Recent progress in Chinese fusion research based on superconducting tokamak configuration

J Zheng, J Qin, K Lu, M Xu, X Duan, G Xu, J Hu… - The innovation, 2022 - cell.com
Fusion energy is a promising source of clean energy, which could solve energy shortages
and environmental pollution. Research into controlled fusion energy has been ongoing for …

Divertor plasma behaviors with neon seeding at different locations on EAST with ITER-like divertor

LY Meng, L Wang, HQ Wang, GZ Deng, H Si… - Nuclear …, 2022 - iopscience.iop.org
For the problem of excessively high divertor heat flux, active impurity seeding is an effective
method to radiate the plasma energy reaching the divertor and thus achieve the divertor …

Development of Langmuir probe array for the new lower tungsten divertor in EAST

LY Meng, JC Xu, JB Liu, L Cao, P Wang, A Li… - Fusion Engineering and …, 2022 - Elsevier
Abstract The divertor Langmuir probes (Div-LPs) system is a key diagnostic, which is widely
used in advanced tokamaks including ITER, for divertor plasma measurement. With the …

Simulation study of the influence of E× B drift on tungsten impurity transport in the scrape-off layer

J Guo, Y Xu, S Mao, M Ye - Nuclear Fusion, 2023 - iopscience.iop.org
Tungsten (W) is used as the plasma-facing material in the divertor region of future fusion
reactors, such as ITER; however, its concentration in the core plasma must be maintained at …

Effects of strike point location on the divertor particle and energy flux decay widths on EAST by experiment and SOLPS modeling

C Zhang, C Sang, Y Tao, G Jia, L Meng, L Wang… - Nuclear …, 2023 - iopscience.iop.org
The new lower tungsten divertor of EAST uses a right-angle shape consisted by horizontal
and vertical targets, which has the capacity of increasing the divertor closure. The strike …

First observation of edge impurity behavior with n= 1 RMP application in EAST L-mode plasma

W Zhang, L Zhang, Y Cheng, S Morita, H Sheng… - Nuclear …, 2024 - iopscience.iop.org
High-Z impurity accumulation suppression and mitigation in core plasma is frequently
observed in EAST edge localized mode mitigation experiments by using resonant magnetic …

Conceptual design of CFETR divertor dome for remote handling

X Zhang, L Yin, T Xu, N Mou… - IEEE Transactions on …, 2022 - ieeexplore.ieee.org
The design of the China Fusion Engineering Test Reactor (CFETR) device is one of the
main tasks in the next stage of research on fusion energy in China. The CFETR divertor is a …

[HTML][HTML] Investigation of particle exhaust from EAST divertor

B Cao, L Wang, YW Yu, GZ Zuo, JS Hu - Nuclear Materials and Energy, 2022 - Elsevier
Particle control is one of the key issues for steady-state tokamak operation. The density
decay time is used to evaluate the capability of the divertor to exhaust particle with all fueling …

Progress, Load Study, and Structural Analysis of the CFETR Divertor Dome

X Zhang, Y Wang, C Zhong, L Yin… - IEEE Transactions on …, 2024 - ieeexplore.ieee.org
China Fusion Engineering Test Reactor (CFETR) is an experimental device of magnetic
confinement tokamak fusion reactor that is being designed and developed in China, and the …

[HTML][HTML] Study on ELM burn-through induced by small ELMs with divertor detachment in EAST

N Ding, QQ Yang, L Wang, GS Xu, LY Meng, KD Li… - Physics Letters A, 2023 - Elsevier
In the H-mode radiative divertor experiments, the transient heat flux induced by edge
localized modes (ELMs) could cause the detached divertor plasma to re-attach in a few …