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First Engineering Commissioning of EAST Tokamak

Plasma Science and Technology, 2006
Experimental Advanced Superconducting Tokamak (EAST) is the first fully superconducting tokamak. The first commissioning started on Feb. 1st of 2006 and finished on March 30th of 2006 at the Institute of Plasma Physics, Chinese Academy of Sciences. It consists of leakage testing at both room temperature and low temperature, pumping down, cooling down ...
Wan Yuanxi   +3 more
openaire   +1 more source

Design and application of GDC on EAST Tokamak

Fusion Engineering and Design, 2011
On EAST Tokamak, DC glow discharge (GDC) is developed to clean the first wall of plasma. It can effectively control the recycling of H, C, O impurities and improve the wall conditions. There are four GDCs which distribute equally on the EAST Tokamak vacuum vessel wall.
Zibo Zhou, Yuntao Song, Jiansheng Hu
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Modelling of First Discharge in EAST Tokamak

Plasma Science and Technology, 2008
An 1.5D equilibrium evolution code was used to model the time evolution of the first ohmic discharges in the EAST experiment. Good agreement between the simulation and the experimental results was obtained in the plasma current, major radius, electron temperature, loop voltage and poloidal field (PF) current for the entire duration of the discharge ...
Liu Chengyue   +3 more
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Equilibrium properties on the EAST superconducting tokamak

Journal of Plasma Physics, 2009
AbstractThe Experimental Advanced Superconducting Tokamak (EAST) has a major radius of R0 = 1.75 m and a midplane halfwidth of 0.5 m. It has been operated with a toroidal magnetic field B0 = 2 T and Ip ≤ 500 kA. The evolution of the plasma equilibrium is analysed between discharges by Equilibrium Fitting Code (EFIT).
J. P. QIAN   +10 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
openaire   +1 more source

Kinetic equilibrium reconstruction on EAST tokamak

Plasma Physics and Controlled Fusion, 2013
Plasma equilibrium is an important basis for tokamak plasma research. The equilibrium reconstructed from experimental diagnostics is a key element for experiments analysis and for theory study. The kinetic equilibrium has the profiles information (current or safety factor profile, kinetic pressure profile), which are key issues for some studies of ...
G Q Li   +8 more
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Pellet injectors for EAST and KSTAR tokamaks

Fusion Engineering and Design, 2017
Abstract The paper presents high frequency pellet injectors developed for edge localized mode mitigation and plasma fuelling of the EAST and KSTAR tokamaks. Each pellet injector is able to inject solid deuterium or hydrogen pellets at steady state mode.
Igor Vinyar   +8 more
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Observation of a strange MHD phenomenon on EAST tokamak

Physics Letters A, 2010
A strange magnetohydrodynamic (MHD) phenomenon has been observed on EAST tokamak. The waveform of the MHD oscillations is similar to that of fishbone mode. The observation and analyzing results suggest that the appearance of the strange oscillations is associated with intensive impurity radiation.
Kaiyun Chen   +4 more
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The magnetic field configuration measurement on EAST tokamak

Fusion Engineering and Design, 2009
Abstract The magnetic field configurations of poloidal field (PF) and toloidal field (TF) are the base of tokamak plasma operation. They are determined by the parameters such as positions and structures of PF and TF coils. Parameters of TF and PF coils of a new fully superconducting tokamak with non-circular cross-section EAST will change when the ...
B. Shen   +4 more
openaire   +1 more source

A digital long pulse integrator for EAST Tokamak

Fusion Engineering and Design, 2014
Abstract A digital integrator has been developed to be compatible with the long pulse plasma discharges on the Experimental Advanced Superconductor Tokamak (EAST), in which the induced signal is modulated by a chopper, and a field programmable gate array (FPGA) in the 16-bit digitizer is used to realize the digital integration in real time.
Y. Wang   +6 more
openaire   +1 more source

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