Results 91 to 100 of about 3,538 (193)

Counter-propagating toroidal Alfvén eigenmodes in tokamaks

Nuclear Fusion
Mechanisms of destabilization of toroidal Alfvén eigenmodes (TAEs) in tokamaks are analyzed with the aim to reveal those leading to modes propagating in the direction opposite to plasma current, i.e. counter-propagating modes (ctr-TAE). Plasmas with fast-
Ya.I. Kolesnichenko, E.D. Fredrickson, V.V. Lutsenko, A.V. Tykhyy   +3 more
doaj   +1 more source

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

Comparative Analysis of the public discourse about fusion and nuclear energy before and after Fukushima: WP12-SER-ACIF-1 Final Report [PDF]

, 2013
This report presents a comparative analysis of media coverage of fusion and fission energy before and after the accident in the nuclear reactors of Fukushima, Japan.
Horta, Ana, Oliveira, Carla, Pereira, Sérgio, Schmidt, Luísa   +3 more
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

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

NSTX/NSTX-U theory, modeling and analysis results

Nuclear Fusion, 2019
S.M. Kaye, D.J. Battaglia, D. Baver, E. Belova, J.W. Berkery, V.N. Duarte, N. Ferraro, E. Fredrickson, N. Gorelenkov, W. Guttenfelder, G.Z. Hao, W. Heidbrink, O. Izacard, D. Kim, I. Krebs, R. La Haye, J. Lestz, D. Liu, L.A. Morton, J. Myra, D. Pfefferle, M. Podesta, Y. Ren, J. Riquezes, S.A. Sabbagh, M. Schneller, F. Scotti, V. Soukhanovskii, S.J. Zweben, J.W. Ahn, J.P. Allain, R. Barchfeld, F. Bedoya, R.E. Bell, N. Bertelli, A. Bhattacharjee, M.D. Boyer, D. Brennan, G. Canal, J. Canik, N. Crocker, D. Darrow, L. Delgado-Aparicio, A. Diallo, C. Domier, F. Ebrahimi, T. Evans, R. Fonck, H. Frerichs, K. Gan, S. Gerhardt, T. Gray, T. Jarboe, S. Jardin, M.A. Jaworski, R. Kaita, B. Koel, E. Kolemen, D.M. Kriete, S. Kubota, B.P. LeBlanc, F. Levinton, N. Luhmann, R. Lunsford, R. Maingi, R. Maqueda, J.E. Menard, D. Mueller, C.E. Myers, M. Ono, J.-K. Park, R. Perkins, F. Poli, R. Raman, M. Reinke, T. Rhodes, C. Rowley, D. Russell, E. Schuster, O. Schmitz, Y. Sechrest, C.H. Skinner, D.R. Smith, T. Stotzfus-Dueck, B. Stratton, G. Taylor, K. Tritz, W. Wang, Z. Wang, I. Waters, B. Wirth   +90 more
openaire   +2 more sources

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

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

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