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Tokamak edge transport studies using linear plasma devices

open access: yes, 2012
Salmagne, C.   +6 more
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Electron Temperature Measurement on the QUEST Spherical Tokamak Device

open access: yesElectron Temperature Measurement on the QUEST Spherical Tokamak Device
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Real-time systems in tokamak devices. A case study: The JET tokamak

2010 17th IEEE-NPSS Real Time Conference, 2010
The achievement of the required performances during the operation of large fusion experimental reactors, is strictly related to the flexibility and reliability of the real-time infrastructures. It turns out that, in tokamak reactors, the real-time infrastructure has to be designed so as to meet a number of common requirements.
DE TOMMASI, GIANMARIA   +10 more
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Axisymmetric control of large tokamak devices

Journal of Plasma Physics, 1984
The problem of controlling the position and cross-sectional shape of plasmas is addressed for circumstances relevant to large tokamaks. A principle for, as well as a practical method of analysis of, this control problem is presented. The relevant elements of the tokamak system included in the analysis are the plasma, a resistive wall (vacuum chamber ...
T. H. Jensen, F. W. McClain
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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   +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   +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   +3 more
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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   +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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