Xu Yang

ORCID: 0000-0001-6373-1650
Publications
Citations
Views
---
Saved
---
About
Contact & Profiles
Research Areas
  • Magnetic confinement fusion research
  • Ionosphere and magnetosphere dynamics
  • Particle accelerators and beam dynamics
  • Superconducting Materials and Applications
  • Advanced Photocatalysis Techniques
  • Fusion materials and technologies
  • Advanced battery technologies research
  • Electrocatalysts for Energy Conversion
  • Physics of Superconductivity and Magnetism
  • Plasma Diagnostics and Applications
  • Laser-Plasma Interactions and Diagnostics
  • Advanced Frequency and Time Standards
  • Solar and Space Plasma Dynamics
  • Atomic and Molecular Physics
  • Geomagnetism and Paleomagnetism Studies
  • Fluid Dynamics and Mixing
  • Metal and Thin Film Mechanics
  • Quantum optics and atomic interactions
  • Magneto-Optical Properties and Applications
  • Atomic and Subatomic Physics Research
  • Water Treatment and Disinfection
  • Water Systems and Optimization

Chongqing Technology and Business University
2019-2025

Dalian University of Technology
2016-2024

California State Polytechnic University
2021

General Atomics (United States)
1990-2018

Materials Modification (United States)
2018

Dalian University
2016

Johns Hopkins University
1990

Fusion Academy
1990

Resonant magnetic perturbations (RMP) have extensively been demonstrated as a plausible technique for mitigating or suppressing large edge localized modes (ELMs). Associated with this is substantial amount of theory and modelling efforts during recent years. Various models describing the plasma response to RMP fields proposed in literature, are briefly reviewed work. Despite their simplicity, linear can provide alternative criteria, than vacuum field based guiding choice coil configurations...

10.1088/0741-3335/58/11/114005 article EN Plasma Physics and Controlled Fusion 2016-10-11

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...

10.1088/1741-4326/57/3/036007 article EN Nuclear Fusion 2016-12-12

Extensive modelling efforts of the plasma response to resonant magnetic perturbation fields, utilized for controlling edge localized mode (ELM), help identify edge-peeling as a key factor, which correlates observed ELM mitigation in several tokamak devices, including MAST, ASDEX Upgrade, EAST, and HL-2A. The recently safety factor window HL-2A experiments is explained terms response. computed response, based on toroidal single fluid resistive model with different assumption flows, found...

10.1063/1.4978884 article EN Physics of Plasmas 2017-03-22

Sustained mitigation and/or suppression of the type-I edge localized modes (ELMs) have been achieved in EAST H-mode plasmas, utilizing resonant magnetic perturbation (RMP) fields, produced by two rows coils located just inside vacuum vessel.Systematic toroidal modelling plasma response to these RMP with various coil configurations (with dominant mode number n=1, 2, 3, 4) EAST, is for first time carried out using MARS-F code [Liu Y et al 2000 Phys.Plasmas 7 3681], results reported here.In...

10.1088/0741-3335/58/11/114006 article EN Plasma Physics and Controlled Fusion 2016-10-11

Density scaling of error field penetration in EAST is investigated with different n = 1 magnetic perturbation coil configurations ohmically heated discharges. The density scalings thresholds under two spectra are and , where br the ne line averaged electron density. One difficulty understanding that key parameters other than determining process may also be changed when plasma changes. Therefore, they should determined from experiments. estimated theoretical analysis ( lower region higher...

10.1088/1741-4326/aab5c0 article EN Nuclear Fusion 2018-03-12

Magnetic coil design study is carried out, for the purpose of mitigating or suppressing edge localized modes (ELMs) in a EU DEMO reference scenario. The design, including both geometry and current requirement, based on criteria derived from linear, full toroidal plasma response computed by MARS-F code (Liu et al 2000 Phys. Plasma 7 3681). With single midplane row coils, size covering about 30°–50° poloidal angle torus found to be optimal ELM control using n > 2 resonant magnetic perturbation...

10.1088/1741-4326/aac602 article EN Nuclear Fusion 2018-05-18

Toroidal computation of the plasma response to n = 2 (n is toroidal mode number) resonant magnetic perturbation field, based on an H-mode in DIII-D, carried out for purpose investigating role ideal versus resistive models while scanning safety factor (q) at edge. Both models, implemented MARS-F code (Liu et al 2000 Phys. Plasmas 7 3681), show significant amplification kink-peeling certain q-windows. A longstanding issue addressed this work sensitivity q-window smoothing X-point geometry...

10.1088/1741-4326/ab20f9 article EN Nuclear Fusion 2019-05-10

Abstract The influence of negative triangularity (NT) the plasma shape on n = 1 (n is toroidal mode number) tearing (TM) stability has been numerically investigated, with results compared to that positive (PT) counterpart. By matching safety factor profile for a series equilibria, several important parameters, including triangularity, equilibrium pressure, resistivity as well rotation, have varied. TM localized near edge found be more unstable in NT plasmas PT fundamental reason this...

10.1088/1741-4326/acc750 article EN cc-by Nuclear Fusion 2023-03-24

The combined effects of anisotropic thermal transport and the plasma shaping, including negative triangularity, on n = 1 (n is toroidal mode number) tearing (TM) stability are numerically investigated utilizing MARS-F code [Liu et al., Phys. Plasmas 7, 3681–3690 (2000)]. While varying boundary TM found to be dictated by competing Shafranov shift induced stabilization bad-curvature destabilization. triangularity shape increases (stabilizing) in core but also enlarges regions (destabilizing)...

