Results 51 to 60 of about 670 (162)

Exploration of the equilibrium operating space for NSTX-Upgrade [PDF]

, 2012
This paper explores a range of high-performance equilibrium scenarios available in the NSTX-Upgrade device [J.E. Menard, submitted for publication to Nuclear Fusion]. NSTX-Upgrade is a substantial upgrade to the existing NSTX device [M.
, Abdou M., Akers R.J., Angioni C., Bell M., Boyle D.P., Breslau J., Buttery R., Chapman I.T., Chapman I.T., Chapman I.T., Diallo A., Dickinson D., Ferron J.R., Fredrickson E.D., Fredrickson E.D., Galeev A.A., Gates D.A., Gates D.A., Gates D.A., Gates D.A., Gerhardt S.P., Gerhardt S.P., Gerhardt S.P., Gerhardt S.P., Gerhardt S.P., Glasser A.H., Goldston R.J., Greenwald M., Greenwald M., Greenwald M., Gryaznevich M., Gryaznevich M.P., Gude A., Gunter S., Hawryluk R.J., Heidbrink W.W., J.E. Menard, Kaye S.M., Kaye S.M., Kessel C.E., Kinsey J.E., Liu D., Menard J.E., Menard J.E., Menard J.E., Menard J.E., Menard J.E., Menard J.E., Menard J.E., Moreau D., Moreau D., Murakami M., Ohkawa T., Ono M., Peeters A.G., Peng Y.-K.M., Peng Y.-K.M., Peng Y.-K.M., Peng Y.-K.M., Peng Y.K.M., Politzer P.A., R. Andre, Reimerdes H., Roberto M., S.P. Gerhardt, Sabbagh S.A., Sabbagh S.A., Sabbagh S.A., Sabbagh S.A., Sabbagh S.A., Sharapov S.E., Sips A.C.C., Sontag A.C., Sontag A.C., Soukhanovskii V.A., Soukhanovskii V.A., Staebler G.M., Stambaugh R.D., Stambaugh R.D., Stevenson T., Suzuki T., Suzuki T., Sykes A., Troyon F., Turnyanski M., Valovic M., Valovic M., Voitsekhovitch I., Wesson J., Wilson H.R., Wilson H.R.   +91 more
core   +1 more source

Spherical tokamak physics research in preparation for the operation of NSTX-U

Nuclear Fusion
The National Spherical Torus Experiment Upgrade (NSTX-U) is preparing to resume operation, representing a crucial step toward realizing compact, cost-effective fusion pilot plants.
S. Munaretto, P.O. Adebayo-Ige, H. Anand, G. Avdeeva, S.G. Baek, K. Barada, E. Belli, E.V. Belova, J.W. Berkery, T.N. Bernard, N. Bertelli, P. Bonofiglo, P.T. Bonoli, M.D. Boyer, J. Candy, C.S. Chang, H. Chung, C. Clauser, M. Comanescu, D. Corona, N.A. Crocker, R. De Levante Rodriguez, E.W. DeShazer, A. Diallo, J. Dominski, V.N. Duarte, F. Ebrahimi, E.D. Emdee, S. Ethier, N.M. Ferraro, E.L. Foley, E.D. Fredrickson, M.E. Galante, K.F. Gan, S. Gerhardt, R.J. Goldston, M. Gorelenkova, W. Guttenfelder, R. Hager, F.D. Halpern, J. Halpern, D. Hatch, F. Hoffmann, M.S. Islam, S.C. Jardin, S.M. Kaye, A. Khodak, J.E. Kinsey, A. Kleiner, E. Kolemen, S. Ku, M. Lampert, B. Leard, B.P. LeBlanc, J.B. Lestz, F.M. Levinton, P.-Y. Li, N.C. Logan, N.A. Lopez, R. Lunsford, T. Macwan, R. Maingi, J. McClenaghan, A.G. McLean, J.E. Menard, Y.-S. Na, A.O. Nelson, M. Ono, A. Pajares, A. Pankin, J. Parisi, F.I. Parra, M.S. Parsons, B.S. Patel, M. Podestá, F.M. Poli, M. Porcelli, T. Rafiq, R. Raman, J.D. Riquezes, S.A. Sabbagh, A. Sanchez-Villar, E. Schuster, S. Shiraiwa, T. Singh, S.P. Smith, D. Smith, V.A. Soukhanovskii, G.M. Staebler, B. Stratton, K.E. Thome, M. Tobin, I.U. Uzun-Kaymak, B. Van Compernolle, W.X. Wang, W. Wehner, A.S. Welander, B.D. Wirth, J. Yang, V. Zamkovska, X. Zhang   +100 more
doaj   +1 more source

Securing MDSplus for the NSTX-U Digital Coil Protection System [PDF]

2015 IEEE 26th Symposium on Fusion Engineering (SOFE), 2015
NSTX used MDSplus extensively to record data, relay information and control data acquisition hardware. For NSTX-U the same functionality is expected as well as an expansion into the realm of securely maintaining parameters for machine protection. Specifically, we designed the Digital Coil Protection System (DCPS) to use MDSplus to manage our physical ...
Gregory J. Tchilinguirian, Keith G. Erickson   +1 more
openaire   +1 more source

Heat Flux Model Validation Utilizing Convolutional Neural Networks and Sub-surface Thermocouples for NSTX-U [PDF]

, 2018
A proof of concept convolutional neural network (CNN) has been developed to assist in operating tokamaks outside of existing empirical scalings for the heat flux width, λq [lambda-q].
Looby, Thomas Patrick
core   +1 more source

Flowing liquid lithium plasma-facing components – Physics, technology and system analysis of the LiMIT system

Nuclear Materials and Energy, 2017
The use of low atomic number liquid metals has been shown to have the potential to solve many of the prevalent problems like erosion and radiation losses associated with the interaction of fusion plasma with the plasma facing component (PFC) structures ...
D.N. Ruzic, M. Szott, C. Sandoval, M. Christenson, P. Fiflis, S. Hammouti, K. Kalathiparambil, I. Shchelkanov, D. Andruczyk, R. Stubbers, C. Joel Foster, B. Jurczyk   +11 more
doaj   +1 more source

Global gyrokinetic simulations of kinetic ballooning mode in NSTX-U plasmas

Nuclear Fusion
Understanding the kinetic ballooning mode (KBM) is crucial for optimizing plasma performance in high- β spherical tokamaks. Global gyrokinetic simulations of KBMs in a projected NSTX-U shot are presented using realistic magnetic geometry and plasma ...
Tajinder Singh, Tariq Rafiq, Eugenio Schuster, Zhihong Lin, Animesh Kuley   +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

Análise dos critérios utilizados pelo código DECAF para a previsão de eventos de instabilidade no plasma do reator NSTX-U [PDF]

, 2021
Trabalho de Conclusão de Curso (graduação)—Universidade de Brasília, Faculdade UnB Gama, Curso de Engenharia de Energia, 2021.Frente a um cenário em que a demanda energética brasileira cresce a taxas de 2,2% a.a., é necessária a introdução de uma fonte ...
Dantas, Débora da Silva
core  

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

Numerical optimization of three-dimensional coils for NSTX-U

Plasma Physics and Controlled Fusion, 2015
A tool for the calculation of optimal three-dimensional (3D) perturbative magnetic fields in tokamaks has been developed. The IPECOPT code builds upon the stellarator optimization code STELLOPT to allow for optimization of linear ideal magnetohydrodynamic perturbed equilibrium (IPEC).
S A Lazerson, J-K Park, N Logan, A Boozer   +3 more
openaire   +2 more sources