Results 81 to 90 of about 4,697,162 (157)

Feedforward equilibrium trajectory optimization with GSPulse

Nuclear Fusion
One of the common tasks required for designing new plasma scenarios or evaluating capabilities of a tokamak is to design the desired equilibria using a Grad-Shafranov (GS) equilibrium solver.
J.T. Wai, M.D. Boyer, D.J. Battaglia, A. Merle, F. Carpanese, F. Felici, M. Kochan, E. Kolemen   +7 more
doaj   +1 more source

Determining the validity of tokamak perturbed equilibrium modeling using nonlinear equilibria

Nuclear Fusion
The prediction of perturbed equilibrium models for tokamaks with small non-axisymmetric fields is strongly dependent on which reference frame for axisymmetry is assumed.
J. Halpern, N.C. Logan, E. Paul, C. Paz-Soldan   +3 more
doaj   +1 more source

Plasma self-driven current in tokamaks with magnetic islands

Nuclear Fusion
Magnetic island perturbations may cause a reduction in plasma self-driven current that is needed for tokamak operation. A novel effect on tokamak self-driven current revealed by global gyrokinetic simulations is due to magnetic-island-induced 3D electric
W.X. Wang, M.G. Yoo, E.A. Startsev, S. Kaye, S. Ethier, J. Chen   +5 more
doaj   +1 more source

Selection and demography drive range-wide patterns of MHC-DRB variation in mule deer. [PDF]

BMC Ecol Evol, 2022
Cook RM, Suttner B, Giglio RM, Haines ML, Latch EK.   +4 more
europepmc   +1 more source

The Impact of Machine Learning on 2D/3D Registration for Image-Guided Interventions: A Systematic Review and Perspective. [PDF]

Front Robot AI, 2021
Unberath M, Gao C, Hu Y, Judish M, Taylor RH, Armand M, Grupp R.   +6 more
europepmc   +1 more source

Modeling of plasma rotation control for NSTX and NSTX-U

, 2016
This thesis studies some applications of feedback control design for plasma physics, specifically plasma drift waves and plasma toroidal rotation and covers two major steps: reduced-order modeling and controller design. This dissertation focuses
Goumiri, Imene
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Divertor leg filaments in NSTX-U

Nuclear Fusion, 2018
Filippo Scotti, Stewart Zweben, Vlad Soukhanovskii, Derek Baver, James Myra   +4 more
openaire   +2 more sources

Diagnostic Development on NSTX

, 2020
-Diagnostics are described which are currently installed or under active development for the newly commissioned NSTX device. The low aspect ratio (R/a£1.3) and low toroidal field (0.1-0.3T) used in this device dictate adaptations in many standard ...
Nstx Team, A L Roquemore, R Kaita, D Johnson   +3 more
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ECH on NSTX [PDF]

, 1997
Electron Cyclotron Heating has been proposed for plasma initiation, startup assistance and non-inductive startup on NSTX. One physics goal of NSTX will be to establish entirely non-inductive plasma operation by utilizing ECH to provide a sufficient start-
Carter, M. D., Batchelor, D. B., Bigelow, T. S., Peng, M., Wilson, J. R.   +4 more
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Modeling of a Laser-Induced Rydberg Spectroscopy diagnostic for Direct Measurement of the Local Electric Field in the Edge Region of NSTX/NSTX-U

, 2018
We discuss a novel diagnostic allowing direct measurements of the local electric field in the edge region in NSTX/NSTX-U. This laser based diagnostic's principle consists of depleting the naturally populated $n=3$ level to a Rydberg state --sensitive to ...
Reymond, L., Vekselman, V., Diallo, A.
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