Results 171 to 180 of about 2,212,062 (221)
Some of the next articles are maybe not open access.

Status of ECRH Project on EAST Tokamak

AIP Conference Proceedings, 2014
A 140GHz electron cyclotron resonance heating and current drive (EC H&CD) project for EAST Tokamak is launched in 2011 with a total power of 4MW and pulse length of 100 s. The main objectives of the system are to provide central H&CD, assist start-up and control of MHD activities.
Handong Xu, Weiye Xu, fukun Liu
exaly   +2 more sources

MIMO Shape Control at the EAST Tokamak: Simulations and Experiments

open access: yesFusion Engineering and Design, 2019
During 2016-2018 experimental campaigns, the plasma magnetic control architecture of the EAST tokamak was revised in order to achieve improved performances, with the final aim of feedback control of alternative divertor configurations (i.e. with multiple
Bingjia Xiao   +2 more
exaly   +2 more sources

Thermal analysis of the EAST tokamak

Fusion Engineering and Design, 2021
Abstract The superconducting magnet of the Experimental Advanced Superconducting Tokamak (EAST) will experience large steady-state and transient heat loads during operation, which is undoubtedly a major challenge for the cryogenic cooling system. The steady-state heat loads are mainly composed of the thermal conduction from the support structure and ...
Ming Zhang   +4 more
openaire   +1 more source

Model-Based MIMO Isoflux Plasma Shape Control at the EAST Tokamak: Experimental Results

open access: yes, 2020
This paper reports on the experimental validation of a MIMO plasma shape controller at the EAST tokamak, carried out during the 2019-2020 experimental campaign. In particular the decoupled SISO controller that is routinely used during operations at EAST,
Roberto Ambrosino   +2 more
exaly   +2 more sources

The stability margin on EAST tokamak

Chinese Physics B, 2009
The experimental advanced superconducting tokamak (EAST) is the first full superconducting tokamak with a D-shaped cross-sectional plasma presently in operation. Its poloidal coils are relatively far from the plasma due to the necessary thermal isolation from the superconducting magnets, which leads to relatively weaker coupling between plasma and ...
Qian Jin-Ping   +5 more
openaire   +1 more source

Equilibrium Reconstruction in EAST Tokamak

Plasma Science and Technology, 2009
Reconstruction of experimental axisymmetric equilibria is an important part of tokamak data analysis. Fourier expansion is applied to reconstruct the vessel current distribution in EFIT code. Benchmarking and testing calculations are performed to evaluate and validate this algorithm.
Qian Jinping   +10 more
openaire   +1 more source

Application of MDSplus on EAST Tokamak

Plasma Science and Technology, 2007
EAST is a fully superconducting Tokamak in China used for controlled fusion research. MDSplus, a special software package for fusion research, has been used successfully as a central repository for analysed data and PCS (Plasma Control System) data since the debugging experiment in the spring of 2006 [1]. In this paper, the reasons for choosing MDSplus
Qu Lianzheng   +4 more
openaire   +1 more source

The Procedure for Assembling the EAST Tokamak

Plasma Science and Technology, 2005
Due to the complicated constitution and high precision requirements of the EAST superconducting tokamak, a meticulous assembling procedure and measurement scheme must be established. The big size and mass of the EAST machine's components and complicated configuration with tight installation tolerances call for a highly careful assembling procedure. The
Wu Songtao, EAST Machine Team
openaire   +1 more source

Runaway Electron Measurements in the EAST Tokamak

Contributions to Plasma Physics, 2010
AbstractAn experimental study of runaway electrons in the EAST tokamak has been performed by a recently developed multi‐channel hard x‐ray diagnostics based on NaI(TL) scintillator detectors. It is found that in the current quench phase, the inductive loop voltage plays an important role in the generation of runaway electrons.
H. W. Lu   +5 more
openaire   +1 more source

Technical diagnosis system for EAST tokamak

Fusion Engineering and Design, 2010
Abstract Technical diagnosis system (TDS) is one of the important subsystems of EAST (experimental advanced superconducting tokamak) device, main function of which is to monitor status parameters in EAST device. Those status parameters include temperature of different positions of main components, resistance of each superconducting (SC) coils, joint ...
Jing Qian   +4 more
openaire   +1 more source

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