Advances in plasma–wall interaction control for H-mode operation over 100 s with ITER-like tungsten divertor on EAST

L Wang, HY Guo, F Ding, YW Yu, QP Yuan… - Nuclear …, 2019 - iopscience.iop.org
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 …

Advances in the long-pulse steady-state high beta H-mode scenario with active controls of divertor heat and particle fluxes in EAST

BN Wan, XZ Gong, Y Liang, N Xiang, GS Xu… - Nuclear …, 2022 - iopscience.iop.org
Since the last IAEA-Fusion Energy Conference, the Experimental Advanced
Superconducting Tokamak (EAST) research program has been, in support of ITER and …

Divertor impurity seeding with a new feedback control scheme for maintaining good core confinement in grassy-ELM H-mode regime with tungsten monoblock divertor …

GS Xu, QP Yuan, KD Li, L Wang, JC Xu… - Nuclear …, 2020 - iopscience.iop.org
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 …

Physics design of new lower tungsten divertor for long-pulse high-power operations in EAST

GS Xu, L Wang, DM Yao, GZ Jia, CF Sang… - Nuclear …, 2021 - iopscience.iop.org
A new lower tungsten divertor has been developed and installed in the EAST
superconducting tokamak to replace the previous graphite divertor with power handling …

EAST steady-state long pulse H-mode with core-edge integration for CFETR

XZ Gong, AM Garofalo, J Huang, JP Qian… - Nuclear …, 2022 - iopscience.iop.org
A recent EAST experiment has successfully demonstrated long pulse steady-state high
plasma performance scenario and core-edge integration since the last IAEA in 2018. A …

Progress of divertor heat and particle flux control in EAST for advanced steady-state operation in the last 10 years

L Wang, GS Xu, JS Hu, KD Li, QP Yuan, JB Liu… - Journal of fusion …, 2021 - Springer
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 …

Joint DIII-D/EAST research on the development of a high poloidal beta scenario for the steady state missions of ITER and CFETR

AM Garofalo, XZ Gong, SY Ding, J Huang… - Plasma Physics and …, 2017 - iopscience.iop.org
Experimental and modeling investigations on the DIII-D and EAST tokamaks show the
attractive transport and stability properties of fully noninductive, high poloidal-beta (β P) …

Divertor detachment and asymmetry in H-mode operation with an ITER-like tungsten divertor in EAST

JB Liu, L Wang, HY Guo, HQ Wang, GS Xu… - Nuclear …, 2019 - iopscience.iop.org
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 …

The first implementation of active detachment feedback control in EAST PCS

QP Yuan, K Wu, L Wang, JC Xu, KD Li, JB Liu… - Fusion Engineering and …, 2020 - Elsevier
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 …

Integrated simulations of H-mode operation in ITER including core fuelling, divertor detachment and ELM control

AR Polevoi, A Loarte, R Dux, T Eich, E Fable… - Nuclear …, 2018 - iopscience.iop.org
ELM mitigation to avoid melting of the tungsten (W) divertor is one of the main factors
affecting plasma fuelling and detachment control at full current for high Q operation in ITER …