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The Alignment and Assembly for EAST Tokamak Device
Plasma Science and Technology, 2005EAST (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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Comparison between EAST and ITER tokamak
Theoretical and Natural ScienceThis paper provides an overview of nuclear fusion, which is considered as an ideal energy source for the future, with emphasis on its theoretical foundation and tokamak device. In nuclear fusion, the mass of products is always less than the mass of reactants, and this mass defect is converted into enormous released energy.
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Sustained high β N plasmas on EAST tokamak
Physics Letters A, 2018Abstract Sustained high normalized beta ( β N ∼ 1.9 ) plasmas with an ITER-like tungsten divertor have been achieved on EAST tokamak recently. The high power NBI heating system of 4.8 MW and the 4.6 GHz lower hybrid wave of 1 MW were developed and applied to produce edge and internal transport barriers in high β N discharges.
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Experimental study of pedestal turbulence on EAST tokamak
Nuclear Fusion, 2015Turbulence in the pedestal region of the EAST tokamak has been observed and studied using reflectometry. In lower hybrid wave (LHW) or neutral beam injection (NBI) dominated heating plasma, a coherent mode (CM) was usually observed in the ELM-free phase just after the L-H transition.
X. Gao +9 more
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Applications of Visible Imaging Diagnostics on EAST Tokamak
Journal of Fusion Energy, 2015Three visible imaging diagnostic systems have been installed on EAST tokamak for several different diagnostic purposes. One is a high-speed camera system that can be operated to study edge plasma phenomena with a maximum recording speed of 16 kfps and a minimum exposure time of 1 µs.
Qiang Wang +4 more
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A digital long pulse integrator for EAST Tokamak
Fusion Engineering and Design, 2014Abstract 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
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Real Time Equilibrium Reconstruction Algorithm in EAST Tokamak
Plasma Science and Technology, 2004The EAST (HT-7U) superconducting tokamak is a national project of China on fusion research, with a capability of long-pulse (~ 1000 s) operation. In order to realize a long-duration steady-state operation of EAST, some significant capability of real-time control is required.
Wang Huazhong +2 more
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Filterscope diagnostic system on the Experimental Advanced Superconducting Tokamak (EAST)
Review of Scientific Instruments, 2016A filterscope diagnostic system has been mounted to observe the line emission and visible bremsstrahlung emission from plasma on the experimental advanced superconducting tokamak during the 2014 campaign. By this diagnostic system, multiple wavelengths including Dα (656.1 nm), Dγ (433.9 nm), He ii (468.5 nm), Li i (670.8 nm), Li ii (548.3 nm), C iii ...
Z. Xu +13 more
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Plasma-facing components damage and its effects on plasma performance in EAST tokamak
Fusion Engineering and Design, 2020Rui Ding, Ling Zhang, Baoguo Wang
exaly