10.1063/5.0205397 article EN cc-by Physics of Plasmas 2024-05-01

Based on an ITER 15MA Q = 10 inductive scenario, a systematic numerical investigation is carried out in order to understand the effect of varying geometry magnetic coils, used for controlling edge localized modes tokamaks, plasma response resonant perturbation (RMP) fields produced by these coils. Toroidal computations show that both based figures merit—one pitch radial field component near and other displacement X-point separatrix—consistently yield same prediction optimal coil geometry....

10.1088/0741-3335/58/11/115003 article EN Plasma Physics and Controlled Fusion 2016-09-08

Our three-dimensional toroidal magnetohydrodynamics code [CLT (Ci-Liu-Ti, which means in Chinese)] is upgraded to CLTx the simulation domain extends a scrape-off layer (SOL). Linear results of resonant magnetic perturbation (RMP) for edge-localized-mode mitigation discharge 52340 EAST Tokamak agree well with those from MARS-F code. With presence X-point and SOL, RMP amplitude phase shift pedestal region, especially higher m mode, are largely affected by resistivity SOL. A π harmonics vacuum...

10.1063/1.5116669 article EN Physics of Plasmas 2019-11-01

Analysis of the circular polarization Lii 6708 Å line emitted from a monoenergetic lithium beam provides spatially resolved measurement poloidal magnetic field on Texas experimental tokamak [Nucl. Technol. Fusion 1, 479 (1989)]. Determined measured field, safety factor axis during Ohmically heated sawtoothing discharges is near unity.

10.1063/1.859317 article EN Physics of Fluids B Plasma Physics 1990-04-01

Abstract A systematic investigation of the plasma response to an externally applied resonant magnetic perturbation (RMP) field, for purpose controlling edge localized modes, is carried out EU DEMO reference plasma. Particular emphasis placed on role kinetic effects associated with both thermal particles and fusion-born alphas. The single fluid, resistive model predicts a large peak amplification n = 1 ( toroidal mode number) target equilibrium, which found be close Troyon no-wall limit. more...

10.1088/1361-6587/acb012 article EN Plasma Physics and Controlled Fusion 2023-01-04

The m/n = 2/1 resonant vacuum error field (EF) in the EAST tokamak experiments, inferred from compass coil current amplitude and phase scan for mode locking, was found to depend on parity between upper lower rows of EF correction (EFC) coils (Wang et al 2016 Nucl. Fusion 56 066011). Here m n are poloidal toroidal harmonic numbers a torus, respectively. This experimental observation implies that results cannot be simply interpreted as reflecting true intrinsic EF. work aims at understanding...

10.1088/1361-6587/aab30f article EN Plasma Physics and Controlled Fusion 2018-03-01

Abstract Systematic toroidal modeling of the plasma response to n = 1–4 ( is mode number) resonant magnetic perturbation (RMP) field carried out in order understand plasma-shaping effect on controlling type-I edge-localized modes (ELMs) tokamak experiments. Considered are large variations elongation and triangularity at a fixed edge safety factor q , for limiter plasmas with both single-null (SN) double-null (DN) divertor-like boundary shapes. Numerical results assuming conformal 3D RMP...

10.1088/1741-4326/ac2636 article EN Nuclear Fusion 2021-09-13

Fresh produce are typically washed in a flume washer to detach and inactivate bacteria from surface the typical sanitizer employed by processors is chlorinated water. The distribution of free chlorine was simulated validated using experimental data. influences injection velocity presence soluble organic matter on spatial were investigated. At lower velocity, more concentrated near bottom compared middle flume. depleted data concentrations reasonable agreement with numerically predicted under...

10.1016/j.lwt.2021.112888 article EN cc-by-nc-nd LWT 2021-12-04

Modification of the external tearing index, Δext′, by magnetic feedback is analytically investigated for purpose controlling resistive plasma wall mode (RP-RWM). The matching method pursued deriving expressions close-loop Δext′ and linking it to counterpart from inner layer. Various coil configurations are found generally reduce stabilize RWM, with either proportional or derivative control. Feedback modification be independent layer interchange index DR, confirming that action primarily...

10.1063/5.0019233 article EN publisher-specific-oa Physics of Plasmas 2021-01-01

Toroidal modeling of plasma response to the resonant magnetic perturbation (RMP) fields, with n = 2 and 3 configurations (n is toroidal mode number), carried out for DIII-D discharge utilizing MARS-F code. In particular, relative phase (coil phase) between lower upper rows I-coil currents scanned from −180° 180°, while computing response. Both resistive rotating ideal static models have been employed predict optimum coil typical safety factor (q95) values that are within windows suppressing...

10.1063/5.0011027 article EN cc-by AIP Advances 2020-05-01

The polarization of the π component Zeeman split Li2P–2S transition allows a direct spectroscopic measurement local magnetic pitch angle. Li atoms are injected radially into TEXT as 95 keV beam and intensity transmitted is detected. A polarization-modulated, cavity-dumped dye laser, tuned resonance with line, collinearly beam. Laser excitation results in an enhanced attenuation. Time-resolved detection determination Details system recent measurements will be discussed.

10.1063/1.1141779 article EN Review of Scientific Instruments 1990-10-01

Abstract Magnetic feedback stabilization of the tearing mode (TM) is numerically investigated, utilizing MARS-F code (Liu et al 2000 Phys. Plasmas 7 3681) for toroidal tokamak equilibria. With control coil configurations assumed in this study, magnetic partially or fully stabilizes TM, with either vanishing finite equilibrium pressure. The best achieved by combination internal active coils and poloidal sensors. external indices are evaluated close-loop system, based on computed eigenvalue...

10.1088/1361-6587/ac0110 article EN Plasma Physics and Controlled Fusion 2021-05-13
Coming Soon ...