Results 161 to 170 of about 20,009 (190)

DIII-D Latest Results and Implications

Fusion Technology, 1989
The DIII-D tokamak has demonstrated the feasibility of the divertor configuration for future reactor relevant devices. H-mode (good) confinement has been demonstrated for deuterium discharges in both single-null and double-null divertor configurations and under a variety of heating scenarios including neutral beam injection, electron cyclotron heating,
R. Callis, J. Luxon, T. Scoville, T. Simonen, R. Stambaugh   +4 more
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DIII-D research program

Journal of Fusion Energy, 1991
The DIII-D tokamak is uniquely positioned to contribute to the development of Magnetic Fusion Energy over the next decade. Recent stability and confinement improvements resulting from current profile control and the discovery of the VH-mode stress the importance of non-inductive current drive.
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Electron Cyclotron Heating on DIII-D

Fusion Science and Technology, 2005
Electron cyclotron heating (ECH) has proved to be a very flexible system for heating applications in DIII-D. The outstanding characteristics of ECH - controllable heating location, a high degree of localization of the power, ability to heat without introducing particles, and ability to heat only the electron fluid - have been used in a wide variety of ...
R. Prater, C. C. Petty
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Advanced tokamak research in DIII-D

Plasma Physics and Controlled Fusion, 2004
Advanced tokamak (AT) research in DIII-D seeks to provide a scientific basis for steady-state high performance operation in future devices. These regimes require high toroidal beta to maximize fusion output and high poloidal beta to maximize the self-driven bootstrap current.
Greenfield, C., Murakami, M., Ferron, J., Wade, M., Luce, T., Petty, C., Menard, J., Petrie, T., Allen, S., Burrell, K., Casper, T., DeBoo, J., Doyle, E., Garofalo, A., Gorelov, I., Groebner, R., Hobirk, J., Hyatt, A., Jayakumar, R., Kessel, C., La Haye, R., Jackson, G., Lao, L., Lohr, J., Makowski, M., Pinsker, R., Politzer, P., Prater, R., Staebler, G., Strait, E., Taylor, T., West, W., DIII-D Team   +32 more
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DIII-D physics analysis database (abstract)

Review of Scientific Instruments, 1990
Since June 1986 the DIII-D tokamak has had over 16 000 discharges accumulating more than 250 Gbytes of raw data (currently over 30 Mbytes per discharge). The centralized DIII-D databases and the associated support software described earlier provide the means to extract, analyze, store, and display reduced sets of data for specific physics issues.
G. Bramson, D. P. Schissel, J. C. DeBoo, H. St. John   +3 more
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ELM energy scaling in DIII-D

Plasma Physics and Controlled Fusion, 2002
The energy lost from the pedestal region due to an average ELM in DIII-D is determined from changes to the electron density and temperature profiles as measured by Thomson scattering. The ELM energy due to loss of temperature in the pedestal is associated with conduction and is found to decrease with increasing pedestal density.
A W Leonard, R J Groebner, M A Mahdavi, T H Osborne, M E Fenstermacher, C J Lasnier, T W Petrie   +6 more
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ICRF Heating Experiments on DIII-D

AIP Conference Proceedings, 1992
Experiments utilizing rf power in the 32–60 MHz range to heat the DIII‐D tokamak plasma are reviewed. In the first set of experiments, a two‐element array of loop antennas oriented in the toroidal direction was used to launch ion Bernstein waves (IBW) either directly or by mode transformation from the electron plasma wave.
R. I. Pinsker, M. J. Mayberry, C. C. Petty, S. C. Chiu, M. Porkolab, R. Prater, F. W. Baity, R. H. Goulding, D. J. Hoffman   +8 more
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Integrated Plasma Control in DIII-D

Fusion Science and Technology, 2005
The integrated plasma control approach provides a systematic method for designing plasma control algorithms with high reliability and for confirming their performance off-line prior to experimental...
D. A. Humphreys, R. D. Deranian, J. R. Ferron, A. W. Hyatt, R. D. Johnson, R. R. Khayrutdinov, R. J. La Haye, J. A. Leuer, B. G. Penaflor, J. T. Scoville, M. L. Walker, A. S. Welander   +11 more
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Status and Plans for DIII-D

Fusion Technology, 1992
This paper summarizes recent DIII-D tokamak experimental results and research plans. DIII-D has demonstrated improved confinement and stability through the use of radiofrequency current drive tools...
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The long range DIII-D plan

Journal of Fusion Energy, 1994
The mission of the DIII-D tokamak research program is to provide data needed by ITER and to develop a conceptual physics blueprint for a commercially attractive electrical demonstration plant (DEMO) that would open a path to fusion power commercialization.
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