Results 11 to 20 of about 670 (162)

Time-Dependent Simulations of Fast-Wave Heated High-Non-Inductive-Fraction H-Mode Plasmas in the National Spherical Torus Experiment Upgrade [PDF]

EPJ Web of Conferences, 2017
30 MHz fast-wave heating may be an effective tool for non-inductively ramping low-current plasmas to a level suitable for initiating up to 12 MW of neutral beam injection on the National Spherical Tokamak Experiment Upgrade (NSTX-U).
Taylor Gary, Bertelli Nicola, Gerhardt Stefan P., Hosea Joel C., Mueller Dennis, Perkins Rory J., Poli Francesca M., Wilson James R., Raman Roger   +8 more
doaj   +2 more sources

Upward-facing lithium flash evaporator for NSTX-U [PDF]

2013 IEEE 25th Symposium on Fusion Engineering (SOFE), 2013
NSTX plasma performance has been significantly enhanced by lithium conditioning [1]. To date, the lower divertor and passive plates have been conditioned by downward facing lithium evaporators (LITER) as appropriate for lower null plasmas. The higher power operation expected from NSTX-U requires double null plasma operation in order to distribute the ...
A. L. Roquemore, D. Andruczyk, R. Majeski, D. K. Mansfield, C. H. Skinner, D. Rodgers   +5 more
openaire   +2 more sources

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   +2 more sources

Preliminary design of a tangentially viewing imaging bolometer for NSTX-U [PDF]

Review of Scientific Instruments, 2016
The infrared imaging video bolometer (IRVB) measures plasma radiated power images using a thin metal foil. Two different designs with a tangential view of NSTX-U are made assuming a 640 × 480 (1280 × 1024) pixel, 30 (105) fps, 50 (20) mK, IR camera imaging the 9 cm × 9 cm × 2 μm Pt foil. The foil is divided into 40 × 40 (64 × 64) IRVB channels.
B. J. Peterson, R. Sano, M. L. Reinke, J. M. Canik, L. F. Delgado-Aparicio, J. D. Lore, K. Mukai, T. K. Gray, G. G. van Eden, M. A. Jaworski   +9 more
openaire   +5 more sources

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   +2 more sources

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

Sci Rep, 2019
AbstractBoronization has been used in the National Spherical Torus-Upgrade (NSTX-U) as first wall conditioning technique. The technique decreased the oxygen impurities in the plasma and the O% on the Plasma Facing Components (PFC) as measured with an in-vacuo probe.
Bedoya F, Allain JP, Dominguez-Gutierrez FJ, Krstic PS.   +3 more
europepmc   +5 more sources

Verification/validation and physics model extension in high fidelity 3D RF full wave simulations on Petra-M [PDF]

, 2023
This paper reports the recent progress towards a whole-device scale RF actuator simulation. Our approach is to combine progresses made by open source scientific and math software communities for meshing, FEM assembly, and linear solvers to construct an ...
C. Lau, D. Milanesio, E. Martin, J. C. Wright, J. Hillairet, J. Myra, N. Bertelli, P. Bonoli, R. Bilato, S. Shiraiwa, W. Helou, W. Tierens   +11 more
core   +1 more source

Control and data acquisition upgrades for NSTX-U [PDF]

Fusion Engineering and Design, 2016
Abstract The extensive NSTX Upgrade (NSTX-U) Project includes major components which allow a doubling of the toroidal field strength to 1 T, of the Neutral Beam heating power to 12 MW, and the plasma current to 2 MA, and substantial structural enhancements to withstand the increased electromagnetic loads.
W.M. Davis, G.J. Tchilinguirian, T. Carroll, K.G. Erickson, S.P. Gerhardt, P. Henderson, S.H. Kampel, P. Sichta, G.N. Zimmer   +8 more
openaire   +1 more source

Neural net modeling of equilibria in NSTX-U

Nuclear Fusion, 2022
Abstract Neural networks (NNs) offer a path towards synthesizing and interpreting data on faster timescales than traditional physics-informed computational models. In this work we develop two NNs relevant to equilibrium and shape control modeling, which are part of a suite of tools being developed for the National Spherical Torus ...
J.T. Wai, M.D. Boyer, E. Kolemen
openaire   +2 more sources

Modeling of lithium granule injection in NSTX using M3D-C1 [PDF]

, 2017
In this paper, we present simulations of pedestal control by lithium granule injection (LGI) in NSTX. A model for small granule ablation has been implemented in the M3D-C1 code (Jardin et al 2012 Comput. Sci.
A. Fil, Bortolon A., Bortolon A., E. Kolemen, Hawryluk R.J., Jardin S.C., Mansfield D.K., N. Ferraro, Nazikian R., P.B. Parks, Parks P.B., Parks P.B., R. Lunsford, R. Maingi, S. Jardin   +14 more
core   +1 more source