Results 51 to 60 of about 20,009 (190)
Infrared thermography system on DIII-D [PDF]
Six infrared cameras measure temperature changes on the protective graphite armor inside the DIII-D vacuum vessel. Simultaneous time-dependent temperature measurements are made on armor tiles located on the centerpost and divertor regions, and on both outboard limiters.
T. W. Petrie +3 more
openaire +1 more source
Access conditions for full suppression of Edge Localised Modes (ELMs) by Magnetic Perturbations (MP) in low density high confinement mode (H-mode) plasmas are studied in the ASDEX Upgrade tokamak.
Bobkov, V. +11 more
core +1 more source
The onset of type I edge localized modes (ELMs) is investigated on the DIII-D tokamak. A fast imaging camera is used with an integration time of 1 νs and a time between frames of about 15 νs continuously recording for a period of 1.3 s.
Antar, G. +5 more
core +2 more sources
Disruption mitigation studies in DIII-D [PDF]
Data on the discharge behavior, thermal loads, halo currents, and runaway electrons have been obtained in disruptions on the DIII-D tokamak [J. L. Luxon and L. G. Davis, Fusion Technol. 8, 2A 441 (1985)]. These experiments have also evaluated techniques to mitigate the disruptions while minimizing runaway electron production.
P. L. Taylor +13 more
openaire +3 more sources
In addition to the receptor-binding domain (DII), the C-terminal domain (DIII) of three-domain Cry insecticidal δ-endotoxins from Bacillus thuringiensis has been implicated in target insect specificity, yet its precise mechanistic role remains unclear ...
Anon Thammasittirong +7 more
doaj +1 more source
Advanced tokamak physics in DIII-D [PDF]
Advanced tokamaks seek to achieve a high bootstrap current fraction without sacrificing fusion power density or fusion gain. Good progress has been made towards the DIII-D research goal of demonstrating a high-β advanced tokamak plasma in steady state with a relaxed, fully non-inductive current profile and a bootstrap current fraction greater than 50%.
Petty, CC +48 more
openaire +3 more sources
Advances in radiated power control at DIII-D
Feedback control of radiated power from the lower divertor Prad, div, L has been implemented in the DIII-D Plasma Control System (PCS). A realtime sensor for Prad, div, L has been constructed from 12 foil bolometer channels which agrees with standard ...
D. Eldon +9 more
doaj +1 more source
Direct Gyrokinetic Comparison of Pedestal Transport in JET with Carbon and ITER-Like Walls [PDF]
This paper compares the gyrokinetic instabilities and transport in two representative JET pedestals, one (pulse 78697) from the JET configuration with a carbon wall (C) and another (pulse 92432) from after the installation of JET's ITER-like Wall (ILW ...
Field, A. R. +11 more
core +2 more sources
Experiments on plasma detachment in a V-shaped slot divertor in the DIII-D tokamak
Experiments in DIII-D demonstrate that the upstream plasma density to detach an un-pumped slot divertor is similar for a V-shaped and a flat-end slot, despite significantly higher neutral pressure in the V-shaped slot and in contrast to SOLPS-ITER ...
R. Maurizio +14 more
doaj +1 more source
The 2D spatial distributions of cross field drift velocities are calculated from 2D Thomson scattering measurements of Te and ne in the divertor and SOL of DIII-D.
P.C. Stangeby +3 more
doaj +1 more source

