Results 201 to 210 of about 15,788,610 (233)
Some of the next articles are maybe not open access.
DIII-D Latest Results and Implications
Fusion Technology, 1989The 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 +4 more
openaire +1 more source
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...
openaire +1 more source
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...
openaire +1 more source
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.
openaire +1 more source
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.
openaire +1 more source
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.
openaire +1 more source
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.
openaire +1 more source
Electron Cyclotron Heating on DIII-D
Fusion Science and Technology, 2005Electron 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
openaire +1 more source
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
openaire +1 more source
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 +6 more
openaire +1 more source
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 +6 more
openaire +1 more source
Spectroscopic characterization of the DIII-D divertor
Physics of Plasmas, 1997Radiative losses along a fixed view into the divertor chamber of the DIII-D tokamak [Plasma Physics Controlled Nuclear Fusion Research 1986 (International Atomic Energy Agency, Vienna, 1987), Vol I, p. 159] have been characterized for attached and partially detached discharges by analyzing line-integrated vacuum ultraviolet (VUV) signals.
R. C. Isler +5 more
openaire +1 more source
Bifurcation to divertor Marfes on DIII-D
Journal of Nuclear Materials, 1995Abstract The parameter dependence of the critical neutral pressure in the private flux region which is required to achieve the transition to partially detached divertor plasmas on DIII-D is found to depend linearly on the parallel heat flux and on the connexion length to the target plates.
Ph. Ghendrih +4 more
openaire +1 more source
A Brief Introduction to the DIII-D Tokamak
Fusion Science and Technology, 2005The DIII-D tokamak was a major upgrade of the Doublet III device and was commissioned in 1986. It featured a large noncircular plasma cross section and was optimized for understanding the role of t...
openaire +1 more source