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Tokamak: A device for nuclear fusion

Indian Journal of Cryogenics, 2016
Tokamak is a plasma confinement device, which uses a combination of magnetic fields to confine hot plasma. Tokamak research has made rapid progress in terms of plasma confinement parameters and temperatures and it is a strong candidate for magnetic confinement based Nuclear Fusion Reactor.
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Thermal Spray Coating of Tungsten for Tokamak Device

Plasma Science and Technology, 2006
Thermal spray, such as direct current (d.c.) plasma spray or radio frequency induced plasma spray, was used to deposit tungsten coatings on the copper electrodes of a tokamak device. The tungsten coating on the outer surface of one copper electrode was formed directly through d.c. plasma spraying of fine tungsten powder.
Jiang Xianliang, F Gitzhofer, M I Boulos
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Multiple view fan beam polarimetry on Tokamak devices

Review of Scientific Instruments, 1997
A polarimeter diagnostic is under development which utilizes several fan beams to accumulate line integrated Faraday rotation data in a Tokamak plasma. The utilization of a fan beam configuration over that of conventional vertical view polarimeter systems significantly reduces access requirements.
W. R. Geck   +2 more
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The Alignment and Assembly for EAST Tokamak Device

Plasma Science and Technology, 2005
EAST (HT-7U) is a large fusion experimental device. It is a full superconducting tokamak with 1 MA of plasma current, 1000 s of plasma duration, high elongation and triangularity. It mainly consists of superconducting magnets of poloidal and toroidal field (PF & TF), vacuum vessel (VV), thermal radiation shield (TRS) and cryostat vessel (CV).
Chen Wenge   +5 more
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Cyclic tokamak operation in the WT-2 device

Nuclear Fusion, 1987
Cyclic tokamak operation has been demonstrated in the WT-2 device. The plasma current is driven alternately by lower hybrid (LH) waves and by the inductive field E||, while the loop voltage of the transformer has negative and positive values successively. The effects of an opposite electric field on LH current drive are studied.
M. Nakamura   +10 more
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THERMONUCLEAR FUTURE OF THE TOKAMAK MAGNETIC CONFINEMENT DEVICE.

Nuclear Fusion, 1969
A possible extrapolation of the Tokamak principle towards a thermonuclear reactor raises many problems among which stress is laid on the minimum values required for the equilibrium and stability parameters. Some technological requirements are confronted with the most recent theoretical developments, revealing the existence of a small domain inside of ...
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Improvement of plasma identification in tokamak devices with dynamical information

IEEE Transactions on Magnetics, 2000
Fast and reliable identification of plasma parameters in tokamak reactors is an issue of primary importance for the effectiveness of plasma position control action. A number of different measurement techniques are available, but the magnetic ones play the major role.
FORMISANO, Alessandro   +3 more
openaire   +3 more sources

A model for plasma discharges simulation in Tokamak devices

AIP Conference Proceedings, 2001
In this work, a “zero-dimensional” model for simulation of discharges in Tokamak machine is presented. The model allows the calculation of the time profiles of important parameters of the discharge. The model was applied to the TCABR Tokamak to study the influence of parameters and physical processes during the discharges.
Antonio M. M. Fonseca   +5 more
openaire   +1 more source

Reduced fusion-neutron production in non-axisymmetric tokamak devices

Nuclear Fusion, 1978
In tokamak plasmas subjected to substantial toroidal-field ripple, sufficiently energetic members of the bulk-ion population can diffuse rapidly away from the hot central region by the superbanana process. The ion velocity distribution is truncated at the velocity above which the escaping fast ions cannot be replaced sufficiently rapidly by Coulomb ...
D.L. Jassby, H.H. Towner, R.J. Goldston
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