Results 101 to 110 of about 1,608 (195)

Predictive modeling of NSTX discharges with the updated multi-mode anomalous transport module

Nuclear Fusion
The objective of this study is twofold: firstly, to demonstrate the consistency between the anomalous transport results produced by updated Multi-Mode Model (MMM) version 9.0.4 and those obtained through gyrokinetic simulations; and secondly, to showcase
T. Rafiq, C. Wilson, C. Clauser, E. Schuster, J. Weiland, J. Anderson, S.M. Kaye, A. Pankin, B.P. LeBlanc, R.E. Bell   +9 more
doaj   +1 more source

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

Sci Rep, 2020
Bedoya F, Allain JP, Dominguez-Gutierrez FJ, Krstic PS.   +3 more
europepmc   +1 more source

A Decade of NSTX Operations Using Collaborative Software

, 2009
Since the beginning of the National Spherical Torus Experiment's (NSTX) research activities in 1999, open-source and collaborative software have been used extensively for experimental operations.
P. Sichta, W. Davis, J. Dong, D. Mastrovito, G. Tchilinguirian, G. Zimmer
core  

Hybrid model predictive control techniques for safety factor profile and stored energy regulation while incorporating NBI constraints

Nuclear Fusion
A novel hybrid Model Predictive Control (MPC) algorithm has been designed for simultaneous safety factor ( q ) profile and stored energy ( w ) control while incorporating the pulse-width-modulation constraints associated with the neutral beam injection ...
Brian Leard, Zibo Wang, Sai Tej Paruchuri, Eugenio Schuster, Tariq Rafiq   +4 more
doaj   +1 more source

Industrial Applications of Dinoflagellate Phycotoxins Based on Their Modes of Action: A Review. [PDF]

Toxins (Basel), 2020
Cho K, Heo J, Han J, Hong HD, Jeon H, Hwang HJ, Hong CY, Kim D, Han JW, Baek K.   +9 more
europepmc   +1 more source

Liquid lithium as divertor material to mitigate severe damage of nearby components during plasma transients. [PDF]

Sci Rep, 2022
Sizyuk V, Hassanein A.
europepmc   +1 more source

FLIPEC, an ideal MHD free-boundary axisymmetric equilibrium solver in the presence of macroscopic flows

Nuclear Fusion
The most relevant features of FLIPEC (Free fLow Iterative Plasma Equilibrium Code) are presented. This new code iteratively calculates free-boundary, axisymmetric ideal MHD equilibria with arbitrary poloidal and toroidal plasma flows.
G. F.-Torija Daza, J.M. Reynolds-Barredo, R. Sanchez, A. Loarte, V. Tribaldos   +4 more
doaj   +1 more source

Lithium vapor cave design considerations

Nuclear Materials and Energy
Recent calculations of the lithium vapor box divertor using SOLPS have demonstrated that far Scrape-Off Layer (SOL) baffling and the corresponding far SOL lithium evaporation are unnecessary for divertor performance.
E.D. Emdee, R.J. Goldston
doaj   +1 more source

Overview of impurity control and wall conditioning in NSTX [PDF]

, 2000
The National Spherical Torus Experiment (NSTX) started plasma operations in February 1999, In the first extended period of experiments, NSTX achieved high current, inner wall limited, double null, and single null plasma discharges, initial Coaxial ...
Berry, R.E., al, et, Maingi, R., Kugel, H.W., Wampler, W.   +4 more
core  

Development of a data-driven neural network model for electron thermal transport in NSTX

Nuclear Fusion
A data-driven electron thermal transport neural network (ETT-NN) model, trained on TRANSP interpretative analysis results of National Spherical Torus Experiment (NSTX), was developed to enable faster and more accurate ETT computation for spherical ...
H. Chung, C.Y. Lee, G.J. Choi, S.M. Kaye, B.P. LeBlanc, J.W. Berkery, Y.-S. Na   +6 more
doaj   +1 more source