A5036023894- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Plasma Diagnostics and Applications
- Thermography and Photoacoustic Techniques
- Optical Systems and Laser Technology
- Advanced optical system design
- Plant Pathogens and Fungal Diseases
- Infrared Target Detection Methodologies
- CCD and CMOS Imaging Sensors
- Adaptive optics and wavefront sensing
- Radiation Detection and Scintillator Technologies
- Nuclear Engineering Thermal-Hydraulics
- Calibration and Measurement Techniques
- Nuclear reactor physics and engineering
- Particle Detector Development and Performance
University of Tennessee at Knoxville
2017-2024
University of Tennessee System
2024
Princeton Plasma Physics Laboratory
2021
Chinese Academy of Sciences
2012-2020
Institute of Plasma Physics
2010-2020
Knoxville College
2019
Hefei Institutes of Physical Science
2017
University of Saskatchewan
2015
Tsinghua University
2015
The Ohio State University
2012
Abstract The objectives of NSTX-U research are to reinforce the advantages STs while addressing challenges. To extend confinement physics low- A , high beta plasmas lower collisionality levels, understanding transport mechanisms that set performance and pedestal profiles is being advanced through gyrokinetic simulations, reduced model development, comparison NSTX experiment, as well improved simulation RF heating. develop stable non-inductive scenarios needed for steady-state operation,...
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...
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 The effects of edge-localized modes (ELMs) on divertor particle and heat fluxes were investigated for the first time in Experimental Advanced Superconducting Tokamak (EAST). experiments carried out with both double null lower single configurations, comparisons made between H-mode plasmas hybrid current drive (LHCD) those combined ion cyclotron resonance heating (ICRH). flux profiles during ELMs obtained from Langmuir triple-probe arrays embedded target plates. And isolated chosen...
ADVERTISEMENT RETURN TO ISSUEPREVArticleNEXTThe Cytotoxic Principles of Solanum incanumChun-Nan Lin, Chai-Ming Lu, Ming-Kung Cheng, Kim-Hong Gan, and Shen-Jeu WonCite this: J. Nat. Prod. 1990, 53, 2, 513–516Publication Date (Print):March 1, 1990Publication History Published online1 July 2004Published inissue 1 March 1990https://pubs.acs.org/doi/10.1021/np50068a041https://doi.org/10.1021/np50068a041research-articleACS PublicationsRequest reuse permissionsArticle...
The Experimental Advanced Superconducting Tokamak (EAST) has recently achieved a variety of H-mode regimes with different edge-localized mode (ELM) dynamics, including type-I ELMs, compound which are manifested by the onset large spike followed sequence small spikes on Dα emissions, usual type-III and very ELMs. This newly observed ELMy appears to be similar type-II H-mode, higher repetition frequency (∼1 kHz) lower amplitude than exhibiting an intermediate confinement level between H-modes....
Dedicated experiments for the scaling of divertor power footprint width have been performed in ITER-relevant radio-frequency (RF)-heated H-mode scheme under lower single null, double null and upper configurations Experimental Advanced Superconducting Tokamak (EAST) lithium wall coating conditioning. A strong inverse edge localized mode (ELM)-averaged fall-off with plasma current (equivalently poloidal field) has demonstrated attached type-III ELMy as by various heat flux diagnostics...
A long-pulse high confinement plasma regime known as H-mode is achieved in the Experimental Advanced Superconducting Tokamak (EAST) with a record duration over 30 s, sustained by Lower Hybrid wave Current Drive (LHCD) advanced lithium wall conditioning and divertor pumping. This characterized co-existence of small Magneto-Hydrodynamic (MHD) instability, i.e., Edge Localized Modes (ELMs) continuous quasi-coherent MHD mode at edge. We find that LHCD provides an intrinsic boundary control for...
A numerical model using field line tracing for modeling of three-dimensional magnetic topology under resonant perturbations (RMPs) on experimental advanced superconducting tokamak (EAST) is presented. The topological structure calculated in the vacuum paradigm. result predicts that possible strike point splitting a plasma-facing component and lobes-like boundary are observable diagnostics at different locations. It shown with dominant spectrum can induce large footprint effect as well wide...
