Results 101 to 110 of about 12,708 (208)

Study and analysis of ion cyclotron resonance heating scenarios for ADITYA-U Tokamak

Nuclear Fusion
This study provides a detailed analysis of ion cyclotron resonance heating (ICRH) scenarios for ADITYA-U Tokamak which is a crucial technique for core plasma heating in magnetically confined devices.
Akhil Jha, Amit K. Singh, Devarshi Brahmakshatriya, Harshita Raj, Joydeep Ghosh, R.G. Trivedi, Indranil Bandyopadhyay, Olivier Sauter   +7 more
doaj   +1 more source

Steady-state burning plasma: a new stage in the development of magnetic confinement fusion energy. [PDF]

Natl Sci Rev, 2023
Wan B, Xu G.
europepmc   +1 more source

Feasibility of main thermal ion heating by ICRF waves using a top launcher in a tokamak with deuterium–tritium plasmas

Nuclear Fusion
A scenario of ion cyclotron range of frequency (ICRF) wave injection from a top launcher is proposed as an efficient and direct heating method for thermal deuterium ions in deuterium–tritium tokamak plasmas. Positioned between the tritium cyclotron layer
Jungpyo Lee, Nicola Bertelli, John Wright, Syun’ichi Shiraiwa, Roberto Bilato, Paul Bonoli   +5 more
doaj   +1 more source

Plasma surrogate modelling using Fourier neural operators

Nuclear Fusion
Predicting plasma evolution within a Tokamak reactor is crucial to realizing the goal of sustainable fusion. Capabilities in forecasting the spatio-temporal evolution of plasma rapidly and accurately allow us to quickly iterate over design and control ...
Vignesh Gopakumar, Stanislas Pamela, Lorenzo Zanisi, Zongyi Li, Ander Gray, Daniel Brennand, Nitesh Bhatia, Gregory Stathopoulos, Matt Kusner, Marc Peter Deisenroth, Anima Anandkumar, the JOREK Team, MAST Team   +12 more
doaj   +1 more source

Modelling the capacitance of the elongated plasma in tokamak. [PDF]

Sci Rep, 2023
Miao P, Li G, Zhang S, Weng Z, Wu Y, Duan Z.   +5 more
europepmc   +1 more source

Evolution of energy confinement physics and most probable compact ignition test device in magnetic fusion

AAPPS Bulletin
The variation of edge confinement modes such as L-mode, H-mode, QH-mode, and I-mode and transitions between these modes in toroidal devices is attributed to interplay between turbulent inflow plasmas from divertor and outflow plasmas from the edge in ...
Hyeon K. Park
doaj   +1 more source

Experiments on a tokamak device with force‐balanced coils

Electrical Engineering in Japan, 1998
Junji Kondoh, Kansuke Fujii, Yasuhiro Komatsu, Akira Sato, Shunji Tsuji-Iio, Ryuichi Shimada   +5 more
openaire   +2 more sources

Studies of RF sheaths and diagnostics on IShTAR [PDF]

, 2015
Crombe, K., Devaux, S., D’Inca, R., Faudot, E., Faugel, H., Fischer, F., Fünfgelder, H., Heuraux, S., Jacquot, J., Louche, F., Moritz, J., Noterdaeme, J., Ochoukov, R., Siegl, G., Tripsky, M., Van Eester, D., Wauters, T.   +16 more
core   +1 more source

The tilted-coil concept for advanced tokamak devices

, 2015
The implications of the adoption of a tokamak’s toroidal field coil characterized by tilting in the azimuthal direction are investigated. The major advantage introduced by tilted coils is that of a drastic reduction over most of the coil section of the electromagnetic forces.
Bombarda, Francesca, GATTO, RENATO
openaire   +1 more source

Accessing the density-free regime with ECRH-assisted ohmic start-up on EAST. [PDF]

Sci Adv
Liu J, Zhu P, Escande DF, Liu W, Xue S, Lin X, Tang P, Wang L, Yan N, Yang J, Duan Y, Jia K, Wu Z, Cheng Y, Zhang L, Qian J, Ding R, Zhou R, EAST team.   +18 more
europepmc   +1 more source