A5084057826- Fusion materials and technologies
- Magnetic confinement fusion research
- Laser-Plasma Interactions and Diagnostics
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
Anhui Normal University
2023
Hefei University
2023
Hefei Institutes of Physical Science
2021
Institute of Plasma Physics
2020-2021
Chinese Academy of Sciences
2020-2021
University of Science and Technology of China
2020-2021
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 Small perturbations and strong impurity exhaust capability associated with the small grassy ELMs render grassy-ELM regime a suitable candidate for achieving steady-state H-mode operation radiative divertor, especially in metal-wall device, such as Experimental Advanced Superconducting Tokamak (EAST). As degradation of pedestal performance excessive divertor seeding or accumulation tends to be accompanied significantly increased radiation near X point, feedback control absolute...
One of the critical challenges for long pulse operation ITER and future fusion reactors is excessively high heat particle fluxes on divertor targets. The detachment offers an effective way control steady state flux erosion at target. Dedicated experiments have been systematically performed both H-mode L-mode plasmas EAST with ITER-like W in last two years to further advance physics understanding. identified by rollover peak near strike point during density ramping up, which correlates...
Simultaneous control of the large edge localized modes (ELMs) and divertor heat fluxes in a metal wall environment is critical issue for steady-state operation tokamak fusion reactors. Here we report sustained ELM suppression scenario achieved EAST compatible with radiative using different seeding impurity species over wide range conditions. A low-n mode appears, as manifested by oscillations radiation front near X-point. This appears to drive strong particle transport tungsten exhaust,...
Abstract One of the key challenges for future fusion research is to mitigate high steady-state heat load on divertor target plates, and detachment offers a promising solution. The Experimental Advanced Superconducting Tokamak (EAST) has developed several feedback control methods detachment. However, when an off-normal event momentarily disturbs main plasma, impurity seeding may still be conducted by these detachment, which probably drives plasma further away from its stable equilibrium or...
Abstract Doubly peaked density distribution is expected not only to affect the plasma-wetted area at divertor plates, but also correlate with upstream profile and hence characteristics of magnetohydrodynamic activities in tokamak plasmas (Wang et al 2020 Phys. Rev. Lett. 124 195002). Clarifying its origin important understand compatibility between power/particle exhausts high-performance core required by present-day future devices. In this paper, we analyze double-peak appearing modeling...
Research was originally carried out to evaluate plasma performance with a tungsten (W) divertor on EAST using the bundled charge state model by coupled multi-fluid and kinetic neutral code SOLPS-ITER. This work focuses comparisons of several models W all ion in low high recycling operational regimes. It is found that have pronounced effect reduction computational time computer memory provide an improved marked speed factor more than five. In regime, compared full model, differences...
Abstract Upstream density profiles in the scrape-off layer (SOL) have been examined low-confinement mode (L-mode) and high-confinement (H-mode) plasmas EAST superconducting tokamak. A weak shoulder forms near SOL region upper single-null configurations when neutral pressure measured at lower divertor exceeds a threshold value of 2 × 10 −2 Pa L-mode plasmas. When is below this threshold, absent sidebands hybrid waves associated with parametric instabilities are reduced. Active detachment...
Simultaneous control of transient heat load induced by large-amplitude edge-localized modes (ELMs) and steady-state on divertor targets under metal wall environment is crucial for operation future tokamak fusion reactors, such as ITER the China Fusion Engineering Test Reactor (CFETR). In recent experiments, sustained partial energy detachment without confinement degradation has been achieved in Experimental Advanced Superconducting Tokamak (EAST) high-performance grassy-ELM H-mode with q95 ~...
Abstract A series of H-mode discharges have been conducted in the EAST tokamak to study effect divertor closure on neutral distribution and edge plasmas by scanning location outer strike point. When point moves close corner within ∼ <?CDATA $4.5\,{\text{cm}}$?> <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mn>4.5</mml:mn> <mml:mrow> <mml:mtext>cm</mml:mtext> </mml:mrow> </mml:math> , gauge upper sub-divertor shows that pressure increases, reciprocating...
A series of L-mode discharges have been conducted in the new ‘corner slot’ divertor on Experimental Advanced Superconducting Tokamak (EAST) to study plasma behavior through sweeping strike point. The control system controls point from horizontal target vertical poloidal field coils, with keeping main stability. surface temperature cools down as moves away, indicating that mitigates heat load. To avoid negative effect probe tip damage, a method based is used get normalized profile and decay...
Abstract The new lower tungsten divertor of EAST uses a right-angle shape consisted by horizontal and vertical targets, which has the capacity increasing closure. strike point (SP) sweeping experiment is carried out to (1) avoid long-term deposition particle heat flux at same location, thus protecting target, (2) study dependence power control capability on SP location. energy densities target depends strongly their decay width. Therefore, it important know how location influences outer (OT)...
Abstract Low-Z impurity injection is frequently used for divertor detachment operations in current tokamaks; however, the effects on main plasma are yet to be fully understood. In this paper, ion temperature gradient (ITG) modes tokamak edge plasmas investigated based Euler matrix eigenvalue method. The eigen-equations with multiple species established from fundamental gyrokinetic theory, which each treated equally. A novel and efficient gyro-kinetic code developed numerical study, code’s...
Abstract Low-frequency drift-wave instabilities play a crucial role in the radial transport of present-day tokamaks, and trapped electron collisions can significantly influence these instabilities. In this paper, effects on are investigated based linear gyro-kinetic simulations. The basic numerical techniques including dispersion relation integral method orthogonal basis function expansion presented detail with necessary benchmark work. results demonstrate that medium gradients, increase...
Abstract One of the key challenges facing magnetic fusion research is to demonstrate compatibility between high confinement and radiative divertors in long-pulse discharges with a metal wall environment. A small edge-localized-mode (ELM) high-confinement plasma an energy factor H 98 ∼ 1.1 Greenwald density fraction f GW 0.65 maintained for 26 s obtained upgraded lower divertor Experimental Advanced Superconducting Tokamak (EAST), periodical detachment achieved through active control neon...
Abstract A major challenge facing the steady-state operation of tokamak fusion reactors is to develop a viable divertor solution with order-of-magnitude increase in power handling capability as compared present experience. recently developed concept for this end has been tested on EAST through combining effects closed corner and E × B drifts. The drifts move particles towards outer area scrape-off layer ∇ directed away from divertor, which can significantly enhance particle concentration...