A5064307823- Magnetic confinement fusion research
- Ionosphere and magnetosphere dynamics
- Fusion materials and technologies
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Solar and Space Plasma Dynamics
- Laser-induced spectroscopy and plasma
- Nuclear reactor physics and engineering
- Physics of Superconductivity and Magnetism
- Nuclear Physics and Applications
- Atomic and Subatomic Physics Research
- Dust and Plasma Wave Phenomena
- Chalcogenide Semiconductor Thin Films
- Quantum Dots Synthesis And Properties
- Ion-surface interactions and analysis
- Atomic and Molecular Physics
- Copper-based nanomaterials and applications
- Photonic and Optical Devices
- Nuclear Materials and Properties
- Geomagnetism and Paleomagnetism Studies
- Rheology and Fluid Dynamics Studies
- Quantum chaos and dynamical systems
- Spacecraft and Cryogenic Technologies
Forschungszentrum Jülich
2016-2025
Sun Yat-sen University
2017-2025
Solar Energy Research Institute of Sun Yat-sen University
2018-2024
Shaanxi Yulin Energy Group
2024
Nankai University
2024
Chinese Academy of Sciences
2014-2023
Huazhong University of Science and Technology
2018-2023
Institute of Plasma Physics
2013-2022
Tongji Hospital
2022
Southwestern Institute of Physics
2022
Type-I edge-localized modes (ELMs) have been mitigated at the JET tokamak using a static external $n=1$ perturbation field generated by four error correction coils located far from plasma. During application of ELM frequency increased factor 4 and amplitude ${\mathrm{D}}_{\ensuremath{\alpha}}$ signal decreased. The energy loss per normalized to total stored energy, $\ensuremath{\Delta}W/W$, dropped values below 2%. Transport analyses shows no or only moderate (up 20%) degradation confinement...
Evidence of a nonlinear transition from mitigation to suppression the edge localized mode (ELM) by using resonant magnetic perturbations (RMPs) in EAST tokamak is presented. This first demonstration ELM with RMPs slowly rotating plasmas dominant radio-frequency wave heating. Changes topology after are indicated gradual phase shift plasma response field linear magneto hydro dynamics modeling result vacuum one and sudden increase three-dimensional particle flux divertor. The threshold depends...
As part of the ITER Design Review and in response to issues identified by Science Technology Advisory Committee, physics requirements were reviewed as appropriate updated. The focus this paper will be on recent work affecting design with special emphasis topics near-term procurement arrangements. This describe results on: sensitivity studies, poloidal field coil requirements, vertical stability, effect toroidal ripple thermal confinement, material choice heat load for plasma-facing...
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...
Significant progress, on both the technological and physical fronts, towards high-performance, long-pulse plasma discharges has been made in EAST (the experimental advanced superconducting tokamak) since last IAEA FEC. With enhanced operational capabilities, following key results have achieved with lithium wall conditioning: fully steady-state diverted plasmas entirely driven by lower hybrid current drive (LHCD) over 400 s stationary H-mode 30 LHCD ion cyclotron resonant heating (ICRF)....
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...
Since the 2012 International Atomic Energy Agency Fusion Conference (IAEA-FEC), significant advances in both physics and technology has been made on Experimental Advanced Superconducting Tomakak (EAST) toward a long-pulse stable high-confinement (H-mode) plasma regime. The experimental capabilities of EAST have technically upgraded with power enhancement (source up to 26 MW) continuous-wave heating current drive system, replacement upper graphite divertor an ITER-like W monoblock divertor,...
Abstract The non-linear reduced four-field RMHD model in cylindrical geometry was extended to include plasma rotation, neoclassical poloidal viscosity and two fluid diamagnetic effects. Interaction of the static resonant magnetic perturbations (RMPs) with rotating plasmas tokamaks studied. self-consistent evolution equilibrium electric field due RMP penetration is taken into account model. It demonstrated that pedestal region steep pressure gradients, mean flows perpendicular field, which...
An electrostatic coherent mode near the electron diamagnetic frequency (20-90 kHz) is observed in steep-gradient pedestal region of long pulse H-mode plasmas Experimental Advanced Superconducting Tokamak, using a newly developed dual gas-puff-imaging system and diamond-coated reciprocating probes. The propagates direction plasma frame with poloidal wavelength ∼8 cm. drives significant outflow particles heat as measured directly probes, thus greatly facilitating sustainment. This shows nature...
