Results 101 to 110 of about 305,568 (222)

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

First physics results from the MAST Mega-Amp Spherical Tokamak

, 2001
First physics results are presented from MAST (Mega-Amp Spherical Tokamak), one of the new generation of purpose built spherical tokamaks (STs) now commencing operation.
Roach, C., MAST Team, Walsh, M. J., Martin, R., Shevchenko, V., Akers, R., Fielding, S. J., Wilson, H. R., Valovic, M., Sykes, A., Ahn, J. W., Price, M., Gryaznevich, M., Arends, E., Counsell, G. F., Carolan, P. G., Tournianski, M.   +16 more
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Optimising TGLF for a Q=10 Burning Spherical Tokamak [PDF]

, 2019
TGLF transport model predictions have been assessed in the vicinity of a theoretical high β burning plasma spherical tokamak at Q=10. Linear micro-stability calculations from TGLF have been compared on a surface at mid-radius with the gyrokinetic code ...
Wilson, Howard Read, Patel, Bhavin, Staebler, Gary, Dickinson, David, Koechl, F., Roach, Colin   +5 more
core   +2 more sources

Electron cyclotron current start-up using a retarding electric field in the QUEST spherical tokamak

Nuclear Fusion
The plasma current start-up experiment is conducted through electron cyclotron (EC) heating in the QUEST spherical tokamak. During the EC heating, the application of a toroidal electric field in the opposite direction to the plasma current effectively ...
T. Onchi, H. Idei, K. Hanada, O. Watanabe, R. Miyata, Y. Zhang, Y. Koide, Y. Otsuka, T. Yamaguchi, A. Higashijima, T. Nagata, I. Sekiya, S. Shimabukuro, I. Niiya, K. Kono, F. Zennifa, K. Nakamura, R. Ikezoe, M. Hasegawa, K. Kuroda, Y. Nagashima, T. Ido, T. Kariya, A. Ejiri, S. Murakami, A. Fukuyama, Y. Kosuga   +26 more
doaj   +1 more source

FAIR-MAST: A fusion device data management system

SoftwareX
We are introducing FAIR-MAST, a data management system designed for historical diagnostic data from the Mega Ampere Spherical Tokamak (MAST) fusion experiments.
Samuel Jackson, Saiful Khan, Nathan Cummings, James Hodson, Shaun de Witt, Stanislas Pamela, Rob Akers, Jeyan Thiyagalingam   +7 more
doaj   +1 more source

Development of FPGA controlled diagnostics on the MAST fusion reactor [PDF]

, 2013
Field Programmable Gate Array technology (FPGA) is very useful for implementing high performance digital signal processing algorithms, data acquisition and real-time control on nuclear fusion devices.
HUANG, BILLY,KIAT
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Plasma self-driven current in tokamaks with magnetic islands

Nuclear Fusion
Magnetic island perturbations may cause a reduction in plasma self-driven current that is needed for tokamak operation. A novel effect on tokamak self-driven current revealed by global gyrokinetic simulations is due to magnetic-island-induced 3D electric
W.X. Wang, M.G. Yoo, E.A. Startsev, S. Kaye, S. Ethier, J. Chen   +5 more
doaj   +1 more source

Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR)

ORCID　0000-0001-8887-7541A concept for a Steady-state Superconducting Advanced Spherical Tokamak Reactor (SASTR) with a slim-CS is proposed. This is a spherical tokamak (ST) with an internal transport barrier (ITB) and superconducting magnets.
NAGAYAMA, Yoshio, FUJITA, Takaaki
core   +1 more source

Thermal energy confinement time of spherical tokamak plasmas in PI3

Nuclear Fusion
The Plasma Injector 3 (PI3) experiment at general fusion has been constructed to demonstrate the ability to form plasma targets suitable for compression in a Magnetized Target Fusion machine.
A. Tancetti, C. Ribeiro, S.J. Howard, S. Coop, C.P. McNally, M. Reynolds, P. Kholodov, F. Braglia, R. Zindler, C. Macdonald, E. Love, P. Carle, X. Feng, A. Rohollahi, K. Leci, D. Plant, C. Dunlea, R. Ivanov, A. Mossman   +18 more
doaj   +1 more source

SOLPS-ITER simulations to study the impact of aspect ratio on edge fueling neutrals in tokamaks

Nuclear Materials and Energy
In this paper, we examine the role of the aspect ratio on the neutral penetration and poloidal distribution for fixed magnetic geometry and plasma profiles using SOLPS-ITER. We start from an H-mode discharge from MAST (Kirk et al., 2012), with its aspect
Yi-Cheng Chuang, Saskia Mordijck, Richard Fitzpatrick, Richard Reksoatmodjo   +3 more
doaj   +1 more source