Results 71 to 80 of about 4,697,162 (157)

A pulse-burst laser system for Thomson scattering on NSTX-U

Journal of Instrumentation, 2017
A pulse-burst laser system has been built for Thomson scattering on NSTX-U, and is currently being integrated into the NSTX-U Thomson scattering diagnostic system. The laser will be operated in three distinct modes. The base mode is continuous 30 Hz rep rate, and is the standard operating mode of the laser.
D.J. Den Hartog, M.T. Borchardt, D.J. Holly, A. Diallo, B. LeBlanc   +4 more
openaire   +2 more sources

PRINCETON PLASMA PHYSICS LABORATORY PRINCETON UNIVERSITY, PRINCETON, NEW JERSEY PPPL-3822 PPPL-3822 UC-70 Diagnostic Development for ST Plasmas on NSTX Availability Diagnostic Development for ST Plasmas on NSTX*

, 2020
Spherical tokamaks (STs) have much lower aspect ratio (a/R) and lower toroidal magnetic field, relative to tokamaks and stellarators. This paper will highlight some of the challenges and opportunities these features pose in the diagnosis of ST plasmas on
Nstx Team, D Johnson
core  

Observation of EHO in NSTX and Theoretical Study of its Active Control Using HHFW Antenna [PDF]

, 2013
Two important topics in the tokamak ELM control, using the non-axisymmetric (3D) magnetic perturbations, are studied in NSTX and combined envisioning ELM control in the future NSTX-U operation: Experimental observations of the edge harmonic oscillation ...
J.-K. Park, et. al.
core   +1 more source

Hybrid model predictive control techniques for safety factor profile and stored energy regulation while incorporating NBI constraints

Nuclear Fusion
A novel hybrid Model Predictive Control (MPC) algorithm has been designed for simultaneous safety factor ( q ) profile and stored energy ( w ) control while incorporating the pulse-width-modulation constraints associated with the neutral beam injection ...
Brian Leard, Zibo Wang, Sai Tej Paruchuri, Eugenio Schuster, Tariq Rafiq   +4 more
doaj   +1 more source

Publisher Correction: Effect of deuterium irradiation on graphite boronized in the NSTX-U tokamak. [PDF]

Sci Rep, 2020
Bedoya F, Allain JP, Dominguez-Gutierrez FJ, Krstic PS.   +3 more
europepmc   +1 more source

Recent progress in the interaction between energetic particles and tearing modes. [PDF]

Natl Sci Rev, 2022
Cai H, Li D.
europepmc   +1 more source

ECRH/EBWH SYSTEM FOR NSTX-

, 2012
The National Spherical Torus Experiment Upgrade (NSTX-U) will operate at an axial toroidal field of up to 1 T, about twice the field available on NSTX. A 28 GHz electron cylotron resonance heating (ECRH) system is currently being planned for NSTX-U.
Taylor, G., Ellis, R. A., Harvey, R. W., Smirnov, A. P., Hosea, J. C.   +4 more
core  

Two-dimensional AXUV-based radiated power density diagnostics on NSTX-U

, 2014
A new set of radiated-power-density diagnostics for the National Spherical Torus Experiment Upgrade (NSTX-U) tokamak have been designed to measure the two-dimensional poloidal structure of the total photon emissivity profile in order to perform power ...
Parker, R., Bell, R. E., Diallo, A., LeBlanc, B., Faust, Ian Charles, Gerhardt, S. P., Stratton, B. C., Delgado-Aparicio, L., Kozub, T. A., Tritz, K., B. C. Stratton, S. P. Gerhardt, T. A. Kozub, R. E. Bell, R. R. Parker, L. Delgado-Aparicio, K. Tritz, I. Faust, B. LeBlanc, A. Diallo   +19 more
core   +1 more source

DECAF cross-device characterization of tokamak disruptions indicated by abnormalities in plasma vertical position and current

Nuclear Fusion
Abnormal (deviating from the target) variations in the plasma vertical position Z and current $I_\textrm{p}$ (such as vertical displacements, transient $I_\textrm{p}$ ‘spikes’ and quenches) constitute common elements of a disruption, a phenomenon that is
V. Zamkovska, S.A. Sabbagh, M. Tobin, J.W. Berkery, J.D. Riquezes, Y.S. Park, K. Erickson, J. Butt, J.G. Bak, J. Kim, K.D. Lee, J. Ko, S.W. Yoon, C.J. Ham, L. Kogan, the MAST Upgrade Team   +15 more
doaj   +1 more source

TRANSP-based closed-loop simulations of current profile optimal regulation in NSTX-Upgrade

, 2019
Active control of the toroidal current density profile is critical for the upgraded National Spherical Torus eXperiment device (NSTX-U) to maintain operation at the desired high-performance, MHD-stable, plasma regime.
Ilhan, Z.O., Schuster, E., Boyer. M.D.
core   +1 more source