Results 51 to 60 of about 3,538 (193)

Observation of stationary filaments with resonant magnetic perturbations in NSTX

Nuclear Fusion
The application of resonant magnetic perturbations (RMPs) induces striated heat fluxes on the divertor plate in tokamaks. These striated heat fluxes were previously considered strike point splitting by the intersection between the divertor and predicted ...
K.F. Gan, E.D. Fredrickson, J.W. Berkery, S. Munaretto, A. Kleiner, M. Lampert, J.-K. Park, R. Maingi, A.G. McLean, T.K. Gray, B.D. Wirth   +10 more
doaj   +1 more source

The effect of gas injection location on a lithium vapor box divertor in NSTX-U

Nuclear Fusion, 2023
The lithium vapor box divertor is a proposed divertor design that will minimize contamination of the upstream plasma in a fusion device, while also ensuring protection of the target.
E.D. Emdee, R.J. Goldston
doaj   +1 more source

Interaction between Faraday rotation and Cotton-Mouton effects in polarimetry modeling for NSTX

, 2010
The evolution of electromagnetic wave polarization is modeled for propagation in the major radial direction in the National Spherical Torus Experiment (NSTX) with retroreflection from the center stack of the vacuum vessel.
J. Zhang, N. A. Crocker, S. Kubota, Swanson D. G., T. A. Carter, W. A. Peebles   +5 more
core   +1 more source

Kinetic Profiles in NSTX Plasmas [PDF]

, 2001
The National Spherical Torus Experiment (NSTX) is a low aspect ratio (R/a approximately 1.3) device with auxiliary heating from neutral-beam injection (NBI) and high-harmonic fast-wave heating (HHFW). Typical NSTX parameters are R(subscript ''0'') = 85 cm, a = 67 cm, I(subscript ''p'') = 0.7-1.4 MA, B(subscript ''phi'') = 0.25-0.45 T. Three co-directed
Bell, R. E., LeBlanc, B. P., Bourdelle, C., Ernst, D. R., Fredrickson, E. D., Gates, D. A., Hosea, J. C., Johnson, D. W., Kaye, S. M., Maingi, R., Medley, S., Menard, J. E., Mueller, D., Ono, M., Paoletti, F., Peng, M., Sabbagh, S. A., Stutman, D., Swain, D. W., Synakowski, E. J., Wilson, J. R.   +20 more
openaire   +2 more sources

Sensitivity of WallDYN material migration modeling to uncertainties in mixed-material surface binding energies

Nuclear Materials and Energy, 2017
The WallDYN package has recently been applied to a number of tokamaks to self-consistently model the evolution of mixed-material plasma facing surfaces.
J.H. Nichols, M.A. Jaworski, K. Schmid
doaj   +1 more source

Reversed magnetic shear scenario development in NSTX-U using TRANSP

Nuclear Fusion
Understanding and control of electron thermal transport is a critical point of research in magnetic fusion experiments. Previous experiments have shown that operation with reversed magnetic shear (RMS) can suppress electron thermal transport, resulting ...
M.E. Galante, M.D. Boyer, I.U. Uzun-Kaymak, E.L. Foley, B.P. LeBlanc, F.M. Levinton   +5 more
doaj   +1 more source

Reduced physics model of the tokamak Scrape-Off-Layer for pulse design

Nuclear Materials and Energy, 2023
The dynamic interplay between the core and the edge plasma has important consequences in the confinement and heating of fusion plasma. The transport of the Scrape-Off-Layer (SOL) plasma imposes boundary conditions on the core plasma, and neutral ...
X. Zhang, F.M. Poli, E.D. Emdee, M. Podestà   +3 more
doaj   +1 more source

Demonstration of transient CHI startup using a floating biased electrode configuration

Nuclear Fusion, 2023
Results from the successful solenoid-free plasma startup using the method of transient coaxial helicity injection (transient CHI) in the QUEST spherical tokamak (ST) are reported.
K. Kuroda, R. Raman, T. Onchi, M. Hasegawa, K. Hanada, M. Ono, B.A. Nelson, J. Rogers, R. Ikezoe, H. Idei, T. Ido, M. Nagata, O. Mitarai, N. Nishino, Y. Otsuka, Y. Zhang, K. Kono, S. Kawasaki, T. Nagata, A. Higashijima, S. Shimabukuro, I. Niiya, I. Sekiya, K. Nakamura, Y. Takase, A. Ejiri, S. Murakami   +26 more
doaj   +1 more source

NSTX High Temperature Sensor Systems [PDF]

, 1999
The design of the more than 300 in-vessel sensor systems for the National Spherical Torus Experiment (NSTX) has encountered several challenging fusion reactor diagnostic issues involving high temperatures and space constraints. This has resulted in unique miniature, high temperature in-vessel sensor systems mounted in small spaces behind plasma facing ...
B.McCormack, Kugel, H.W., Goranson, P., Kaita, R., al, et   +4 more
openaire   +2 more sources

Importance of on ETG stability, turbulence, and transport in NSTX

Nuclear Fusion
This study employs electron-scale gyrokinetic simulations to investigate the electron temperature gradient (ETG) driven instabilities, turbulence, and transport in the pedestal region of the National Spherical Torus Experiment, comparing non-lithiated ...
P.-Y. Li, D.R. Hatch, J.F. Parisi, M. Lampert, E.A. Belli, M. Kotschenreuther, S.M. Mahajan   +6 more
doaj   +1 more source