Results 151 to 160 of about 20,009 (190)
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Hybrid Scenario Development in DIII-D
Fusion Science and Technology, 2005Experiments in the DIII-D tokamak have demonstrated the ability to sustain ELMing H-mode discharges with high beta and good confinement quality under stationary conditions. These experiments have shown the ability to sustain normalized fusion performance (in terms of {beta}{sub N}H{sub 89P} /q{sub 95}{sup 2}) at or above that projected for Q{sub fus} =
Wade, M. +8 more
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Sawtooth Precursor Oscillations on DIII-D
IEEE Transactions on Plasma Science, 2011The sawtooth oscillation, observed in tokamak plasmas with a central safety factor of less than unity, is a periodic disruptive instability characterized by a slow ramping of central plasma density and temperature, followed by a fast relaxation resulting in flattening of both profiles.
Tobias, B.J. +8 more
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Fusion Science and Technology, 2005
Studies of the H-mode pedestal in the DIII-D tokamak are presented. The global energy confinement increases as the plasma pressure on top of the pedestal increases. The best empirical description for a pedestal width parameter is {delta}{sub pe} [proportional to] ({beta}{sub pol}{sup PED}){sup 0.4}, where {delta}{sub pe} is the width of the electron ...
R. J. Groebner +11 more
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Studies of the H-mode pedestal in the DIII-D tokamak are presented. The global energy confinement increases as the plasma pressure on top of the pedestal increases. The best empirical description for a pedestal width parameter is {delta}{sub pe} [proportional to] ({beta}{sub pol}{sup PED}){sup 0.4}, where {delta}{sub pe} is the width of the electron ...
R. J. Groebner +11 more
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DIII-D divertor reflectometer system
Review of Scientific Instruments, 1997Divertor density profiles, asymmetries, turbulence, and MARFE diagnosis are extremely important and affect the divertor design process for ITER and other future devices. In addition, a functioning divertor density profile system will be essential for the operation of these machines.
T. L. Rhodes +5 more
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Fusion Technology, 1994
This paper summarizes the recent DIII-D experimental results and the development of the relevant hardware systems. The DIII-D program focuses on divertor solutions for next generation tokamaks such as International Thermonuclear Experimental Reactor (ITER) and Tokamak Physics Experiment (TPX), and on developing configurations with enhanced confinement ...
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This paper summarizes the recent DIII-D experimental results and the development of the relevant hardware systems. The DIII-D program focuses on divertor solutions for next generation tokamaks such as International Thermonuclear Experimental Reactor (ITER) and Tokamak Physics Experiment (TPX), and on developing configurations with enhanced confinement ...
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Physics of Plasmas, 2007
In the absence of any auxiliary torque input, the DIII-D plasma consists of nonzero toroidal angular momentum, in other words, it rotates. This effect is commonly observed in tokamaks, being referred to as intrinsic rotation. Measurements of intrinsic rotation profiles have been made in DIII-D [J. Luxon, Nucl.
J. S. deGrassie +4 more
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In the absence of any auxiliary torque input, the DIII-D plasma consists of nonzero toroidal angular momentum, in other words, it rotates. This effect is commonly observed in tokamaks, being referred to as intrinsic rotation. Measurements of intrinsic rotation profiles have been made in DIII-D [J. Luxon, Nucl.
J. S. deGrassie +4 more
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Deuterium retention of DIII-D DiMES sample
Journal of Nuclear Materials, 1999Abstract The deuterium retention property of B4C converted graphite and isotropic graphite exposed to DIII-D deuterium plasma was examined by using a technique of thermal desorption spectroscopy. Major outgassing species were HD, D2 and CD4 in both the graphite and the B4C. In the case of the graphite, the ratios of deuterium desorbed in the forms of
Yamauchi, Y. +7 more
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IEEE Transactions on Nuclear Science, 1987
The DIII-D tokamak, an upgrade of Doublet III, a device to study magnetic confinement fusion at GA Technologies, became operational in February 1986. The new timing system consists of two major subsystems. The trigger subsystem synchronizes control and data acquisition for the experiment.
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The DIII-D tokamak, an upgrade of Doublet III, a device to study magnetic confinement fusion at GA Technologies, became operational in February 1986. The new timing system consists of two major subsystems. The trigger subsystem synchronizes control and data acquisition for the experiment.
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Thomson scattering diagnostic upgrade on DIII-D
Review of Scientific Instruments, 2010The DIII-D Thomson scattering system has been upgraded. A new data acquisition hardware was installed, adding the capacity for additional spatial channels and longer acquisition times for temperature and density measurements. Detector modules were replaced with faster transimpedance circuitry, increasing the signal-to-noise ratio by a factor of 2. This
D M, Ponce-Marquez +4 more
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1991
The completion of additional radiation shielding in the spring of 1989 has allowed the DIII-D tokamak to enter a new phase of experimental operation, in which the potential of injecting deuterium beam injection into deuterium plasmas has been exploited. The benefit of the isotope effect in increased energy confinement time, and increased power delivery
Callis, R. +5 more
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The completion of additional radiation shielding in the spring of 1989 has allowed the DIII-D tokamak to enter a new phase of experimental operation, in which the potential of injecting deuterium beam injection into deuterium plasmas has been exploited. The benefit of the isotope effect in increased energy confinement time, and increased power delivery
Callis, R. +5 more
openaire +1 more source

