Results 141 to 150 of about 601 (182)

First plasma experiment on spherical tokamak device UTST

Electrical Engineering in Japan, 2009
AbstractThe UTST (University of Tokyo Spherical Tokamak) device was constructed for the purpose of exploring the formation of ultrahigh‐beta ST (spherical tokamak) plasma using the double null plasma merging method. When two plasmas merge together to form a single plasma, magnetic field lines reconnect, and magnetic field energy is converted to plasma ...
Ryota Imazawa, Makoto Nakagawa, Shuji Kamio, Ryuma Hihara, Takuma Yamada, Michiaki Inomoto, Yuichi Takase, Yasushi Ono   +7 more
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Analysis of error field sources in TOKAMAK devices

International Journal of Applied Electromagnetics and Mechanics, 2012
Due to unavoidable tolerances in components construction and assembly, the actual magnetic field in Tokamak devices differs from the nominal one. The experimental studies nowadays available indicate a strong impact of the error fields on the plasma stability in next generation, large size, devices.
BONITO OLIVA A, PORTONE A, TESTONI P, FORMISANO, Alessandro, MARTONE, Raffaele   +4 more
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The role of tokamak ignition device options

Journal of Fusion Energy, 1985
The U.S. Dept. of Energy discusses the Tokamak Fusion Core Experiment Design Study Program. The options that were considered were based on the D-shaped tokamak configuration, which included versions with copper magnets, superconducting magnets, and varied in degrees of risk both in the physics and the technology. The Plasma Physics Laboratory addresses
N. Anne Davies, Paul Rutherford, Daniel R. Cohn, Carl D. Henning   +3 more
openaire   +1 more source

Design of the HT-7U tokamak device

18th IEEE/NPSS Symposium on Fusion Engineering. Symposium Proceedings (Cat. No.99CH37050), 2003
The HT-7U superconducting tokamak is an advanced steady-state plasma physics experimental device to be built at the Institute of Plasma Physics, the Chinese Academy of Sciences (ASIPP). HT-7U have a long pulse (60-1000 s) capability, a flexible PF system, and auxiliary heating and current drive systems, and will be able to accommodate divertor heat ...
S.T. Wu, W.Y. Wu, D.M. Yao, Z.M. Chen, Y.F. Bi, Y.N. Pan, B.Z. Li, Z.Y. Liao, J. Yu, Y.X. He, Y.T. Song, W.G. Chen, X.B. Wu, D.J. Gao, A.H. Ji, W.J. Pan, D. Wu, Y.L. Chao   +17 more
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Current density measurements in Tokamak devices

Plasma Physics and Controlled Fusion, 1992
Tokamak plasmas are, at present, the most studied objects in controlled thermonuclear fusion research. The basic concept of these devices relies on externally induced currents which serve the twofold purpose of heating the plasma and creating an appropriate magnetic field structure for confinement.
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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
openaire   +1 more source

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, C. W. Domier, N. C. Luhmann, Jr.   +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, Wu Songtao, Wei Jing, Wu Weiyue, Gao Daming, Weng Peide   +5 more
openaire   +1 more source

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, K. Ogura, A. Ando, H. Tanaka, M. Iida, S. Ide, K. Oho, S. Ozaki, T. Maekawa, Y. Terumichi, S. Tanaka   +10 more
openaire   +1 more source