Results 71 to 80 of about 345 (184)

Development of electron cyclotron wall conditioning with argon gas in the spherical tokamak QUEST for hydrogen removal from metal walls

Nuclear Fusion
Electron cyclotron wall conditioning with argon gas (Ar-ECWC) has been performed on the normal conducting spherical tokamak QUEST with metal walls for the purpose of applying this technique to future superconducting fusion devices with metal walls as an ...
Masakatsu Fukumoto, Qilin Yue, Pakkapawn Prapan, Kazuaki Hanada, Shinichiro Kojima, Tomohide Nakano, Naoaki Yoshida, Ryuya Ikezoe, Yoshihiko Nagashima, Takeshi Ido, Takumi Onchi, Hiroshi Idei, Takumi Komiyama, Hiroki Iguchi, Taiichi Shikama, Akira Ejiri, Suguru Masuzaki, Mizuki Sakamoto, Yoshio Ueda, Kengoh Kuroda, Kaori Kono, Shun Shimabukuro, Aki Higashijima   +22 more
doaj   +1 more source

Boundary plasma studies for a spherical tokamak with lithium walls

Nuclear Materials and Energy
Boundary plasma and plasma-material interactions are investigated for magnetised target fusion (MTF) applications. The General Fusion magnetised target fusion technology uses coaxial helicity injection (CHI) start-up which forms a spherical tokamak in a ...
A. Antony, L. Carbajal, T.D. Rognlien, M.V. Umansky, A. Froese, S. Howard, C. Ribeiro, R. Ivanov, C. Dunlea, C.P. McNally   +9 more
doaj   +1 more source

Current rearrangement in merging start-up of spherical tokamak plasmas

Nuclear Fusion
Torus plasma merging technique that provides high power ion heating by magnetic reconnection is expected to significantly expand the operation scenarios of spherical tokamak (ST) fusion reactors.
M. Inomoto, Y. Maeda, T. Suzuki, H. Jin, S. Cho, H. Ueo, M. Otsuka, T. Kono, E. Sakuraba, S. Takeda, H. Tanabe, Y. Ono, E. Kawamori, S. Usami, R. Yanai   +14 more
doaj   +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

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

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

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

Observation of a new pedestal stability regime in MAST Upgrade H-mode plasmas

Nuclear Fusion
The first pedestal stability and structure analysis on the new MAST Upgrade (MAST-U) spherical tokamak H-mode plasmas is presented. Our results indicate that MAST-U pedestals are close to the low toroidal mode number ( n ) peeling branch of the peeling ...
K. Imada, T.H. Osborne, S. Saarelma, J.G. Clark, A. Kirk, M. Knolker, R. Scannell, P.B. Snyder, C. Vincent, H.R. Wilson, the MAST Upgrade Team   +10 more
doaj   +1 more source