Results 41 to 50 of about 1,608 (195)

The H-mode Pedestal and Edge Localized Modes in NSTX [PDF]

, 2004
The research program of the National Spherical Torus Experiment (NSTX) routinely utilizes the H-mode confinement regime to test and extend beta and pulse length limits.
Roquemore, A. L., Nishino, N., Fredrickson, E. D., Maingi, R., Menard, J. E., Sabbagh, S. A., Tritz, K.   +6 more
core   +1 more source

In search of X-point radiator regime features in NSTX and DIII-D discharges with the snowflake divertor

Nuclear Materials and Energy
Experimental data from NSTX and DIII-D discharges with the snowflake (SF) divertor configurations are analyzed toward the development of the X-point radiator (XPR) concept. The XPR divertor regime was recently realized in standard divertor configurations
V.A. Soukhanovskii, S.L. Allen, M.E. Fenstermacher, C.J. Lasnier, A.G. McLean, F. Scotti, E. Kolemen, A. Diallo, S. Gerhardt, S. Kaye, B.P. LeBlanc, R. Maingi, J.E. Menard, R. Raman, A.W. Hyatt, A.W. Leonard, T.H. Osborne   +16 more
doaj   +1 more source

NSTX-U research advancing the physics of spherical tokamaks

Nuclear Fusion
The objectives of NSTX-U research are to reinforce the advantages of STs while addressing the challenges. To extend confinement physics of low- A , high beta plasmas to lower collisionality levels, understanding of the transport mechanisms that set ...
J.W. Berkery, P.O. Adebayo-Ige, H. Al Khawaldeh, G. Avdeeva, S-G. Baek, S. Banerjee, K. Barada, D.J. Battaglia, R.E. Bell, E. Belli, E.V. Belova, N. Bertelli, N. Bisai, P.T. Bonoli, M.D. Boyer, J. Butt, J. Candy, C.S. Chang, C.F. Clauser, L.D. Corona Rivera, M. Curie, P.C. de Vries, R. Diab, A. Diallo, J. Dominski, V.N. Duarte, E.D. Emdee, N.M. Ferraro, R. Fitzpatrick, E.L. Foley, E. Fredrickson, M.E. Galante, K.F. Gan, S. Gerhardt, R. Goldston, W. Guttenfelder, R. Hager, M.O. Hanson, S.C. Jardin, T.G. Jenkins, S.M. Kaye, A. Khodak, J. Kinsey, A. Kleiner, E. Kolemen, S. Ku, M. Lampert, B. Leard, B.P. LeBlanc, J.B. Lestz, F.M. Levinton, C. Liu, T. Looby, R. Lunsford, T. Macwan, R. Maingi, J. McClenaghan, J.E. Menard, S. Munaretto, M. Ono, A. Pajares, J. Parisi, J-K. Park, M.S. Parsons, B.S. Patel, Y.V. Petrov, M. Podestà, F. Poli, M. Porcelli, T. Rafiq, S.A. Sabbagh, Á. Sánchez Villar, E. Schuster, J. Schwartz, A. Sharma, S. Shiraiwa, P. Sinha, D. Smith, S. Smith, V.A. Soukhanovskii, G. Staebler, E. Startsev, B. Stratton, K.E. Thome, W. Tierens, M. Tobin, I.U. Uzun-Kaymak, B. Van Compernolle, J. Wai, W. Wang, W. Wehner, A. Welander, J. Yang, V. Zamkovska, X. Zhang, X.L. Zhu, S. Zweben   +96 more
doaj   +1 more source

Rogowski Loop design for NSTX [PDF]

, 2000
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 the constraints of the very limited space available on the center stack, 5,000 volt isolation, flexibility requirements as it remained a part of the Center Stack assembly after the first ...
McCormack, B., Kaita, R., Kugel, H., Hatcher, R.   +3 more
openaire   +2 more sources

The NSTX fast-ion D-alpha diagnostic [PDF]

Review of Scientific Instruments, 2008
A new diagnostic, aimed at energy-resolved measurements of the spatial and temporal dynamics of fast ions in NSTX plasmas, is described. It is based on active charge-exchange recombination spectroscopy. The fast-ion signal is inferred from light emitted in the wavelength range of the Dα line by fast ions recombining with an injected neutral beam.
Podestà, M, Heidbrink, WW, Bell, RE, Feder, R   +3 more
openaire   +4 more sources

Tokamak Simulation Code modeling of NSTX [PDF]

, 2000
The Tokamak Simulation Code [TSC] is widely used for the design of new axisymmetric toroidal experiments. In particular, TSC was used extensively in the design of the National Spherical Torus eXperiment [NSTX].
Jardin, S. C., Kaye, S., Glasser, A. H., Menard, J., Kessel, C.   +4 more
core   +1 more source

Snowflake divertor configuration studies for NSTX-Upgrade [PDF]

, 2011
Snowflake divertor experiments in NSTX provide basis for PMI development toward NSTX-Upgrade. Snowflake configuration formation was followed by radiative detachment. Significant reduction of steady-state divertor heat flux observed in snowflake divertor.
Soukhanovskii, V A
core  

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

2D full-wave simulation of waves in space and tokamak plasmas

EPJ Web of Conferences, 2017
Simulation results using a 2D full-wave code (FW2D) for space and NSTX fusion plasmas are presented. The FW2D code solves the cold plasma wave equations using the finite element method.
Kim Eun-Hwa, Bertelli Nicola, Johnson Jay, Valeo Ernest, Hosea Joel   +4 more
doaj   +1 more source

Elimination of inter-discharge helium glow discharge cleaning with lithium evaporation in NSTX

Nuclear Materials and Energy, 2017
Operation in the National Spherical Torus Experiment (NSTX) typically used either periodic boronization and inter-shot helium glow discharge cleaning (HeGDC), or inter-shot lithium evaporation without boronization, and initially with inter-shot HeGDC. To
R. Maingi, R. Kaita, F. Scotti, V.A. Soukhanovskii   +3 more
doaj   +1 more source