A5102706688- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Nuclear reactor physics and engineering
- Plasma Diagnostics and Applications
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Advanced Computational Techniques and Applications
- Superconducting and THz Device Technology
- Glaucoma and retinal disorders
- Muon and positron interactions and applications
- Terahertz technology and applications
- Electrostatic Discharge in Electronics
- Ocular Diseases and Behçet’s Syndrome
- Metallurgical Processes and Thermodynamics
- Aluminum Alloy Microstructure Properties
- Electromagnetic Launch and Propulsion Technology
- Power Systems and Technologies
- Gyrotron and Vacuum Electronics Research
- Microwave Dielectric Ceramics Synthesis
- Ferroelectric and Piezoelectric Materials
- Crystal Structures and Properties
North Minzu University
2025
The Graduate University for Advanced Studies, SOKENDAI
2025
University of California, Davis
2024
Institute of Plasma Physics
2013-2022
Chinese Academy of Sciences
2013-2022
University of Science and Technology of China
2017-2021
Hefei Institutes of Physical Science
2021
University of Saskatchewan
2015
Tsinghua University
2015
Johns Hopkins University
2015
The Chinese Fusion Engineering Testing Reactor (CFETR), complementing the ITER facility, is aiming to demonstrate fusion energy production up 200 MW initially and eventually reach DEMO relevant power level 1 GW, manifest a high duty factor of 0.3–0.5, pursue tritium self-sufficiency with breeding ratio (TBR) >1. key challenge meet missions CFETR run machine in steady state (or long pulse) factor. By using multi-dimensional code suite physics-based models, self-consistent steady-state hybrid...
In order to withstand rapid increase in particle and power impact onto the divertor demonstrate feasibility of ITER design under long pulse operation, upper EAST tokamak has been upgraded actively water-cooled, ITER-like tungsten mono-block structure since 2014 campaign, which is first attempt for on devices. Therefore, a new Langmuir probe diagnostic system (DivLP) was designed successfully obtain plasma parameters region such as electron temperature, density, heat fluxes. More...
This study employs the first-principles calculation method based on density functional theory to investigate and analyze effects of doping various rare earthions optical properties bismuth silicate (Bi4Si3O12, BSO) crystals. The results indicate that electronic structure variations earth ions significantly influence transition characteristics BSO crystals, thereby altering their properties. Specifically, Tm3+ notably enhances polarization capability infrared responsiveness Ho3+ improves...
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...
The poloidal long-wavelength E x B time-varying flows were directly measured using a forked Langmuir probe in the HT-7 tokamak. Low-frequency (<10 kHz) observed at plasma edge, which possess many of characteristics zonal flows, including (k(theta)rho(i) approximately 0) and narrow radial extent (k(r)rho(i) 0.1). cross bicoherence turbulent Reynolds stress indicates existence nonlinear three-wave coupling processes generation low-frequency flows. estimated flow-shearing rate is same order...
The Experimental Advanced Superconducting Tokamak (EAST) has demonstrated, for the first time, long-pulse divertor plasmas over 400 s, entirely driven by lower hybrid current drive (LHCD), and further extended high-confinement plasmas, i.e. H-modes, 30 s with predominantly LHCD advanced lithium wall conditioning. Many new exciting physics results have been obtained in quest operations. key findings are as follows: (1) access to H-modes EAST favours configuration ion ∇B drift directed away...
Abstract A total power injection up to 0.3 GJ has been achieved in EAST long pulse H-mode operation of 101.2 s with an ITER-like water-cooled tungsten (W) mono-block divertor, which steady-state exhaust capability 10 MWm −2 . The peak temperature W target saturated at 12 the value T ~ 500 °C a heat flux ~3.3 MW m being maintained during discharge. By tailoring 3D divertor plasma footprint through edge magnetic topology change, load was broadly dispersed and thus sputtering were well...
The active feedback control of radiated power to prevent divertor target plates overheating during long-pulse operation has been developed and implemented on EAST. radiation algorithm, with impurity seeding via a supersonic molecular beam injection (SMBI) system, shown great success in both reliability stability. By sequence short neon (Ne) pulses the SMBI from outer mid-plane, bulk plasma can be well controlled, duration radiative (feedforward feedback) is 4.5 s discharge 10 s. Reliable...
