One of the key challenges for future fusion research is to mitigate the high steady-state heat
load on the divertor target plates, and divertor detachment offers a promising solution. The …

A total power injection up to 0.3 GJ has been achieved in EAST long pulse H-mode
operation of 101.2 s with an ITER-like water-cooled tungsten (W) mono-block divertor, which …

Active control of the excessively high heat and particle fluxes on the divertor target plates is
of fundamental importance to the steady state operation of tokamaks, especially for fusion …

A multi-function divertor feedback control system has been built on Experimental Advanced
Superconducting Tokamak (EAST) to treat the divertor heat load issue. With the real-time …

Small perturbations and strong impurity exhaust capability associated with the small grassy
ELMs render the grassy-ELM regime a suitable candidate for achieving steady-state H …

Abstract EAST achieved 101.2 seconds H-mode discharge with total power injection up to
3MW in 2017. Consequently to the enhanced auxiliary heating power, the active divertor …

The detached divertor has recently been achieved in H-mode plasmas in EAST with an ITER-
like tungsten divertor, which is essential for high power long pulse operation in the near …

A new lower tungsten divertor has been developed and installed in the EAST
superconducting tokamak to replace the previous graphite divertor with power handling …

Detachment in helium (He) discharges has been achieved in the EAST superconducting
tokamak equipped with an ITER-like tungsten divertor. This paper presents the experimental …

EAST implements the double feedback control experiments of the detachment by using two
control systems at the same time to explore the new detachment control way. We hire two …