Results 171 to 180 of about 1,608 (195)

Structure of MARFEs and ELMs in NSTX

Journal of Nuclear Materials, 2007
The fast-evolving structure of MARFEs and ELMs is observed in the National Spherical Torus Experiment (NSTX) using a fast-framing camera. It is shown that Type V ELMs, the small ELM regime in NSTX, is characterized by a poloidally propagating ionization front close to the separatrix position.
R.J. Maqueda, R. Maingi, K. Tritz, K.C. Lee, C.E. Bush, E.D. Fredrickson, J.E. Menard, A.L. Roquemore, S.A. Sabbagh, S.J. Zweben   +9 more
openaire   +1 more source

Upgrades to the NSTX HHFW antenna

AIP Conference Proceedings, 2014
The High Harmonic Fast Wave (HHFW) antenna for the National Spherical Torus Experiment (NSTX) at PPPL will be upgraded as part of the NSTX upgrade project. Higher magnetic fields and plasma current result in disruption forces on the current straps that can be up to four times the original design values.
R. Ellis, C. Brunkhorst, J. Hosea
openaire   +1 more source

Temporal structure of blobs in NSTX

Physics of Plasmas, 2022
The time dependence of the blob pulse shape and the waiting time between blobs was found using data from the gas puff imaging diagnostic in NSTX. The database used was of 103 shots from 2010 as described in a previous paper (Zweben et al., Phys. Plasmas 29, 012505 (2022).].
S. J. Zweben, M. Lampert, J. R. Myra
openaire   +1 more source

Rogowski loop designs for NSTX

18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050), 2003
The Rogowski loop is one of the most basic diagnostics for tokamak operations. On the National Spherical Torus Experiment (NSTX), the plasma current Rogowski Loop had constraints of very limited space available on the center stack, 5000 volt isolation, flexibility requirements as it remained a part of the Center Stack assembly after the first phase of ...
B. McCormack, R. Kaita, H. Kugel, R. Hatcher   +3 more
openaire   +1 more source

Heating and current drive on NSTX

AIP Conference Proceedings, 1997
Low aspect ratio tokamaks pose interesting new challenges for heating and current drive. The NSTX (National Spherical Tokamak Experiment) device to be built at Princeton is a low aspect ratio toroidal device that has the achievement of high toroidal beta (∼45%) and non-inductive operation as two of its main research goals.
J. R. Wilson, D. Batchelor, M. Carter, J. Hosea, D. Ignat, B. LeBlanc, R. Majeski, M. Ono, C. K. Phillips, J. H. Rogers, G. Schilling   +10 more
openaire   +1 more source

Secondary ELM filaments in NSTX

Journal of Nuclear Materials, 2009
Abstract Filamentary structures are observed in the scrape-off layer of the National Spherical Torus Experiment during ELMs. While the primary filaments correspond to a direct result of the ELM event, the ‘secondary’ filaments which occur generally later but still within 1 ms of the ELM onset are observed to have the same characteristics as inter-ELM
R.J. Maqueda, R. Maingi, J.-W. Ahn
openaire   +1 more source

H-mode research in NSTX

Nuclear Fusion, 2003
H-modes are routinely obtained in the National Spherical Torus Experiment (NSTX) and have become a standard operational scenario. L–H transitions triggered by NBI heating have been obtained over a wide parameter range in Ip, Bt, and e in either lower-single-null (LSN) or double-null (DN) diverted discharges.
R Maingi, M.G Bell, R.E Bell, C.E Bush, E.D Fredrickson, D.A Gates, T Gray, D.W Johnson, R Kaita, S.M Kaye, S Kubota, H.W Kugel, C.J Lasnier, B.P LeBlanc, R.J Maqueda, D Mastrovito, J.E Menard, D Mueller, M Ono, F Paoletti, S.J Paul, Y.-K.M Peng, A.L Roquemore, S.A Sabbagh, C.H Skinner, V.A Soukhanovskii, D Stutman, D.W Swain, E.J Synakowski, T Tan, J.B Wilgen, S.J Zweben   +31 more
openaire   +1 more source

Trajectory simulations for an NSTX HIBP

Review of Scientific Instruments, 2003
The ion trajectories for a heavy ion beam probe (HIBP) diagnostic for the National Spherical Torus experiment NSTX are simulated. The National Spherical Torus experiment (NSTX) equilibria modeled include both low β and high β (β=23%) discharges. The simulation used a sodium ion beam with energies varying from 350 to 550 keV.
X. Zhang, P. M. Schoch, K. A. Connor
openaire   +1 more source

Engineering-Physical Model (GLOBSYS) for the Next STEP of the Globus-M Spherical Tokamak Program: Verification of Some Subsystems on Achieved and Predictable Data From Installations NSTX, NSTX-U, MAST, MAST-U, and ST40

Physics of Atomic Nuclei, 2022
V N Tanchuk, G S Kurskiev, E N Bondarchuk   +2 more
exaly  

MHD Simulations of Disruptions in NSTX

2011
Research tokamaks such as ITER must be designed to tolerate a limited number of disruptions without sustaining significant damage. It is therefore vital to have numerical tools that can accurately predict the effects of these events. The 3D nonlinear extended MHD code M3D [1] has been augmented with models of the vacuum/halo region and a thin ...
JA Breslau, HR Strauss, R Paccagnella, SC Jardin   +3 more
openaire   +2 more sources