A5034750228- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Nuclear Materials and Properties
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Laser-Plasma Interactions and Diagnostics
- Ionosphere and magnetosphere dynamics
- Physics of Superconductivity and Magnetism
- Evacuation and Crowd Dynamics
- Water Systems and Optimization
- Structural Analysis and Optimization
- Electromagnetic Launch and Propulsion Technology
- Advanced materials and composites
- Magnetic Field Sensors Techniques
- Flow Measurement and Analysis
- Vibration and Dynamic Analysis
- Nuclear Engineering Thermal-Hydraulics
- Erosion and Abrasive Machining
- High-Temperature Coating Behaviors
- Internet of Things and Social Network Interactions
- Target Tracking and Data Fusion in Sensor Networks
- Heat transfer and supercritical fluids
Hefei Institutes of Physical Science
2022-2024
Institute of Plasma Physics
2014-2024
Chinese Academy of Sciences
2018-2024
University of Science and Technology of China
2024
Hefei First People's Hospital
2023
Abstract A new lower tungsten divertor has been developed and installed in the EAST superconducting tokamak to replace previous graphite with power handling capability increasing from <2 MW m −2 ∼10 , aiming at achieving long-pulse H-mode operations a full metal wall environment steady-state heat flux of . concept, ‘corner slot’ (CS) divertor, employed. By using effect’, strongly dissipative local buildup high neutral pressure near corner can be achieved, so that stable detachment...
Abstract Tungsten (W) is one of the most promising plasma-facing materials for future fusion devices. Although its melting point highest among all metals, it still has great risk under extremely high plasma heat fluxes, which a big concern ITER and reactors. Actively cooled W components (PFCs) with both monoblocks flat-type structure have been successfully installed in lower divertor EAST tokamak since 2021, provide good opportunity direct comparison damage mechanism two types PFCs. Various...
Abstract Transient heat flux up to thousands of MW/m2 in a short pulse (~ms) tokamak poses great challenge on plasma facing components (PFCs), major concern for ITER. Despite numerous high tests, the analysis situ transient flux-induced damage PFCs remains necessary. Such damages, including melting and cracking tungsten (W) PFCs, are notably observed divertor (dome baffle plates) limiter EAST. These damages identified as being induced by runaway electron loss during disruption early startup...
The divertor target components for the Chinese fusion engineering test reactor (CFETR) and future experimental advanced superconducting tokamak (EAST) need to remove a heat flux of up ∼20 MW m−2. In view such high removal requirement, this study proposes conceptual design flat-tile based on explosive welding brazing technology. Rectangular water-cooled channels with special thermal transfer structure (TTS) are designed in sink improve target's performance (HTP). parametric optimization...
Abstract Compact torus (CT) injection is a highly promising technique for the central fueling of future reactor-grade fusion devices since it features extremely high velocity and relatively plasma mass. Recently, CT injector EAST tokamak, EAST-CTI, was developed platform-tested. In first round experiments conducted with low parameter settings, maximum mass were 150 km·s −1 90 μ g, respectively. However, parameters obtained by EAST-CTI still very far from requirements device such as that has...
Abstract A novel electromagnetic probe array (EMPA) diagnostic, which consists of a magnetic and an electrostatic array, has recently been developed on EAST. The EMPA is fixed near the first wall at horizontal port P. 24 identical probes, each them capable measuring toroidal, poloidal radial fluctuations simultaneously, providing additional toroidal fluctuation measurements compared with regular probes With higher sampling rate self-resonant frequency, can provide frequency measurements....
Abstract In this paper, a compact torus (CT) injector system is designed for experimental advanced superconducting tokamak (EAST). The consists of coaxial electrode and four pulsed power systems generates self-organized CT with high density velocity. addition, the performance EAST-CTI evaluated using series diagnostics systems. results show that velocity, electron density, number particles are 56.0 km/s, 8.73 × 10 20 m -3 , 2.4 18 respectively. detailed description presented in paper.
A record duration of a 310 s H-mode plasma (H98y2 ∼ 1.3, ne/nGW 0.7, fBS &gt; 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...
