A5029947227- Magnetic confinement fusion research
- Ionosphere and magnetosphere dynamics
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Superconducting Materials and Applications
- Solar and Space Plasma Dynamics
- Evacuation and Crowd Dynamics
- Robot Manipulation and Learning
- Fire dynamics and safety research
- Plasma Diagnostics and Applications
- Human Pose and Action Recognition
- 3D Shape Modeling and Analysis
- Fire effects on ecosystems
- 3D Surveying and Cultural Heritage
- Advanced Measurement and Metrology Techniques
- Computer Graphics and Visualization Techniques
- Manufacturing Process and Optimization
- Advanced Numerical Analysis Techniques
- Robotics and Sensor-Based Localization
- Robotic Path Planning Algorithms
- Image and Object Detection Techniques
- Laser-induced spectroscopy and plasma
- Nuclear reactor physics and engineering
- Advanced machining processes and optimization
Chongqing University
2025
Southwest University of Science and Technology
2025
Changchun University of Science and Technology
2025
University Town of Shenzhen
2017-2024
Tsinghua University
2013-2024
Chinese Academy of Sciences
2015-2024
University of California, Los Angeles
2012-2024
University of Electronic Science and Technology of China
2024
Tsinghua–Berkeley Shenzhen Institute
2021-2024
Chang'an University
2024
Mastering nuclear fusion, which is an abundant, safe, and environmentally competitive energy, a great challenge for humanity. Tokamak represents one of the most promising paths toward controlled fusion. Obtaining high-performance, steady-state, long-pulse plasma regime remains critical issue. Recently, big breakthrough in steady-state operation was made on Experimental Advanced Superconducting (EAST). A with world-record pulse length 1056 s obtained, where density divertor peak heat flux...
The EAST research program aims to demonstrate steady-state long-pulse advanced high-performance H-mode operations with ITER-like poloidal configuration and RF-dominated heating schemes. Since the 2014 IAEA FEC, has been upgraded all ITER-relevant auxiliary current drive systems, enabling investigation of plasma profile control by coupling/integration various combinations. Fully non-inductive (H 98,y2 > 1.1) was extended over 60 s for first time sole RF plus good power coupling impurity...
A double-pass, radially viewing, far-infrared laser-based POlarimeter-INTerferometer (POINT) system utilizing the three-wave technique has been implemented for diagnosing plasma current and electron density profiles in Experimental Advanced Superconducting Tokamak (EAST). POINT operated routinely during most recent experimental campaign provides continuous 11 chord line-integrated Faraday effect measurement throughout entire discharge all heating schemes conditions (including ITER relevant...
Strong mitigation of edge-localized modes has been observed on Experimental Advanced Superconducting Tokamak, when lower hybrid waves (LHWs) are applied to H-mode plasmas with ion cyclotron resonant heating. This demonstrated be due the formation helical current filaments flowing along field lines in scrape-off layer induced by LHW. leads splitting outer divertor strike points during LHWs similar previous observations magnetic perturbations. The change topology qualitatively modeled...
Since the last IAEA-FEC in 2016, EAST physics experiments have been developed further support of high-performance steady-state operation for ITER and CFETR.First demonstration >100 seconds time scale long-pulse scenario with a good plasma performance (H98(y2) ~ 1.1) control impurity heat exhaust upper tungsten divertor has achieved on using pure radio frequency (RF) power heating current drive.The operational domain significantly extended towards more CFETR related high beta regime (βP ~2.5...
Abstract Recent J-TEXT research has highlighted the significance of role that non-axisymmetric magnetic perturbations, so called three-dimensional (3D) perturbation (MP) fields, play in a fundamentally 2D concept, i.e. tokamaks. This paper presents results achieved over last two years, especially on impacts 3D MP fields magnetohydrodynamic instabilities, plasma disruptions and turbulence transport. On J-TEXT, resonant (RMP) system, capable providing either static or high frequency (up to 8...
Pseudo-label-based semi-supervised learning (SSL) has achieved great success on raw data utilization. However, its training procedure suffers from confirmation bias due to the noise contained in self-generated artificial labels. Moreover, model's judgment becomes noisier real-world applications with extensive out-of-distribution data. To address this issue, we propose a general method named Class-aware Contrastive Semi-Supervised Learning (CCSSL), which is drop-in helper improve pseudo-label...
