A review of lithium application for the plasma-facing material in EAST Tokamak

JS Hu, L Li, GZ Zuo, Z Sun, W Xu, XC Meng… - Reviews of Modern …, 2023 - Springer
As a low-Z material, lithium is widely tested and used in tokamak devices for particle
recycling and impurity control to improve plasma performance. Lithium application as …

[HTML][HTML] Fuel recycling control in long pulse operation with full tungsten divertors in EAST tokamak

Y Yu, D Zhou, M Sakamoto, B Cao, G Zuo… - Nuclear Materials and …, 2023 - Elsevier
Fuel recycling control in long pulse discharges is studied in EAST tokamak with tungsten
divertors by particle balance. Double null configuration, proper Resonant Magnetic …

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 …

[HTML][HTML] Tungsten erosion and divertor leakage from the DIII-D SAS-VW tungsten-coated divertor in experiments with neon gas seeding

MS Parsons, JD Mateja, SH Messer, T Abrams… - Nuclear Materials and …, 2023 - Elsevier
Collector probes have been used to examine tungsten divertor leakage in a variety of
scenarios with low-Z impurity seeding during operation with the new tungsten-coated SAS …

Mitigation of plasma–wall interactions with low-Z powders in DIII-D high confinement plasmas

F Effenberg, A Bortolon, L Casali, R Nazikian… - Nuclear …, 2022 - iopscience.iop.org
Experiments with low-Z powder injection in DIII-D high confinement discharges
demonstrated increased divertor dissipation and detachment while maintaining good core …

Comparison of active impurity control between lithium and boron powder real-time injection in EAST

W Xu, JS Hu, Z Sun, R Maingi, GZ Zuo, YZ Qian… - Physica …, 2021 - iopscience.iop.org
The lithium and boron powder have been successfully real-time injected into Experimental
Advanced Superconducting Tokamak (EAST) high-confinement (H−) mode discharges …

Liquid lithium as divertor material to mitigate severe damage of nearby components during plasma transients

V Sizyuk, A Hassanein - Scientific Reports, 2022 - nature.com
The successful operation of thermonuclear fusion reactors such as ITER, DEMO, and future
commercial plants is mainly determined by the optimum choice of materials for various …

Effect of lithium on the atmospheric corrosion characteristics of TZM as the first-wall material in EAST

W Zheng, R Yan, G Zuo, L Mu, N Liu, X Meng… - Journal of Nuclear …, 2024 - Elsevier
Abstract The effect of Lithium (Li) coating on the corrosion behavior of molybdenum-titanium-
zirconium (TZM) alloy was investigated in low-and high-humidity air at room temperature …

Impacts of recycling impurity on the background ELM behavior during repetitive radiative divertor experiments in EAST

QQ Yang, X Lin, GS Xu, L Zhang, WM Zhang… - Nuclear …, 2023 - iopscience.iop.org
A significant change in the background ELM behavior prior to neon (Ne) seeding has been
observed in a series of repetitive radiative divertor experiments in EAST. With similar …

Design and development of the EAST plug-in cryopump for long-pulse high-performance operation

C Zhang, Z Chen, Q Yang, Y Song, H Zhang, G Wang… - Vacuum, 2024 - Elsevier
At present, the in-vessel cryopump of the EAST divertor demonstrates inadequate pumping
performance during long-pulse high confinement mode (H-mode) plasma operations, and …