Results 91 to 100 of about 5,989 (213)

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

FAIR-MAST: A fusion device data management system

open access: yesSoftwareX
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   +7 more
doaj   +1 more source

Comparative evaluation of solar, fission, fusion, and fossil energy resources, part 3 [PDF]

open access: yes
The role of nuclear fission reactors in becoming an important power source in the world is discussed. The supply of fissile nuclear fuel will be severely depleted by the year 2000. With breeder reactors the world supply of uranium could last thousands of
Clement, J. D., Reupke, W. A.
core   +1 more source

Plasma self-driven current in tokamaks with magnetic islands

open access: yesNuclear 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   +5 more
doaj   +1 more source

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

open access: yesNuclear 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   +3 more
doaj   +1 more source

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