A critical challenge facing the basic long-pulse high-confinement operation scenario ($H$ mode) for ITER is to control a magnetohydrodynamic (MHD) instability, known as edge localized mode (ELM), which leads cyclical high peak heat and particle fluxes at plasma components. breakthrough made in Experimental Advanced Superconducting Tokamak achieving new steady-state $H$ without presence of ELMs duration exceeding hundreds energy confinement times, by using novel technique continuous real-time...
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...
Sustained edge-localized mode (ELM) mitigation has been achieved using resonant magnetic perturbations (RMPs) with a toroidal number of n = 4 and 6 in lower single null 3 connected double plasmas on MAST. The ELM frequency increases by up to factor eight similar reduction energy loss. A threshold current for is observed above which the approximately linearly coils. comparison filament structures during ELMs natural mitigated stages shows that have characteristics type I even though their...
Recent experiments on JET have shown that type-I edge localized modes (ELMs) can be controlled by the application of static low n = 1 external magnetic perturbation fields produced four error field correction coils (EFCC) mounted far away from plasma between transformer limbs. When an with amplitude a few mT at (the normalized poloidal flux, ?, is larger than 0.95) applied during stationary phase ELMy H-mode plasma, ELM frequency rises ~30?Hz up to ~120?Hz. The energy loss per total stored...
The first results of edge-localized mode (ELM) pacing using small spherical lithium granules injected mechanically into H-mode discharges are reported. Triggering ELMs was accomplished a simple rotating impeller to inject sub-millimetre size at speeds few tens meters per second the outer midplane EAST fusion device. During injection phase, were triggered with near 100% efficiency and amplitude induced as measured by Dα clearly reduced compared contemporaneous naturally occurring ELMs. In...
A set of in-vessel resonant magnetic perturbation (RMP) coil has been recently installed in EAST. It can generate a range spectrum, and there is relatively large window for edge localized mode (ELM) control according to the vacuum field modeling island overlapping area. Observation mitigation suppression ELM slow rotating plasmas during application an n = 1 RMP presented this paper. Strong effect observed neutral beam injection heating plasmas. The frequency increases by factor 5, crash...
The J-TEXT tokamak has been operated for ten years since its first plasma obtained at the end of 2007. diagnostics development and main modulation systems, i.e. resonant magnetic perturbation (RMP) systems massive gas injection (MGI) will be introduced in this paper. Supported by these efforts, contributed to research on several topics, especially RMP physics disruption mitigation. Both experimental theoretical show that could lock, suppress or excite tearing modes, depending amplitude,...
Abstract In the last two years, three major technical improvements have been made on J-TEXT in supporting of expanded operation regions and diagnostic capabilities. (1) The successful commission 105 GHz/500 kW/1 s electron cyclotron resonance heating (ECRH) system increasing core temperature from 0.9 keV up to around 1.5 keV. (2) poloidal divertor configuration with an X -point high-field side has achieved. particular, 400 kW wave also successfully injected into diverted plasma. (3) A...
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...
Abstract A systematic numerical investigation is carried out to understand magnetohydrodynamic stability of the ideal infernal-kink instability in tokamak plasmas with both negative triangularity (neg-D) shaping and central shear for equilibrium safety factor profile. The latter motivated by desire form internal transport barrier neg-D configuration, which known have difficulty forming edge barrier. mode generally found be more unstable as compared their positive D-shaped (pos-D)...
Radial profiles of ion temperature and plasma flow are measured at the n/m = 1/1 magnetic island produced by external perturbation coils in Large Helical Device. The sheared poloidal flows radial electric field observed boundaries island, because vanishes inside static island. When width becomes large, along flux surface appears around O point direction which reduces shear boundary
In the first four years of LHD experiment, several encouraging results have emerged, most significant which is that MHD stability and good transport are compatible in inward shifted axis configuration. The observed energy confinement at this optimal configuration consistent with ISS95 scaling an enhancement factor 1.5. over smaller heliotron devices attributed to high edge temperature. We find plasma average beta 3% stable configuration, even though theoretical conditions Mercier modes...