Results 171 to 180 of about 3,538 (193)

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

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

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

A real-time velocity diagnostic for NSTX

Review of Scientific Instruments, 2012
A new system for fast measurements of the plasma toroidal velocity has been installed on the National Spherical Torus Experiment, NSTX [M. Ono et al., Nucl. Fusion 40, 557 (2000)10.1088/0029-5515/40/3Y/316]. The diagnostic, based on active charge-exchange recombination spectroscopy, can measure at up to six radial locations with maximum sampling rate ...
M, Podestà, R E, Bell
openaire   +2 more sources

NSTX OH Coil Design Improvements

2007 IEEE 22nd Symposium on Fusion Engineering, 2007
The National Spherical Torus Experiment (NSTX) has been operating successfully since February of 1999. A unique element of NSTX is the center solenoid or OH coil that from the start has been a design challenged by the low aspect ratio/geometry of the device.
M. Kalish, J. Chrzanowski, C. Neumeyer, B. Paul, R. Woolley, C. Jun   +5 more
openaire   +1 more source

The motional Stark effect diagnostic on NSTX

Review of Scientific Instruments, 2008
This work describes the implementation and recent results from the motional Stark effect (MSE) collisionally induced fluorescence diagnostic on NSTX. Due to the low magnetic field on NSTX the MSE diagnostic requires a new approach for the viewing optics and spectral filter.
F M, Levinton, H, Yuh
openaire   +2 more sources

Power system for NSTX upgrade

2011 IEEE/NPSS 24th Symposium on Fusion Engineering, 2011
This The National Spherical Torus Experiment (NSTX) has been designed and installed in the existing facilities at Princeton Plasma Physic Laboratory (PPPL). Most of the hardware, plant facilities, auxiliary sub-systems, and power systems originally used for the Tokamak Fusion Test Reactor (TFTR) have been used with suitable modifications to reflect ...
S. Ramakrishnan, C. Neumeyer, J. Lawson, R. Mozulay, E. Baker, R. Hatcher, N. Desai, null Weiguo Que, null Xin Zhao   +8 more
openaire   +1 more source

NSTX-U Construction Related Analysis Issues

Fusion Science and Technology, 2015
The National Spherical Torus Experiment Upgrade (NSTX-U) is currently under construction at Princeton Plasma Physics Laboratory (PPPL) It is scheduled to start operations early in 2015. Upgrade designs were analyzed and qualified prior to the beginning of construction, but many issues arose during manufacture and assembly that required adjustments in ...
Peter H. Titus*, L. Dudek, M. Smith, A. Brooks   +3 more
openaire   +1 more source

Heat flux scaling experiments in NSTX

Journal of Nuclear Materials, 2003
Abstract We report the first results of heat flux scaling experiments in National Spherical Torus Experiment (NSTX). We find that the peak heat flux observed in the outer divertor was ∼6 MW/m2 at 5 MW heating power in lower-single-null diverted configuration.
R. Maingi, H.W. Kugel, C.J. Lasnier, A.L. Roquemore, V.A. Soukhanovskii, C.E. Bush, null The NSTX Team   +6 more
openaire   +1 more source

Linear ion-scale microstability analysis of high and low-collisionality NSTX discharges and NSTX-U projections

Physics of Plasmas, 2022
C F Clauser, Walter Guttenfelder, Tariq Rafiq   +2 more
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