Results 91 to 100 of about 6,012 (210)

Full orbit simulations of collisional impurity transport in spherical tokamak plasmas with strongly-sheared electric fields

open access: yes, 2011
The collisional dynamics of test impurity ions in spherical tokamak plasmas with strongly-sheared radial electric fields is investigated by means of a test particle full orbit simulation code.
McClements, K. G.   +2 more
core  

Energetic particles in spherical tokamak plasmas

open access: yesPlasma Physics and Controlled Fusion, 2017
Spherical tokamaks (STs) typically have lower magnetic fields than conventional tokamaks, but similar mass densities. Suprathermal ions with relatively modest energies, in particular beam-injected ions, consequently have speeds close to or exceeding the Alfven velocity, and can therefore excite a range of Alfvenic instabilities which could be driven by
K G McClements, E D Fredrickson
openaire   +2 more sources

Overview of recent results from the ST40 compact high-field spherical tokamak

open access: yesNuclear Fusion
ST40 is a compact, high-field ( $B_{\mathrm{T0}}\unicode{x2A7D} 2.1\,\,\,\textrm{T}$ ) spherical tokamak (ST) with a mission to expand the physics and technology basis for the ST route to commercial fusion.
S.A.M. McNamara   +71 more
doaj   +1 more source

The impact of E × B shear on microtearing based transport in spherical tokamaks

open access: yesNuclear Fusion
Electromagnetic microtearing modes (MTMs) have been observed in many different spherical tokamak (ST) regimes. Understanding how these and other electromagnetic modes nonlinearly saturate is likely critical in understanding the confinement of a high β ST.
B.S. Patel   +5 more
doaj   +1 more source

Development of the Langmuir probe under q-distribution for NCST

open access: yesAIP Advances
The Langmuir probe is one of the important diagnostic methods for measuring the edge plasma parameters of tokamak. A quadruple Langmuir probe (QLP) system was designed and built on the NanChang Spherical tokamak (NCST).
Donghua Xiao   +4 more
doaj   +1 more source

Boundary plasma studies for a spherical tokamak with lithium walls

open access: yesNuclear 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   +9 more
doaj   +1 more source

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

open access: yesNuclear 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   +22 more
doaj   +1 more source

Testing of the SOLPS-ITER code at Globus-M2 spherical tokamak with detached divertor

open access: yesMATEC Web of Conferences, 2018
In according to a present understanding of Scrape-Off Layer (SOL) physics, future thermonuclear devices like ITER, DEMO and beyond, require high radiation regimes in order to reduce heat loads on tokamak divertor. Recent experiments at ASDEX Upgrade, JET
Sorokina Daria   +3 more
doaj   +1 more source

FLIPEC, an ideal MHD free-boundary axisymmetric equilibrium solver in the presence of macroscopic flows

open access: yesNuclear 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   +4 more
doaj   +1 more source

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

open access: yesNuclear 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   +26 more
doaj   +1 more source

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