A5042128905- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- HVDC Systems and Fault Protection
- Ionosphere and magnetosphere dynamics
- Plasma Diagnostics and Applications
- Vacuum and Plasma Arcs
- Spectroscopy and Chemometric Analyses
- Electromagnetic Launch and Propulsion Technology
- Optical Imaging and Spectroscopy Techniques
- Spectroscopy Techniques in Biomedical and Chemical Research
- Atomic and Subatomic Physics Research
- Particle Accelerators and Free-Electron Lasers
Institute of Plasma Physics
2010-2024
Chinese Academy of Sciences
2011-2024
Hefei Institutes of Physical Science
2022-2024
Shenzhen University
2023
University of Science and Technology of China
2016-2022
Princeton Plasma Physics Laboratory
2011
Princeton University
2011
Academia Sinica
1994
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...
Abstract A recent EAST experiment has successfully demonstrated long pulse steady-state high plasma performance scenario and core-edge integration since the last IAEA in 2018. discharge with a duration over 60 s β P ∼ 2.0, N 1.6, H 98y2 1.3 an internal transport barrier on electron temperature channel is obtained multi-RF power heating current drive. higher ( 1.8, p 1.3, n e / GW 0.75) of 20 achieved by using modulated neutral beam power, where several normalized parameters are close or even...
Abstract Recently, the first ever 100 s long, steady-state H-mode discharge with good control of impurities, core and edge MHD stabilities, heat exhaust was demonstrated in Experimental Advanced Superconducting Tokamak (EAST) using ITER-like (International Reactor) tungsten upper divertor. Using both radio frequency (RF) power neutral beam injection (NBI) heating, EAST has fully non-inductive scenarios an extension fusion performance at high density low rotation: β P ∼ 2.5, N 2.0, H 98,y2...
In this work, a purely data-driven discharge prediction model was developed and tested without integrating any data or results from simulations. The based on the experimental Experimental Advanced Superconducting Tokamak (EAST) campaign 2010-2020 discharges can predict actual plasma current $I_{p}$, normalized beta $\beta_{n}$, toroidal $\beta_{t}$, poloidal $\beta_{p}$, electron density $n_{e}$, store energy $W_{mhd}$, loop voltage $V_{loop}$, elongation at boundary $\kappa$, internal...
High-k turbulence (1 < kθρs 5) spectrograms have been directly measured in density modulation experiments of the EAST tokamak using collective Thomson scattering diagnostic system. Density-peaking is achieved Lower Hybrid Wave (LHW) experiments, revealing that broadband sensitive to power LHW and concomitant variation density-peaking. Additionally, contributions 2.45/4.6 GHz peaking differ when Neutral Beam Injection (NBI) on/off, displaying distinct responses low/high frequency...
Disruption database and disruption warning of the EAST tokamak had been established by a research group. The database, based on Structured Query Language (SQL), comprises 41 parameters, which include current quench characteristics, EFIT equilibrium kinetic halo currents, vertical motion. Presently most databases are plasma experiments non-superconducting devices. purposes to find characteristics statistics fully superconducting EAST, elucidate physics underlying disruptions, explore...
The paper outlines the design of Fusion-Fission Research Facility (FFRF) for study hybrid reactors with a unique fusion mission and pioneering merging fission physics technology accumulation engineering, physical, operational data future applications.The was developed in Institute Plasma Physics Chinese Academy Sciences (ASIPP) Princeton Laboratory (USA) participation.Parameters facility are R/a = 4/1m/m, I pl 5 MA, B tor 4-6 T, P DT 50-100 MW, 80-4000 1 m thick blanket.The FFRF will use as...
A record duration of a 310 s H-mode plasma (H98y2 ∼ 1.3, ne/nGW 0.7, fBS > 50%) has been recently achieved on experimental advanced superconducting tokamak (EAST) with metal walls, exploiting the device's improved long-pulse capabilities. The experiment demonstrates good control tungsten concentration, core/edge MHD stability, and particle heat exhaust an ITER-like divertor zero injected torque, establishing milestone path to steady-state high-performance scenarios in support ITER...
A high temperature superconductor (HTS) current feeder system is used as the transmission lines for EAST Tokamak. It consists of a pair 16 kA HTS Toroidal Field (TF) coils, 6 pairs 15 feeders Central Solenoid (CS) coils and Poloidal (PF) coils. The magnets are made Bi-2223/Ag-Au alloy tapes supplied by American Superconductor Corporation. Several methods have been quench detection in feeder. For investigated conditions, detecting resistance voltage shows best performance main method due to...
A central solenoid model coil (CSMC) is to verify the large-scalar superconducting manufacture technology for China Fusion Engineering Test Reactor (CFETR) in Institute of Plasma Physics, Chinese Academy Sciences (ASIPP). The CSMC composed Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn and NbTi hybrid magnet can reach 12 T maximum magnetic field. main manufacturing processes are developed verified by R&Ds mockup fabrication. For...
Abstract I-mode is a promising regime for future fusion reactors due to the high energy confinement and moderate particle confinement. However, effect of lithium, which has been widely applied recycling impurity control, on plasma still unclear. Recently, experiments real-time lithium powder injection have carried out in EAST Tokamak. It was found that performance can be improved by injection, strongly reduce electron turbulence (ET) then trigger ion (IT). Four different regimes identified...
The DC vacuum circuit breaker plays an important role in the quench protection system of Comprehensive Research Facility for Fusion Technology (CRAFT) project. study operating characteristics breakers can effectively improve breaking reliability. This article introduces design and basis series double break CRAFT system. It adopts electromagnetic repulsion driving method to ensure rapid action mechanism synchronization action. A magnetic shielding setting is proposed through simulation...
The DC mechanical switch is connected in series with the superconducting magnet quench protection system. As main that carries current for a long time, temperature of its conductive unit, especially contact part, inevitably increases significantly during operation. It necessary to design water-cooled structure control rise. This article introduces structural unit Comprehensive Research Facility Fusion Technology system and uses combination theoretical calculation, thermal-electrical coupling...
A new method is used to diagnose plasma density space-profiles that involves phase conjugate reflection of four-wave mixing. Theoretical calculations for parameters in the HT-6M tokamak show two pump-wave beams (HCN laser), with a power 1 W together signal beam (D<sub>2</sub>O or CH<sub>3</sub>F laser) 0.1 W, can create 0.43 mW where cross section all external cm<sup>2</sup>. This means reflective ratio mixing orders larger than laser superheating scatter. The lower laser, therefore, be plasmas.