Abrasive water jet is a promising method for processing rolled tungsten plates, which are considered the most plasma-facing material in fusion devices. To investigate erosion of due to abrasive jet, we conducted tests and numerical simulations. We examined morphological characteristics damage. An model was developed by coupling smoothed-particle hydrodynamics with finite-element simulate erosion. The mechanism behind damage analyzed. Our findings reveal that as depth increases, kinetic...
Abstract Compact torus (CT) injection is one of the most promising methods for central fuelling next-generation reactor-grade fusion devices due to its high density, velocity, and self-contained magnetised structure. A newly compact injector (CTI) device in Keda Torus eXperiment (KTX), named KTX-CTI, was successfully developed tested at University Science Technology China. In this study, first, we briefly introduce basic principles structure then, present an accurate circuit model that...
The divertor is the key plasma-facing components of tokamak device for exhausting heat load. uneven distribution load inherent characteristic divertor, it may be caused by geometric configuration and physical experiments. improvement assembly accuracy can alleviate So, analysis important content in upgrading Experimental Advanced Superconducting Tokamak (EAST) lower divertor. According to experiments modeling scrape-off layer, parent requirements profile <inline-formula...
China Fusion Engineering Test Reactor (CFETR) is an experimental device of magnetic confinement tokamak fusion reactor that being designed and developed in China, the divertor its important plasma-facing components (PFCs). The basic function to remove heat impurities. For CFETR carries out research on high power, design faces greater challenges: higher requirements for removal capacity, mechanical properties, low activation under strong neutron flux radiation, remote handling (RH)...
Abstract Recently, a compact torus injection (CTI) system was developed for central fueling on experimental advanced superconducting tokamak (EAST). As impurity generated by the interaction between CTI plasma and electrode material can dilute fuel particle, it is important to measure content in evaluate effect of before application EAST. A vacuum-ultraviolet (VUV) spectrometer that utilizes concave holographic grating with 1200 groove mm -1 installed EAST-CTI emission measurement transport...
Abstract A type of actively cooled W/Cu flat-type component with high heat exhaust capacity was installed as limiter during the EAST spring plasma campaign in 2022, aiming to support long pulse operation. Unfortunately, severe melting phenomena obvious droplets ejection repeatedly monitored by CCD and IR cameras, which not only induced failure but also seriously influenced The temperature around midplane main is identified be closely connected ICRF fast ions loss. Indeed, surface too ignore....
The steady state with duty cycle time 0.3-0.5 of Chinese fusion engineering testing reactor (CFETR) is a big challenge. To realize this goal, the divertor should be reliable. At preconceptual phase CFETR design, reliability engaged to determine how reliable and much level be. plasma facing components (PFCs), base plate, support frame have been considered during analysis for modules. relation between system its modules has analyzed. relations steady-state operation studied in paper. How...
A general-purpose high payload in-vessel remote handling (RH) system is required for fusion reactors such as China engineering test reactor (CFETR). One of the key technical challenges to implement a RH its rotary joints that should be able handle various components having both and small requiring precision within constrained space. In addition, it needs withstand seismic loads, radiation, get low contamination during maintenance operation, easily decontaminated. This article presents design...
Abstract In the EAST experiment, extent of damages divertor is different in toroidal direction. One reasons uneven heat load distribution, which may be caused by geometric errors surface. The lower cooled 8 active water-cooling branches, and calorimetric system estimates its distribution measuring cooling water temperature difference flow rate. non-uniformity branches -3.5% ∼ 4.5%. Besides, using Leica AT960 / AT401 laser tracker to measure profile deviation upgraded divertor, accuracy -15%...
In order to better study the magnetic fluctuations in high-field side of EAST tokamak, a new probe array (HFS-MPA) has been developed on recently. The HFS-MPA consists 12 identical three-dimensional (3D) probes, which are mounted HFS wall with carefully designed arrangement. probes bring additional toroidal fluctuation measurements comparing regular can only provide poloidal and radial measurements. And upper limits frequency mode number (n) have improved i.e., 650 kHz vs 100 n=23 n=1....