[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 …

In situ melting phenomena on W plasma-facing components for lower divertor during long-pulse plasma operations in EAST

D Zhu, Z Guo, C Xuan, B Yu, C Li, B Gao, R Ding… - Nuclear …, 2023 - iopscience.iop.org
Tungsten (W) is one of the most promising plasma-facing materials for future fusion devices.
Although its melting point is the highest among all metals, it still has great risk of melting …

The influence of E× B drift on tungsten target erosion and W impurity transport during neon seeding on EAST

Y Wang, C Sang, X Zhao, Y Wu, Q Zhou… - Nuclear …, 2023 - iopscience.iop.org
Mitigating tungsten (W) wall erosion and core accumulation are vitally important for the
steady-state operation of tokamaks. It is well known that drifts have a great impact on the …

Compatibility of large ELM control and stable partial detachment with neon/argon seeding in EAST

K Li, X Lin, Z Yang, Q Yang, G Xu, L Meng… - Nuclear …, 2023 - iopscience.iop.org
It is necessary to achieve simultaneous exhaust of excessive transient and steady-state heat
fluxes on the divertor target for the divertor protection in the future fusion reactors. The …

Modelling of tungsten impurity edge transport and screening for different divertor conditions in EAST

H Wang, G Xu, R Ding, X Liu, H Si, Q Zhang… - Nuclear …, 2022 - iopscience.iop.org
Tungsten (W) transport and screening in the edge plasma are investigated for EAST high
dissipative divertor conditions. By combining the 1D impurity fluid model (1DImpFM) and the …

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 …

Recent EAST experimental results and systems upgrade in support of long-pulse steady-state plasma operation

Y Song, B Wan, X Gong, J Li, X Wu… - … on Plasma Science, 2022 - ieeexplore.ieee.org
In recent years, EAST has achieved a 60-s scale steady-state plasma operation (SSO),
which is electron dominant heated by the electron cyclotron wave and low hybrid wave …

Design and thermal-hydraulic analysis for CFETR divertor OVT in consideration of RH compatibility

X Zhang, L Yin, N Mou, L Cao, T Xu, D Yao - Fusion Engineering and …, 2023 - Elsevier
The divertor is a key in-vessel component of the China Fusion Engineering Test Reactor
(CFETR), which is mainly used to remove high heat load and exclude particles. In addition …

Achievements of actively controlled divertor detachment compatible with sustained high confinement core in DIII-D and EAST

L Wang, HQ Wang, D Eldon, QP Yuan, S Ding… - Nuclear …, 2022 - iopscience.iop.org
The compatibility of efficient divertor detachment with high-performance core plasma is vital
to the development of magnetically controlled fusion energy. The joint research on the EAST …