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Published on 15 November 2017

EAST tokamak in ASIPP is designed on the basis of the latest tokamak achievements of the last century. Its mission is to conduct fundamental physics and engineering researches on advanced tokamak fusion reactors with a steady, safe and high performance, to provide a scientific base for experimental reactor design and construction, and to promote the development of plasma physics and related disciplines and technologies. EAST has three distinct features: non-circular cross-section, fully superconducting magnets and fully actively water cooled plasma facing components (PFCs) which will be beneficial to explore the advanced steady-state plasma operation modes.

EAST construction and physics research will provide direct experience for the construction of ITER. Compared with ITER, although smaller, EAST is similar to ITER in shape and equilibrium, yet more flexible. During the 10 years for ITER construction, EAST will be one of a few international devices that can be an important experimental test bench for conducting ITER related steady-state advanced plasma science and technology research.

Achievements have been made on EAST experiments: obtainment of repeatable plasma current of 1MA, the highest parameter on all existing superconducting devices, realizing and long-pulse diverted plasma discharges of 0.25MA and 100s duration under the central electron temperature of 15 million degrees. This is the longest diverted plasma discharge in the world up to now. Through the further optimization of the operation, H-mode plasma discharge reaches 6.4s, with the duration more than 60 times of energy confinement time, realizing quasi-steady state. Progress has also been made on the study of plasma spontaneous rotation experiment and mechanism research of L-H mode conversion.