A low amplitude (δbr∕BT=1 part in 5000) edge resonant magnetic field perturbation with toroidal mode number n=3 and poloidal numbers between 8 15 has been used to suppress most large type I localized modes (ELMs) without degrading core plasma confinement. ELMs have suppressed for periods of up 8.6 energy confinement times when the safety factor q95 is 3.5 4. The are replaced by packets events (possibly II ELMs) small amplitude, narrow radial extent, a higher level density fluctuations,...
Recent results from an ITPA joint experiment to study the onset, growth, and decay of relativistic electrons (REs) indicate that loss mechanisms other than collisional damping may play a dominant role in dynamics RE population, even during quiescent Ip flattop. Understanding physics growth mitigation is motivated by theoretical prediction disruptions full-current (15 MA) ITER discharges could generate up 10 MA REs with 10–20 MeV energies. The MHD group conducting measure detection threshold...
Recent Experimental Advanced Superconducting Tokamak (EAST) experiments have successfully demonstrated a long-pulse steady-state scenario with improved plasma performance through integrated operation since the last IAEA FEC in 2016. A discharge duration over 100 s using pure radio frequency (RF) power heating and current drive has been obtained required characteristics for future tokamak reactors such as good energy confinement quality (H98y2 ~ 1.1) electron internal transport barrier inside...
Key plasma physics and real-time control elements needed for robustly stable operation of high fusion power discharges in ITER have been demonstrated recent research worldwide.Recent analysis has identified the current density profile as main drive disruptive instabilities simulating ITER's baseline scenario with low external torque.Ongoing development model-based active magnetohydrodynamic is improving stability multiple scenarios.Significant advances made toward physicsbased prediction...
Accurate object 6D pose estimation is a core task for robot bin-picking applications, especially when objects are randomly stacked with heavy occlusion. To address this problem, paper proposes simple but novel Point-wise Pose Regression Network (PPR-Net). For each point in the cloud, network regresses of instance that belongs to. We argue regressed poses points from same should be located closely space. Thus, these can clustered into different instances and their corresponding objects'...
Abstract Small perturbations and strong impurity exhaust capability associated with the small grassy ELMs render grassy-ELM regime a suitable candidate for achieving steady-state H-mode operation radiative divertor, especially in metal-wall device, such as Experimental Advanced Superconducting Tokamak (EAST). As degradation of pedestal performance excessive divertor seeding or accumulation tends to be accompanied significantly increased radiation near X point, feedback control absolute...
In this study, a long short-term memory (LSTM) model is trained on large disruption warning database to predict the EAST tokomak. To compare performance of proposed with previously reported full convolutional neural network (CNN) (Guo et al 2020 Plasma Phys. Control. Fusion 63 025008), same data set and diagnostic signals are used. Based test set, area under receiver operating characteristic curve, i.e. AUC value LSTM obtained as 0.87, true positive rate (TPR) sim87.5%, while false (FPR)...
Full suppression of type-I edge localized modes (ELMs) using n = 4 resonant magnetic perturbations (RMPs) as planned for ITER has been demonstrated the first time (n is toroidal mode number applied RMP). This achieved in EAST plasmas with low input torque and tungsten divertor, target plasma these experiments chosen to be relevant Q 10 operational scenario, thus also addressing significant scenario issues ITER. In lowest neutral beam injection (NBI) around TNBI ∼ 0.44 Nm, which extrapolates...
Small edge resonant magnetic perturbations are used to control the pedestal transport and stability in low electron collisionality (νe*), ITER [ITER Physics Basis Editors et al., Nucl. Fusion 39, 2137 (1999)] relevant, poloidally diverted plasmas. The applied reduce height of density increase its width while increasing temperature gradient. effect on gradients is controlled by current perturbation coil, poloidal mode spectrum neutral beam heating power, divertor deuterium fueling rate. Large...
Magnetic turbulence is observed at the beginning of current quench in intended TEXTOR disruptions. Runaway electron (RE) suppression has been experimentally found magnetic larger than a certain threshold. Below this threshold, generated RE inversely proportional to level turbulence. The originates from background plasma and amplitude depends strongly on toroidal field density. These results explain previously threshold for generation have be considered predictions ITER.