Results 51 to 60 of about 337 (131)
The present research presents an innovative approach by integrating magnetohydrodynamic (MHD) flow with resistive heating, integrating a partly permeable layer and interior heat production to scrutinize natural convective flow within a square domain. It also examines both straight and wavy interfaces between the porous and fluid domains.
Nahid Hasan +3 more
wiley +1 more source
Towards detachment-compatible I-mode plasma on EAST tokamak
The divertor detachment is important for the improved confinement mode (I-mode) to serve as a reliable operating scenario in future fusion reactors. A reproducible steady-state I-mode operation with the energy detachment of the inner target has been ...
L. Yu +25 more
doaj +1 more source
Lithiation is beneficial to enhance plasma performance in EAST by reducing hydrogen and impurities recycling via lithium (Li) wall conditioning. High-Z materials like tungsten (W) have been selected as up–divertor in EAST tokamak.
Cong Li +7 more
doaj +1 more source
Impurity control study of radiative tungsten divertor in EAST tokamak
EAST was equipped with W-coated divertor plates and dome for the upper divertor, the remaining plasma facing components include the plasma facing components at lower divertor consisted of Carbon materials, at the baffles and main chamber walls consisted ...
YiPing Chen +4 more
doaj +1 more source
Tokamak discharge simulation for EAST by coupling METIS and free-boundary equilibrium code FBT
Fast and reliable discharge modeling is an essential tool for tokamak scenario development, as extensive simulations are required to explore the feasible operational space and translate physical targets into implementable actuator waveforms. In this work,
Wenyi Lu +31 more
doaj +1 more source
Millimeter Wave Power Monitoring in EAST ECRH System
This paper presents a stable millimeter-wave power monitoring system for ECRH on EAST tokamak. The real-time power monitoring was realized based on power monitor miter bends. The “Exchange”method was proposed to monitor the reflection power
Weiye Xu +7 more
doaj +1 more source
Thermal damage detection of EAST internal component based on machine learning
During the discharge process, thermal events are common and destructive in Tokamak experiments. High energy particles in plasma can collide with device components such as limiters and diverters, which can lead to overheating, material cracking, and even ...
Zhongfang Guan +20 more
doaj +1 more source
Calculation of in-situ steady-state heat flux on EAST lower divertor
Heat flux is a key issue in tokamak devices. The non-uniform high heat flux on Plasma-Facing Components (PFCs) has led to local severe damage, including cracks and melting, in current tokamaks such as EAST and WEST.
Chunyu He +12 more
doaj +1 more source
To build an online and non-contact diagnosis system of surface morphology of Plasma-Facing Components (PFCs) in fusion devices, a measurement system based on Laser Speckle Interferometry (LSI) is in development in our laboratory.
Yuanbo Li +3 more
doaj +1 more source
The effect of neon seeding on plasma edge transport in EAST
Impurity seeding is crucial for power exhaust in future power plants. In the presented analysis, neon seeding for the Experimental Advanced Superconducting Tokamak (EAST) tokamak is studied.
Dieter Boeyaert +9 more
doaj +1 more source