The infrared (IR) thermography diagnostic has recently been upgraded to achieve real-time temperature measurement and feedback capability in the experimental advanced superconducting tokamak (EAST). A new control data acquisition program for IR camera is developed with online calibration compensation. Reflective memory (RFM) configured system transmission plasma (PCS). Based on diagnostic, detachment achieved first time EAST active feedback. divertor impurity seeding used inject a sequence...
The divertor heat flux footprint in tokamaks is often observed to be non-axisymmetric due intrinsic error fields, applied 3D magnetic fields or during transients such as edge localized modes. Typically, only 1D radial profiles are analyzed; however, analysis of the full 2D measurements provides opportunities study asymmetric nature deposited flux. To accomplish this an improved Fourier method has been successfully a conduction solver (TACO) determine distribution at lower surface National...
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...
Recent experiments from the Experimental Advanced Superconducting Tokamak (EAST) show that lower hybrid waves (LHWs) can profoundly change magnetic topology by inducing helical current filaments flowing along field lines in scrape-off layer. Here, it is investigated for first time how these perturbations caused LHWs affect edge plasma transport utilizing three-dimensional Monte Carlo code EMC3-EIRENE, both double-null and single-null configurations. The 3D structure reflected properties, due...
Abstract The mission of the low aspect ratio spherical tokamak NSTX-U is to advance physics basis and technical solutions required for optimizing configuration next-step steady-state fusion devices. will ultimately operate at up 2 MA plasma current 1 T toroidal field on axis 5 s, has available 15 MW neutral beam injection power different tangency radii 6 high harmonic fast wave heating. With these capabilities develop understanding control tools ramp-up sustain performance fully...
The lower hybrid wave (LHW) heating experiments at the Experimental Advanced Superconducting Tokamak (EAST) show a wide range of similarities to effects known from applied resonant magnetic perturbations (RMPs) by in-vessel or external perturbation coils. These observations suggest current flow understood be along scrape-off layer (SOL) field lines; here called helical filaments (HCFs). For better understanding experimental observations, model incorporate HCFs in topology has been developed....
Divertor heat patterns induced by Lower Hybrid Current Drive (LHCD) L-mode plasmas are investigated using an infra-red (IR) camera system on Experimental Advanced Superconducting Tokamak (EAST). A two-dimensional finite element analysis code DFlux is used to compute flux along the poloidal divertor target and corresponding quantities. Outside Origin Strike Zone (OSZ), a Second Peak Heat Flux (SPHF) zone, where even stronger than that at OSZ, appears lower-outer (LO) plates with LHCD...
Dedicated experiments focusing on the influence of lower hybrid waves (LHWs) edge-localized modes (ELMs) were first performed during 2012 experimental campaign EAST, via modulating input power LHWs in high-confinement-mode (H-mode) plasma mainly sustained by ion cyclotron resonant heating. Natural ELMs are effectively mitigated (ELM frequency increases, while its intensity decreases dramatically) as LHW is applied, observed over a fairly wide range current or edge safety factor. By scanning...
Significant progress on both L- and H-mode long-pulse discharges has been made recently in Experimental Advanced Superconducting Tokamak (EAST) with lower hybrid current drive (LHCD) [J. Li et al., Nature Phys. 9, 817 (2013) And B. N. Wan Nucl. Fusion 53, 104006 (2013).]. In this paper, LHCD experiments at high density L-mode plasmas have investigated order to explore possible methods of improving (CD) efficiency, thus extend the operational space performance plasma regime. It is observed...
Edge-localized modes (ELMs) are the focus of tokamak edge physics studies because large heat loads associated with ELMs have great impact on divertor design future reactor-grade tokamaks such as ITER. In experimental advanced superconducting (EAST), first ELMy high confinement (H-modes) were obtained 1 MW lower hybrid wave power in conjunction wall conditioning by lithium (Li) evaporation and real-time Li powder injection. The EAST at this heating mostly type-III ELMs. They observed close to...
Disruption of the plasma is one most dangerous instabilities in tokamak. During disruption, thermal energy lost, which causes damages to facing components. Infrared (IR) camera an effective tool detect temperature distribution on first wall, and deposited wall can be calculated from surface profile measured by IR camera. This paper concentrates characteristics heat flux onto under different disruptions, including minor disruption vertical displacement events (VDE) disruption. Several...