A5008855712- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Geotechnical and Geomechanical Engineering
- Advanced Battery Technologies Research
- Nuclear reactor physics and engineering
- Ionosphere and magnetosphere dynamics
- Laser Material Processing Techniques
- Nuclear Materials and Properties
- Laser-induced spectroscopy and plasma
- Magneto-Optical Properties and Applications
- Particle Accelerators and Free-Electron Lasers
- Plasma Diagnostics and Applications
- Advanced Surface Polishing Techniques
- Advanced machining processes and optimization
University of Nottingham Ningbo China
2024
Tongji University
2024
University of Science and Technology of China
2012-2021
Institute of Plasma Physics
2015-2018
Chinese Academy of Sciences
2015-2018
Abstract The long-pulse high-confinement (H-mode) plasma regime is considered to be a preferable scenario in future fusion devices, and the period of normal operation during H-mode, edge-localised modes (ELMs) are one most serious threats performance capability divertor targets. EAST recently achieved variety H-mode regimes with ELMs. For purpose studying upgraded type I ELMs, series simulations were performed by using three-dimensional (3D) finite element code. To make visible outcome...
Laser trepanning drilling is a widely used manufacturing technology for creating holes in thin-walled parts or difficult-to-cut materials due to its exceptional efficiency and versatility with various material types. Although there have been several experimental studies on laser trepanning, comprehensive understanding of the relationship between system layout, beam alignment, produced hole geometries still lacking from theoretical perspective. To address this, generic model typical...
China Fusion Engineering Test Reactor (CFETR) is now in the conceptual design phase. The main objective of CFETR demonstration fusion energy with 50 ~ 200 MW power, fuel cycle T self-sustained and steady-state operation duty 0.3 0.5. involves complex system structure, there are constrains between physics engineering. Between optimization performance parameters structure key components, numerous data exchange iterative necessary for optimal sub-systems. To do design, a code under development....
Neutral beam (NB) attenuation and emission are important aspects for Beam Emission Spectroscopy diagnostic on magnetic confinement devices. In this article, we present the simulation of in typical HL-2A discharge scenarios, i.e. Low mode (L-mode) High (H-mode) discharges. Not only NB attenuation, but also plasma density electron temperature determine intensity. The pronounced peak ranges from ρ =r/a=0.7 to 0.9 H-mode discharge, while it has a much lower broader L-mode discharge. 16 BES...
China Fusion Engineering Testing Reactor (CFETR) is proposed as a good complement to ITER for demonstration of fusion energy. The main goals CFETR are power 50〜200 MW, duty cycle time 0.3〜0.5 and tritium breeding ratio ≥ 1.2. based on both physics some technologies ITER. Therefore, lower single-null (LSN) divertor (also called ITER-like divertor) basic choice CFETR. heat from core plasma into scrapped-off layer (SOL) estimated 100 which implies that the must have enough ability reduce via...