen pellet injector for plasma fueling

S.K. Combs; S. L. Milora; C.R. Foust; C.A. Foster; D.D. Schuresko

A repeating pneumatic pellet injector has been developed for plasma fueling applications. The repetitive device extends pneumatic injector operation to steady state. The active mechanism consists of an extruder and a gun assembly that are cooled by flowing liquid‐helium refrigerant. The extruder provides a continuous supply of solid hydrogen to the gun assembly, where a reciprocating gun barrel forms and chambers cylindrical pellet from the extrusion; pellets are then accelerated with compressed hydrogen gas (pressures up to 125 bar) to velocities ≤1.9 km/s (1.6 km/s for deuterium pellets). The gun assembly design can accommodate different pellet sizes and barrel lengths. Steady‐state rates of 2 s−1 have been obtained with 2.1‐ , 3.4‐ , and 4.0‐mm‐diameter pellets. The present apparatus operates at higher firing rates in short bursts; for example, a rate of 6 s−1 for 2 s with the larger pellets. These pellet parameters are in the range applicable for fueling large present‐day fusion devices such as the To...


Review of Scientific Instruments | 1986

Fast‐opening magnetic valve for high‐pressure gas injection and applications to hydrogen pellet fueling systems

S. L. Milora; S.K. Combs; C.R. Foust

A fast, magnetically driven gas valve and its application to pneumatic‐based solid hydrogen pellet injectors are described. The valve, which is equipped with a polyimide stem tip (hard seal) and a 5‐mm‐diam orifice, can open against working pressures up to 140 bar (2000 psi). Other unique features of this design include temperature‐ and radiation‐resistant seals, a programmable output pressure pulse, and repetitive operation in excess of 20 Hz. A prototype valve has been used to propel frozen hydrogen isotope pellets to speeds of up to 1900 m/s.


Nuclear Fusion | 2007

Pellet fuelling and control of burning plasmas in ITER

L. R. Baylor; P.B. Parks; T.C. Jernigan; J. B. O. Caughman; S.K. Combs; C.R. Foust; W. A. Houlberg; S. Maruyama; D.A. Rasmussen

Pellet injection from the inner wall is planned for use in ITER as the primary core fuelling system since gas fuelling is expected to be highly inefficient in burning plasmas. Tests of the inner wall guide tube have shown that 5 mm pellets with up to 300 m s−1 speeds can survive intact and provide the necessary core fuelling rate. Modelling and extrapolation of the inner wall pellet injection experiments from present days smaller tokamaks leads to the prediction that this method will provide efficient core fuelling beyond the pedestal region. Using pellets for triggering of frequent small edge localized modes is an attractive additional benefit that the pellet injection system can provide. A description of the ITER pellet injection systems capabilities for fuelling and ELM triggering is presented and performance expectations and fusion power control aspects are discussed.


Nuclear Fusion | 2009

Pellet fuelling, ELM pacing and disruption mitigation technology development for ITER

L. R. Baylor; S.K. Combs; C.R. Foust; T.C. Jernigan; S. J. Meitner; P.B. Parks; J. B. O. Caughman; D. T. Fehling; S. Maruyama; A. L. Qualls; D.A. Rasmussen; C.E. Thomas

Plasma fuelling with pellet injection, pacing of edge localized modes (ELMs) by small frequent pellets and disruption mitigation with gas jets or injected solid material are some of the most important technological capabilities needed for successful operation of ITER. Tools are being developed at the Oak Ridge National Laboratory that can be employed on ITER to provide the necessary core pellet fuelling and the mitigation of ELMs and disruptions. Here we present progress on the development of the technology to provide reliable high throughput inner wall pellet fuelling, pellet ELM pacing with high frequency small pellets and disruption mitigation with gas jets and shattered pellets. Examples of how these tools can be employed on ITER are discussed.


Nuclear Fusion | 2001

Impact of pellet injection on extension of the operational region in LHD

R. Sakamoto; H. Yamada; Kenji Tanaka; K. Narihara; S. Morita; S. Sakakibara; S. Masuzaki; S. Inagaki; L. R. Baylor; P.W. Fisher; S.K. Combs; M.J. Gouge; S. Kato; A. Komori; O. Kaneko; N. Ashikawa; P. de Vries; M. Emoto; H. Funaba; M. Goto; K. Ida; H. Idei; K. Ikeda; M. Isobe; S. Kado; K. Kawahata; K. Khlopenkov; S. Kubo; R. Kumazawa; T. Minami

Pellet injection has been used as a primary fuelling scheme in the Large Helical Device. With pellet injection, the operational region of NBI plasmas has been extended to higher densities while maintaining a favourable dependence of energy confinement on density, and several important values, such as plasma stored energy of 0.88?MJ, energy confinement time of 0.3?s, ? of 2.4% at 1.3?T and density of 1.1 ? 1020?m -3, have been achieved. These parameters cannot be attained by gas puffing. Ablation and the subsequent behaviour of the plasma have been investigated. The measured pellet penetration depth estimated on the basis of the duration of the H? emission is shallower than the depth predicted from the simple neutral gas shielding (NGS) model. It can be explained by the NGS model with inclusion of the effect of fast ions on the ablation. Just after ablation, the redistribution of the ablated pellet mass was observed on a short timescale (~400?ms). The redistribution causes shallow deposition and low fuelling efficiency.