A stationary edge-localized mode (ELM)-absent H-mode regime, with an electrostatic edge coherent (ECM) which resides in the pedestal region, has been achieved EAST tokamak recently. This regime allows operation of a nearly fully noninductive long pulse (>15 s), exhibiting relatively high and good global energy confinement near 1.2, excellent impurity control. Furthermore, this is mostly obtained 4.6 GHz lower hybrid current drive (LHCD) or counter-current neutral beam injection (NBI), plus...
The fast electron flux driven by Lower Hybrid Wave (LHW) in the scrape-off layer (SOL) EAST is analyzed both theoretically and experimentally. five bright belts flowing along magnetic field lines SOL hot spots at LHW guard limiters observed charge coupled device infrared cameras are attributed to flux, which directly measured retarding analyzers (RFA). current carried ranging from 400 6000 A/m2 direction opposite plasma current, scanned radial limiter surface position about 25 mm beyond...
Abstract The power threshold for low (L) to high (H) confinement mode transition achieved by radio-frequency (RF) heating and lithium-wall coating is investigated experimentally on EAST two sets of walls: an all carbon wall (C) molybdenum chamber a divertor (Mo/C). For both walls, minimum P thr ~0.6 MW was found when the operates in double null (DN) configuration with intensive coating. When operating upper single (USN) or lower (LSN), depends ion ∇ B drift direction. density dependence L–H...
The long-pulse high-performance fully non-inductive plasma is one of the major scientific objectives on EAST using ITER-like tungsten upper divertor.Understanding and optimizing fast-ion behaviors critical issue to extend performance EAST.Recently, both NBI (neutral beam injection) RF (low hybrid, electron cyclotron ion cyclotron) heating, high-β P scenarios with extension fusion at high density low rotation have been achieved β up 2.5, N 2.0 H 98y2 >1.1, bootstrap current fraction (f BS )...
Joint DIII-D/EAST experiments in the radio-frequency (RF) heated H-mode scheme with comparison to that of neutral beam (NB) were carried out on DIII-D and EAST under similar conditions examine effect heating scrape-off layer (SOL) width plasmas for application ITER. A dimensionally plasma equilibrium was used match shape parameters. The divertor heat flux SOL widths measured infra-red camera DIII-D, while Langmuir probe array EAST. It has been demonstrated both RF-heated a broader than...
In this paper, we present clear experimental evidence of core region nonlinear coupling between (intermediate, small)-scale microturbulence and an magnetohydrodynamics (MHD) mode during the current ramp-down phase in a set L-mode plasma discharges advanced superconducting tokamak (EAST, Wan et al (2006 Plasma Sci. Technol. 8 253)). Density fluctuations broadband () MHD (toroidal number , poloidal ) are measured simultaneously, using four-channel tangential laser collective scattering...
Three dimensional (3D) divertor particle flux footprints induced by the lower hybrid wave (LHW) have been systematically investigated in EAST superconducting tokamak during recent experimental campaign. We find that striated (SPF) peaks away from strike point (SP) closely fit pitch of edge magnetic field line for different safety factors q95, as predicted a tracing code taking into account helical current filaments (HCFs) scrape-off-layer (SOL). As LHW power increases, it requires fuelling...
The experimental advanced superconducting tokamak (EAST) is one of the fully tokamaks. A high-power neutral beam injector (NBI) system consisting two injectors (EAST-NBI) was employed on EAST for plasma heating and current driving. designed deuterium energy 50–80 keV, power 2–4 MW, duration 10–100 s. Each beamline equipped with hot cathode ion sources can be operated individually. In order to support planned physics research EAST, NBI-2 shifted from port F D, at same time, its injection...
Abstract The fast‐reconnection simulation of ELMs in high‐confinement mode tokamak discharges with non‐ideal physics effects has been reported by Xu, et al [1] a minimum set three‐field two‐fluid equations. Here we improve the adding perturbed parallel velocity and Hall effect, then extend model to four‐field equations describe pedestal collapse BOUT++ code. Compared previous results, find that can decrease growth rate 20.0%, ELM size is decreased 12.1%. effect influences linear effectively....