Review of Scientific Instruments | 1989

Performance of a pneumatic hydrogen‐pellet injection system on the Joint European Torus

S.K. Combs; T.C. Jernigan; L. R. Baylor; S. L. Milora; C.R. Foust; P. Kupschus; M. Gadeberg; W. Bailey

A pneumatic‐based, hydrogen isotope pellet injector that was developed at the Oak Ridge National Laboratory (ORNL) has been used in recent plasma fueling experiments on the Joint European Torus (JET). The injector consists of three independent machine‐gun‐like mechanisms (nominal pellet sizes of 2.7, 4.0, and 6.0 mm in diameter) and features repetitive operation (1–5 Hz) for quasi‐steady‐state conditions (>10 s). An extensive set of injector diagnostics permits evaluation of parameters for each pellet shot, including speed, mass, and integrity. Pellet speeds range from 1.0 to 1.5 km/s. Over 3700 pellets have been fired with the equipment at JET, with about 1500 pellets shot for plasma fueling experiments. In recent experiments, the system performance has been outstanding, including excellent reproducibility in pellet speed and mass, and a reliability of >98% in delivery of pellets to the plasma.


Nuclear Engineering and Design. Fusion | 1986

A numerical model for swirl flow cooling in high-heat-flux particle beam targets and the design of a swirl-flow-based plasma limiter*

S. L. Milora; S.K. Combs; C.A. Foster

An unsteady, two-dimensional heat conduction code has been used to study the performance of swirl-flow-based neutral particle beam targets. The model includes the effects of two-phase heat transfer and asymmetric heating of tubular elements. The calorimeter installed in the Medium Energy Test Facility, which has been subjected to 30-s neutral beam pulses with incident heat flux intensities of greater than or equal to 5 kW/cm/sup 2/, has been modeled. The numerical results indicate that local heat fluxes in excess of 7 kW/cm/sup 2/ occur at the water-cooled surface on the side exposed to the beam. This exceeds critical heat flux limits for uniformly heated tubes wih straight flow by approximately a factor of 5. The design of a plasma limiter based on swirl flow heat transfer is presented.


symposium on fusion technology | 2001

ORNL mock-up tests of inside launch pellet injection on JET and LHD☆

S.K. Combs; L. R. Baylor; P.W Fisher; C.R. Foust; M.J. Gouge; D Pavarin; R Sakamoto; P Twynam; M Watson; H Yamada

Abstract In experiments on ASDEX-Upgrade and DIII-D tokamaks, the injection of D2 pellets from the magnetic high-field side of the plasma resulted in deeper pellet penetration and improved fueling efficiency. Based on those successful experiments, fusion researchers at the Joint European Torus and the Large Helical Device decided to implement inside launch pellet injection. These injection schemes require the use of curved guide tubes to route the pellets from the acceleration devices to the inside launch locations, and the pellets are subjected to stresses from centrifugal and impact forces in traversing the tubes. Before the installations on the large experimental fusion devices, mock-ups of the guide tubes were constructed and tested at the Oak Ridge National Laboratory to determine the pellet speed limit for reliable operation without pellet fracturing. In laboratory testing of the mock-ups, it was found that the pellet speed had to be limited to a few hundreds of meters per second for intact pellets. In this paper, the test equipment and experimental results are described.


Review of Scientific Instruments | 1986

Simple pipe gun for hydrogen pellet injection

S.K. Combs; S. L. Milora; C.R. Foust

A new single‐shot hydrogen pellet injector based on a simple ‘‘pipe gun’’ design is described. In the cryogenic gun block, the 4‐mm‐diam (nominal) pellet is frozen in situ directly from the gaseous hydrogen isotope and then accelerated in the gun barrel with a burst of high‐pressure (≤130‐bar) hydrogen gas to speeds of up to 1680 m/s.

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L. R. Baylor

Oak Ridge National Laboratory

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C.R. Foust

Oak Ridge National Laboratory

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S. J. Meitner

Oak Ridge National Laboratory

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D. T. Fehling

Oak Ridge National Laboratory

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S. L. Milora

Oak Ridge National Laboratory

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D.A. Rasmussen

Oak Ridge National Laboratory

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T.C. Jernigan

Oak Ridge National Laboratory

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J. B. O. Caughman

Oak Ridge National Laboratory

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P.W. Fisher

Oak Ridge National Laboratory

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